ML12156A343
| ML12156A343 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/20/2012 |
| From: | Kelly Clayton Operations Branch IV |
| To: | Omaha Public Power District |
| References | |
| 50-285/12-004 | |
| Download: ML12156A343 (216) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Station Date of Examination: April 16, 2012 Examination Level: RO Operating Test Number: 2012-01 Administrative Topic Type Describe activity to be performed (see Note) Code*
Create a 1/M plot to estimate when criticality will be reached. (Per OP-2A, Attachment 2, 2A)
RA1: Conduct of Operations N, R K/A 2.1.23 Ability to perform specific and integrated plant procedures during all modes of plant operation (CFR: 41.10, 45.2, 45.6)
RO IR: 4.3 Quadrant Power Tilt Calculation with Excore detectors RA2: Conduct of Operations operable and ERF inoperable per OI-NI-1 N, R K/A 2.1.20 Ability to interpret and execute procedure steps (CFR: 41.10, 45.12)
RO IR: 4.6 Determine tagout/clearance requirements to remove a HPSI pump from service.
RA3: Equipment Control N, R K/A 2.2.13 Knowledge of tagging and clearance procedures (CFR: 41.10, 45.13)
RO IR: 4.1 Perform a stay time calculation.
RA4: Radiation Control N, R K/A 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions (CFR: 41.14, 45.10)
RO IR: 3.5 Emergency Procedures/Plan N/A 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 Station Date of Examination: April 16, 2012 Examination Level: SRO Operating Test Number: 2012-01 Administrative Topic Type Describe activity to be performed (see Note) Code*
Perform a spent fuel pool demineralized water makeup calculation per OI-SFP-2 Appendix 1.
SA1: Conduct of Operations N, R K/A 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
(CFR: 43.6, 45.6)
SRO IR: 4.6 Quadrant Power Tilt Calculation with Excore detectors operable and ERF inoperable per OI-NI-1 SA2: Conduct of Operations N, R K/A 2.1.20 Ability to interpret and execute procedure (same as RA2) steps (CFR: 43.5, 45.12)
SRO IR: 4.6 Review a tagging/clearance for removal of a HPSI pump from service.
SA3: Equipment Control N, R K/A 2.2.13 Knowledge of tagging and clearance procedures (CFR: 45.13)
SRO IR: 4.3 Determine whether to install shielding based on given dose rates and work times.
SA4: Radiation Control K/A 2.3.12 Knowledge of radiological safety principles N, R pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 45.9, 45.10)
SRO IR: 3.7 Determine Emergency Action Level for a given emergency.
SA5: Emergency K/A 2.4.38 Ability to take actions called for in the facility N, R emergency plan, including supporting or acting as Procedures/Plan emergency coordinator if required. (CFR: 43.5, 45.11)
SRO IR: 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 Station Date of Examination: April 16, 2012 Exam Level: RO Operating Test No.: 2012-01 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: Swap pressurizer pressure mode from manual to automatic, N, A, S 3 followed by spurious actuation of PORV (block valve not operable)
S-2: Engineered Safeguards Actuation Verification N, EN, A, S 2 S-3: Place a containment cooling unit in service D, S 5 S-4: Place shutdown cooling in service. N, L, S 4P S-5: Maintain S/G water levels during startup using AFW. N, A, L, S 4S S-6: Valve stroke time testing of CCW valves HCV-401C/D N, S 8 S-7: Dilute to achieve desired boron concentration for desired critical N, A, L, S 1 rod height (dilution continues until stopped)
S-8: Transfer 4160V loads onto 345kV bus per AOP-32 N, S 6 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1: Respond to a steam bound AFW pump D, E 4S P-2: Rack in GE Automatic 480V breaker N 6 P-3: Waste Gas Transfer from the Vent Header to the Gas Decay D, A, R 9 Tank
@ 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 Station Date of Examination: April 16, 2012 Exam Level: SRO-I Operating Test No.: 2012-01 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: Swap pressurizer pressure mode from manual to automatic, N, A, S 3 followed by spurious actuation of PORV (block valve not operable)
S-2: Engineered Safeguards Actuation Verification N, EN, A, S 2 S-3: Place a containment cooling unit in service D, S 5 S-5: Maintain S/G water levels during startup using AFW. N, A, L, S 4S S-6: Valve stroke time testing of CCW valves HCV-401C/D N, S 8 S-7: Dilute to achieve desired boron concentration for desired critical N, A, L, S 1 rod height (dilution continues until stopped)
S-8: Transfer 4160V loads onto 345kV bus per AOP-32 N, S 6 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1: Respond to a steam bound AFW pump D, E 4S P-2: Rack in GE Automatic 480V breaker N, R 6 P-3: Waste Gas Transfer from the Vent Header to the Gas Decay D, A, R 9 Tank
@ 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 Station Date of Examination: April 16, 2012 Exam Level: SRO-U Operating Test No.: 2012-01 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: Swap pressurizer pressure mode from manual to automatic, N, A, S 3 followed by spurious actuation of PORV (block valve not operable)
S-2: Engineered Safeguards Actuation Verification N, EN, A, S 2 S-7: Dilute to achieve desired boron concentration for desired critical N, A, L, S 1 rod height (dilution continues until stopped)
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1: Respond to a steam bound AFW pump D, E 4S P-3: Waste Gas Transfer from the Vent Header to the Gas Decay D, A, R 9 Tank
@ 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 Operating Test Quality Checklist Form ES-301-3 Facilty: Fort Calhoun Station Date of Exam: April 16, 2012 Scenario Numbers: / / Operating Test No.: 2012-01 Initials
- 1. General Criteria a b* c#
- a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).
- b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
- c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1.a.)
- d. Overlap with the written examination and between different parts of the operating test is within acceptable limits.
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.
- 2. Walk-Through Criteria -- -- --
- a. Each JPM includes the following, as applicable:
- initial conditions
- initiating cues
- references and tools, including associated procedures
- reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee
- operationally important specific performance criteria that include:
- detailed expected actions with exact criteria and nomenclature
- system response and other examiner cues
- statements describing important observations to be made by the applicant
- criteria for successful completion of the task
- identification of critical steps and their associated performance standards
- restrictions on the sequence of steps, if applicable
- b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.
- 3. Simulator Criteria -- -- --
The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.
Printed Name / Signature Date
- a. Author ______________________________________________ __ _ ______________
- b. Facility Reviewer(*) ______________________________________________ __ _ ______________
- c. NRC Chief Examiner (#) ______________________________________________ __ _ ______________
- d. NRC Supervisor ______________________________________________ __ _ ______________
NOTE:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Fort Calhoun Station Date of Exam: April 16, 2012 Scenario Numbers: / / Operating Test No.: 2012-01 QUALITATIVE ATTRIBUTES Initials a b* c#
- 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.
- 2. The scenarios consist mostly of related events.
- 3. Each event description consists of
- the point in the scenario when it is to be initiated
- the malfunction(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew
- the expected operator actions (by shift position)
- the event termination point (if applicable)
- 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
- 5. The events are valid with regard to physics and thermodynamics.
- 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
- 7. If time compression techniques are used, the scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints.
Cues are given.
- 8. The simulator modeling is not altered.
- 9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
- 10. Every operator will be evaluated using at least one new or significantly modified scenario.
All other scenarios have been altered in accordance with Section D.5 of ES-301.
- 11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
- 12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
- 13. The level of difficulty is appropriate to support licensing decisions for each crew position.
Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --
- 1. Total malfunctions (5-8) 6/6/6/7
- 2. Malfunctions after EOP entry (1-2) 2/2/2/2
- 3. Abnormal events (2-4) 2/2/2/2
- 4. Major transients (1-2) 1/1/1/1
- 5. EOPs entered/requiring substantive actions (1-2) 2/2/2/2
- 6. EOP contingencies requiring substantive actions (0-2) 0/0/1/0
- 7. Critical tasks (2-3) 2/2/2/2
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Fort Calhoun Station Date of Exam: April 16, 2012 Operating Test No.: 2012-01 A E Scenarios P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I
M C S A B S A B S A B S A B L U A T R T O R T O R T O R T O M(*)
N Y O C P O C P O C P O C P R I U T P E
RX 1 1 1 R1 NOR 1,6 2 1 I/C 2,3,4 3,5,8, 7 4 9
MAJ 6 7 2 2 TS 0 0 RX 6 1 1 NOR 1 1 1 I/C 4,5, 2,4, 8 4 R2 7,8 5,9 MAJ 6 7 2 2 TS 0 0 RX 1 1 1 R3 NOR 1,6 2 1 I/C 2,3,4 3,5,8, 7 4 9
MAJ 6 7 2 2 TS 0 0 RX 6 1 1 R4 NOR 1 1 2 1 I/C 4,5, 2,4, 3,5,6 11 4 7,8 5,9 MAJ 6 7 8 3 2 TS 0 RX 6 1 1 R5 NOR 1 1 1 I/C 4,5, 2,4, 8 4 7,8 5,9 MAJ 6 7 2 2 TS 0 0
RX 1 1 2 1 I1 NOR 1 1,6 3 1 I/C 2,3,4 3,5,8, 2,9, 10 4 5,7,8 9 10 MAJ 6 7 8 3 2 TS 2,3, 3 2 5
RX 1 6 1 3 1 I2 NOR 1 1 2 1 I/C 2,3,4 2,3,4 2,3,5 15 4 5,8,9 6,9, 10 MAJ 6 7 8 3 2 TS 4,6,7 6 2 2,4,5 RX 1 6 2 1 I3 NOR 1 1 2 1 I/C 2,3,4 2,4, 3,5,6 11 4 5,7,8 5,9 MAJ 6 7 8 3 2 TS 2,3, 3 2 5
RX 1 1 2 1 I4 NOR 1,6 1 3 1 I/C 2,3,4 3,5,8, 2,3,5 10 4 9 6,9, 10 MAJ 6 7 8 3 2 TS 4,6,7 3 2 RX 6 1 2 1 I5 NOR 1 1 2 1 I/C 4,5, 2,3,4 2,9, 13 4 7,8 5,8,9 10 MAJ 6 7 8 3 2 TS 3 2 2,4,5 RX 1 6 2 0 U1 NOR 1 1 2 1 I/C 2,3,4 2,3,4 12 2 5,7,8 5,8,9 MAJ 6 7 2 1 TS 2,3, 6 2 5 2,4,5 RX 1 6 2 0 U2 NOR 1 1 2 1
I/C 2,3,4 2,3,4 12 2 5,7,8 5,8,9 MAJ 6 7 2 1 TS 2,3, 6 2 5 2,4,5 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 Station Date of Examination: April 16, 2012 Operating Test No.: 2012-01 APPLICANTS RO BOP SRO Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 2,3, 2,4, 2,4, 5,6, 3,5, 3,5, 2,3, 2,3, 2,3, Events and Conditions 4,6 5,7, 7,8, 7,8 7,8, 6 4,5, 4,5, 4,5, 9 9, 9 6,7, 6,7, 6,7, 10 8 8 8,9, 10 Comply With and 1,2, 2,4, 1,2, 1,4, 1,3, 1,3, 1,2, 1,2, 1,2, Use Procedures (1) 3,4, 5,6, 8,9, 5,6, 5,6, 5,6 3,4, 3,4, 3,4, 6 7,9 10 7,8 7,8, 5,6, 5,6, 5,6, 9 7,8 7,8, 7,8, 9 9, 10 Operate Control 1,2, 2,4, 1,2, 1,4, 1,3, 1,3, Boards (2) 3,4, 5,6, 8,9, 5,6, 5,6, 5,6 6 7,9 10 7,8 7,8, 9
Communicate 1,2, 2,4, 1,2, 1,4, 1,3, 1,3, 1,2, 1,2, 1,2, and Interact 3,4, 5,6, 4,7, 5,6, 5,6, 5,6 3,4, 3,4, 3,4, 6 7,9 8,9, 7,8 7,8, 5,6, 5,6, 5,6, 10 9 7,8 7,8, 7,8, 9 9, 10 Demonstrate 1,2, 1,2, 1,2, Supervisory Ability (3) 3,4, 3,4, 3,4, 5,6, 5,6, 5,6, 7,8 7,8, 7,8, 9 9, 10 Comply With and 2,3, 2,4, 4,6, Use Tech. Specs. (3) 5 5 7 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 JOB PERFORMANCE MEASURE JPM No: RA1 Rev 0 JPM
Title:
1/M Plot Location: Classroom Approximate Time: 15 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 2.1.23 Procedures: OP-2A Other (tech specs, etc): TDB-II Handout(s): OP-2A, Attachment 2A Blank 1/M Graph Paper Task List#: 776 Applicable Position(s): RO/SRO/STA Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 1/17/2012 Page 1 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 0 JPM
Title:
1/M Plot Operators Name:
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: 1/M Graph Paper Safety Considerations:
Comments: Task normally performed by STA but is also a RO task per the MTL Page 2 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 0 JPM
Title:
1/M Plot TASK STANDARD: Given count rate and CEA position data during a reactor startup, the Candidate will perform a 1/M plot in accordance with OP-2A, Attachment 2A and predict critical CEA position to be Group 4 between 45 and 75 inches.
INITIAL CONDITIONS: The plant is performing an initial reactor startup following an extended outage. I&C has connected scaler-timers to Wide Range Log Channels A and C.
CEAs have been withdrawn to Group 3 @ 90 inches.
An ECP has estimated the critical CEA position to be group 4 @ 85 INITIATING CUE:
The CRS has asked you to perform a 1/M plot to independently verify the STAs prediction of critical CEA position.
CEA WR Channel A WR Channel C Position counts per 100 counts per 100 seconds seconds Base 2112 1870 Group 1 @ 2341 1989 90 Group 2 @ 4402 3339 90 Group 3 @ 17602 12460 90 Page 3 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 0 JPM
Title:
1/M Plot Critical Steps shown in gray STEP ELEMENT STANDARD 1 Mark the ECP estimated critical Marked ECP as group D @
position on the 1/M graph 85
[ SAT ] [ UNSAT ]
2 Use TDB-II, Figure II.B.2.a to Marked ECP-1% position determine the ECP-1% to be group 2 between 90 and position and mark it on the 1/M 110 graph
[ SAT ] [ UNSAT ]
3 Determine Base Count Rate for Entered counts on Base WR Channels A Count Rate Data Sheet and calculated Base Count Rate as 21 cps +/- 1 cps
[ SAT ] [ UNSAT ]
4 Determine Base Count Rate for Entered counts on Base WR Channels C Count Rate Data Sheet and calculated Base Count Rate as 19 cps +/- 1 cps
[ SAT ] [ UNSAT ]
Page 4 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 0 JPM
Title:
1/M Plot STEP ELEMENT STANDARD 5 Determine 1/M for group 1 @ Entered count data on CEA 90 using WR Channel A Withdrawal Inverse Count Rate Data Sheet and calculated count rate to be 23 cps +/- 1 cps and 1/M to be 0.9
+/- 0.05. Placed Mark at 1/M versus % position.
Used last two points to estimate critical CEA position as beyond all CEAs withdrawn
[ SAT ] [ UNSAT ]
6 Determine 1/M for group 1 @ Entered count data on CEA 90 using WR Channel C Withdrawal Inverse Count Rate Data Sheet and calculated count rate to be 20 cps +/- 1 cps and 1/M to be 0.94
+/- 0.05. Placed Mark at 1/M versus % position.
Used last two points to estimate critical CEA position as beyond all CEAs withdrawn
[ SAT ] [ UNSAT ]
7 Determine 1/M for group 2 @ Entered count data on CEA 90 using WR Channel A Withdrawal Inverse Count Rate Data Sheet and calculated count rate to be 44 cps +/- 1 cps and 1/M to be 0.48
+/- 0.05. Placed Mark at 1/M versus % position.
Used last two points to estimate critical CEA position as beyond all CEAs withdrawn
[ SAT ] [ UNSAT ]
Page 5 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 0 JPM
Title:
1/M Plot STEP ELEMENT STANDARD 8 Determine 1/M for group 2 @ Entered count data on CEA 90 using WR Channel C Withdrawal Inverse Count Rate Data Sheet and calculated count rate to be 33 cps +/- 1 cps and 1/M to be 0.56
+/- 0.05. Placed Mark at 1/M versus % position.
Used last two points to estimate critical CEA position as beyond all CEAs withdrawn
[ SAT ] [ UNSAT ]
9 Determine 1/M for group 3 @ Entered count data on CEA 90 using WR Channel A Withdrawal Inverse Count Rate Data Sheet and calculated count rate to be 176 cps +/- 1 cps and 1/M to be 0.12
+/- 0.05. Placed Mark at 1/M versus % position.
[ SAT ] [ UNSAT ]
10 Determine 1/M for group 3 @ Entered count data on CEA 90 using WR Channel C Withdrawal Inverse Count Rate Data Sheet and calculated count rate to be 125 cps +/- 1 cps and 1/M to be 0.15
+/- 0.05. Placed Mark at 1/M versus % position.
[ SAT ] [ UNSAT ]
Page 6 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 0 JPM
Title:
1/M Plot STEP ELEMENT STANDARD 11 Determine critical CEA position Used last two points for each channel to estimate critical CEA position as group 4 between 45 and 75 inches.
Filled in answer sheet.
[ SAT ] [ UNSAT ]
Examiner Note: Ensure Candidate writes name on OP-2A, Attachment 2A.
Termination Criteria: Candidate has completed 1/M plot and estimated critical CEA position.
Page 7 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 INITIAL CONDITIONS: The plant is performing an initial reactor startup following an extended outage. I&C has connected scaler-timers to Wide Range Log Channels A and C.
CEAs have been withdrawn to Group 3 @ 90 inches.
An ECP has estimated the critical CEA position to be group 4 @ 85 INITIATING CUE: The CRS has asked you to perform a 1/M plot to independently verify the STAs prediction of critical CEA position.
CEA WR Channel A WR Channel C Position counts per 100 counts per 100 seconds seconds Base 2112 1870 Group 1 @ 2341 1989 90 Group 2 @ 4402 3339 90 Group 3 @ 17602 12460 90 Name: __________________________________________
Critical CEA Position using WR Channel A: Group ____ @ _________ inches Critical CEA Position using WR Channel C: Group ____ @ _________ inches Page 8 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 0 JPM
Title:
Perform a Quadrant Power Tilt Calculation Location: Classroom Approximate Time: 10 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 2.1.20 OI-NI-1, Revision 22 Handout(s): FC-171 Revision 11 Task List#:
Applicable Position(s): RO, SRO-I, SRO-U Time Critical: No Alternate Path: No JPM Prepared by: Date:
Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 0 JPM
Title:
Perform a Quadrant Power Tilt Calculation Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 0 JPM
Title:
Perform a Quadrant Power Tilt Calculation TASK Candidate performed a quadrant power tilt calculation STANDARD: per OI-NI-1 Attachment 4 Step 2. Candidate calculated QPTR to be 0.53% for the upper and 0.90% for the lower. Candidate determined that the calculated lower tilt exceeds the FC-171 value provided.
INITIAL ERF and GARDEL are inoperable. Excore detectors CONDITIONS: are available. I&C have measured and recorded voltage readings for the excore detectors per OI-NI-1, NUCLEAR INSTRUMENTATION SYSTEM, Attachment 4, Quadrant Power Tilt Calculation, Step 2.a.
FC-171, CORRECTED EXCORE AZIMUTHAL POWER TILT LIMITS, is attached.
INITIATING CUE: You have been directed to perform a quadrant power tilt calculation per OI-NI-1, Attachment 4, Step 2, using the information collected by I&C. Based on your calculations, determine if the indicated upper tilt and indicated lower tilt are within the values given in FC-171.
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 0 JPM
Title:
Perform a Quadrant Power Tilt Calculation Critical Steps shown in gray STEP ELEMENT STANDARD 1 (OI-NI-1, Calculate Upper Quadrant Candidate determines upper , Power Tilt quadrant power tilt to be Step 2.c) 0.53%:
(5.125 - 5.075) / (5.125 +
5.075) = 4.902 E-3 (5.1 - 5.05) / (5.1 + 5.05) =
4.9261 E-3 (4.902E-3)2 + (4.9261E-3)2 -
(1.48628
- 4.902E-3 *4.9261E-
- 3) = 1.2406 E-5 (1.2406E-5*2.2334)
- 100 =
0.526%
Range of 0.52%-0.535% is acceptable.
[ SAT ] [ UNSAT ]
2 (Step 2.d) Calculate Lower Quadrant Candidate determines lower Power Tilt quadrant power tilt to be 0.90%.
(4.925 - 4.85) / (4.925 + 4.85)
7.673 E-3 (4.9 - 4.875) / (4.9 + 4.875)
2.5575 E-3 (7.673E-3)2 + (2.5575E-3)2 -
(1.48628
- 7.673E-3
- 2.5575E-3) = 3.6245 E-5 (3.6245E-5
- 2.2334)
- 100 =
0.90%
Range of 0.89 - 0.91% is Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 0 JPM
Title:
Perform a Quadrant Power Tilt Calculation STEP ELEMENT STANDARD acceptable.
[ SAT ] [ UNSAT ]
3 (Step 2.e) Verify calculated tilt values are Candidate reviews FC-171 less than current FC-171 and determines that the lower indicated tilt values. tilt is greater than current FC-171 indicated tilt value.
[ SAT ] [ UNSAT ]
4
[ SAT ] [ UNSAT ]
Termination Criteria: Determined upper and lower quadrant power tilts and determined that the lower quadrant power tilts is not within current values specified in FC-171 Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 INITIAL ERF and GARDEL are inoperable. Excore detectors CONDITIONS: are available. I&C have measured and recorded voltage readings for the excore detectors per OI-NI-1, NUCLEAR INSTRUMENTATION SYSTEM, Attachment 4, Quadrant Power Tilt Calculation, Step 2.a.
FC-171, CORRECTED EXCORE AZIMUTHAL POWER TILT LIMITS, is attached.
INITIATING CUE: You have been directed to perform a quadrant power tilt calculation per OI-NI-1, Attachment 4, Step 2, using the information collected by I&C. Based on your calculations, determine if the indicated upper tilt and indicated lower tilt are within the values given in FC-171.
Upper Quadrant Power Tilt: %
Lower Quadrant Power Tilt: %
Values within current FC-171 values? ___________________
If not, which one(s) is (are) outside current FC-171 values? _____________
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 0 JPM
Title:
Prepare a Manual Clearance for Maintenance on AC-3C Location: Classroom Approximate Time: 20 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 2.2.13 RO IMP: 4.1 Knowledge of tagging and clearance procedures Procedures: SO-G-20A Other (tech specs, etc): P&IDs Handout(s): Three Blank SOMS forms per Candidate Task List#: 0075 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 2/1/2012 Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 0 JPM
Title:
Prepare a Manual Clearance for Maintenance on AC-3C Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 0 JPM
Title:
Prepare a Manual Clearance for Maintenance on AC-3C TASK STANDARD: The candidate prepared a Manual Clearance in accordance with SO-G-20A. All of the criteria for critical steps 2, 4, 5 and 6 were satisfied.
INITIAL CONDITIONS: Maintenance is being planned to replace the impellor on Component Cooling Pump, AC-3C.
SOMS is unavailable.
INITIATING CUE:
You are directed to prepare a manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A using the blank SOMS forms provided. The following information is required:
- Tag Type
- Equipment
- Placement Sequence
- Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Please write your name on each SOMS Form.
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 0 JPM
Title:
Prepare a Manual Clearance for Maintenance on AC-3C Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refer to applicable references: Candidate used reference
- SO-G-20A material as required.
- Plant Procedures
2 Prepare Clearance per SO-G- The Control Switch for AC-3C 20A using blank SOMS form must be first item in the sequence. It is placed in PTL and CAUTION tagged.
[ SAT ] [ UNSAT ]
3 The breaker 69 switch should be the second item in the sequence. It is placed in PTL with No Tag.
[ SAT ] [ UNSAT ]
4 The breaker must be in the sequence before any valves. It is racked out with a DANGER tag.
[ SAT ] [ UNSAT ]
5 AC-3Cs discharge valve, AC-108, and AC-3Cs suction valve, AC-106 must be the next 2 items in the sequence.
It is not required that AC-108 be listed before AC-106. Both of these valves must be danger tagged closed.
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 0 JPM
Title:
Prepare a Manual Clearance for Maintenance on AC-3C STEP ELEMENT STANDARD 6 AC-3Cs vent and drain valves, AC-359, AC-360 and AC-361 must be listed. They should be designated as CLOSED (per Shift Manager Discretion) with NO TAG
[ SAT ] [ UNSAT ]
Note: AC-163, AC-1116, AC-838 and AC-837 may also be listed but are not required.
Examiner Note: Ensure Candidate has written name on blank SOMS Forms Termination Criteria: The candidate has completed the clearance form with the information listed in the initiating Cue.
Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 INITIAL CONDITIONS: Maintenance is being planned to replace the impellor on Component Cooling Pump, AC-3C.
SOMS is unavailable.
INITIATING CUE: You are directed to prepare a manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A using the blank SOMS forms provided. The following information is required:
- Tag Type
- Equipment
- Placement Sequence
- Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Please write your name on each SOMS Form.
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4 Rev 0 JPM
Title:
Perform a stay time calculation Location: Classroom Approximate Time: 10 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 000000 2.3.7 (3.5/3.6): Ability to comply with radiation work permit requirements during normal or abnormal conditions SO-G-101, Radiation Worker Practices RP-202, Radiological Surveys Handout(s): RP-202 for Room 13 Task List#: N/A Applicable Position(s): RO Time Critical: No Alternate Path: No JPM Prepared by: Date:
Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4 Rev 0 JPM
Title:
Perform a stay time calculation Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4 Rev 0 JPM
Title:
Perform a stay time calculation TASK Candidate reviewed provided survey map and RWP STANDARD: information and calculated the allowable time at point B after working 30 minutes at point A to be 41 to 42 minutes.
INITIAL You will be entering the RCS to perform work. Your CONDITIONS: current year to date exposure is as follows:
- DDE - 825 mrem
- CEDE - 110 mrem
- Dose limit alarm - 75 mrem
- Dose rate alarm - 150 mrem/hr INITIATING CUE: You have been directed to enter Room 13 to perform work. The survey map for Room 13 is attached.
Assuming you first spend 30 minutes at point A on the attached survey map, determine how much time you could perform work at point B.
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4 Rev 0 JPM
Title:
Perform a stay time calculation Critical Steps shown in gray STEP ELEMENT STANDARD 1 Review survey map. Candidate reviewed survey map.
[ SAT ] [ UNSAT ]
2 Determine amount of time you Candidate determines from can perform work at point B information in initiating cue after spending 30 minutes that the dose limit is 65 mrem working at point A due to previous exposure (1000 mrem from FCS occupational sources - TEDE, TEDE= DDE + CDE = 825 +
110 = 935 mrem, therefore, 1000 - 935 = 65 mrem remaining exposure.)
Dose at point A = 20 mrem/hr
- 0.5hr = 10 mrem Remaining dose = 65 mrem -
10 mrem = 55 mrem Dose rate at point B = 80 mrem/hr Allowable time at point B =
55 mrem / 80 mrem/hr =
0.6875 hr
- 60 min/hr = 41.25 minutes. (41 to 42 minutes acceptable)
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4 Rev 0 JPM
Title:
Perform a stay time calculation Termination Criteria: Candidate has reviewed survey map and calculated an allowable stay time of 41 to 42 minutes for work at point B assuming 30 minutes of work at point A.
Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4 INITIAL You will be entering the RCS to perform work. Your CONDITIONS: current year to date exposure is as follows:
- DDE - 825 mrem
- CEDE - 110 mrem
- Dose limit alarm - 75 mrem Dose rate alarm - 150 mrem/hr INITIATING CUE: You have been directed to enter Room 13 to perform work. The survey map for Room 13 is attached.
Assuming you first spend 30 minutes at point A on the attached survey map, determine how much time you could perform work at point B.
Allowable stay time to perform work at point B: _____________
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 0 JPM
Title:
Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration Location: Classroom Approximate Time: minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): TDB-V.12 Rev. 10 TDB-VII Rev.15 Handout(s):
Task List#:
Applicable Position(s): SRO-I, SRO-U Time Critical: No Alternate Path: No JPM Prepared by: Date:
Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 0 JPM
Title:
Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration Operators Name:
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: None Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 0 JPM
Title:
Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration TASK Candidate calculates the amount of demineralized STANDARD: water and the amount of boric acid to add to the SIRWT to raise level from 185 inches to 195 inches while maintaining current SIRWT concentration. Candidate determines that 6117 gallons of water (6110-6125 gal) and 3883 gallons of boric acid (3875-3890) must be added.
INITIAL Current SIRWT level is 185 inches.
CONDITIONS: Current SIRWT boric acid concentration is 2247 ppm.
Both BASTs most recent sample indicate 3.31 %wt boric acid.
INITIATING CUE: You have been asked to determine that total number of gallons required to raise SIRWT level 10 inches to a final level of 195 inches. You have also been asked to determine that amount of demineralized water and the amount of water from the BASTs required to raise the SIRWT 10 inches while maintaining current SIRWT boric acid concentration. Calculations that are normally used for determining additions to the RCS can be used for the SIRWT without change.
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 0 JPM
Title:
Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration Critical Steps shown in gray STEP ELEMENT STANDARD 1 TDB-VII Determine total number of Candidate determines from the gallons required to raise graph that approximately SIRWT level from 185 inches 10,000 total gallons are to 195 inches. required to raise SIRWT level 10 inches (330,000 -320,000 =
10,000 gallons).
(9,950 - 10,050 gallons acceptable)
[ SAT ] [ UNSAT ]
2 TDB-V.12 Determine number of gallons of Gal water / gal acid =
demineralized water and (1748*3.31%) / 2247 ppm -1 =
number of gallons of water 1.575 from BASTs Gal water = 1.575
- gal acid Gal water + gal acid = 10,000 gal 2.575 gal acid = 10,000 gal Gal acid =3883.5 gal (3875-3890 gal)
Gal water = 10,000 - 3883.5 =
6116.5 gal (6110 - 6125 gal)
OR Gal water = 1.575
- 3883.5 =
6116.5 gal (6110-6125)
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 0 JPM
Title:
Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration STEP ELEMENT STANDARD
[ SAT ] [ UNSAT ]
Termination Criteria: Candidate has calculated that it will require 3884 (3875 - 3890) gallons of boric acid and 6117 (6110 -
6125) gallons of demineralized water for a total of 10,000 (9,950 -10,050) gallons to raise SIRWT level 10 inches while maintaining current SIRWT boric acid concentration.
Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 INITIAL Current SIRWT level is 185 inches.
CONDITIONS: Current SIRWT boric acid concentration is 2247 ppm.
Both BASTs most recent sample indicate 3.31 %wt boric acid.
INITIATING CUE: You have been asked to determine that total number of gallons required to raise SIRWT level 10 inches to a final level of 195 inches. You have also been asked to determine that amount of demineralized water and the amount of water from the BASTs required to raise the SIRWT 10 inches while maintaining current SIRWT boric acid concentration. Calculations that are normally used for determining additions to the RCS can be used for the SIRWT without change.
Total number of gallons to raise SIRWT level from 185 to 195 inches:
Amount of demineralized water: ___________________
Amount of borated water from the BASTs: ___________________
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 0 JPM
Title:
Review a Manual Clearance for Maintenance on AC-3C Location: Classroom Approximate Time: 20 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 2.2.13 RO IMP: 4.1 Knowledge of tagging and clearance procedures Procedures: SO-G-20A Other (tech specs, etc): P&IDs Handout(s): Filled out SOMS Forms Task List#: 0075 Applicable Position(s): SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 2/1/2012 Page 1 of 5
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 0 JPM
Title:
Review a Manual Clearance for Maintenance on AC-3C Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 5
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 0 JPM
Title:
Review a Manual Clearance for Maintenance on AC-3C TASK STANDARD: The candidate reviewed the Manual Clearance in accordance with SO-G-20A. The Candidate did not approve the Clearance because items were not listed in the required sequence. The Control Switch in the Control Room should have been the first item in the sequence.
INITIAL CONDITIONS: Maintenance is being planned to replace the impellor on Component Cooling Pump, AC-3C.
SOMS is unavailable. A Manual Clearance has been prepared.
INITIATING CUE:
You are directed to perform a SRO review of the manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A. The following information should be reviewed:
- Tag Type
- Equipment
- Placement Sequence
- Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Page 3 of 5
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 0 JPM
Title:
Review a Manual Clearance for Maintenance on AC-3C Critical Steps shown in gray STEP ELEMENT STANDARD 1 Reviewed Manual Clearance Candidate reviewed Form form.
[ SAT ] [ UNSAT ]
2 Refer to applicable references: Candidate used reference
- SO-G-20A material as required.
- Plant Procedures
2 Approve Clearance The Candidate did not approve the clearance (Circled NO) because the Control Switch for AC-3C must be first item in the sequence.
[ SAT ] [ UNSAT ]
Note: the Candidate may also wish to add AC-163, AC-1116, AC-838 and AC-837 to the Clearance.
Termination Criteria: The candidate has completed the clearance form with the information listed in the initiating Cue.
Page 4 of 5
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 INITIAL CONDITIONS: Maintenance is being planned to replace the impellor on Component Cooling Pump, AC-3C.
SOMS is unavailable. A Manual Clearance has been prepared.
INITIATING CUE: You are directed to perform a SRO review of the manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A. The following information should be reviewed:
- Tag Type
- Equipment
- Placement Sequence
- Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Name:__________________________________________________
Approve Clearance: (Circle One) YES NO If you did not approve, specify why below:
Page 5 of 5
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA4 Rev 0 JPM
Title:
Determine if temporary shielding should be requested Location: Classroom Approximate Time: 5 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 2.3.12 K/A#2.3.7 RP-307, Use and Control of Temporary Shielding Other (tech specs, etc)
Handout(s):
Task List#:
Applicable Position(s): SRO-I, SRO-U Time Critical: No Alternate Path: No JPM Prepared by: Date:
Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA4 Rev 0 JPM
Title:
Determine if temporary shielding should be requested Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA4 Rev 0 JPM
Title:
Determine if temporary shielding should be requested TASK Candidate calculated total estimated dose for the work STANDARD: without installing shielding to be 140 mrem. Candidate calculated total estimated dose for the work with shielding (including shielding installation) to be approximately 132 mrem. Candidate recommends requesting temporary shielding be installed.
INITIAL Work is being planned to be performed in Room 13 CONDITIONS: near HS#23 which has a 30 cm dose rate reading of 80 mR/hr. This work is expected to take 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.
It has been determined that if shielding is installed, the dose rate will decrease to 45 mR/hr. The time to install the shielding is estimated to take 40 minutes.
INITIATING CUE: Determine the total expected dose for the work if shielding is not installed and the total expected dose if shielding is installed. Recommend whether or not temporary shielding should be requested.
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA4 Rev 0 JPM
Title:
Determine if temporary shielding should be requested Critical Steps shown in gray STEP ELEMENT STANDARD 1 Determine expected dose Candidate determines without shielding. expected dose without shielding.
80 mR/hr
- 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> = 140 mrem
[ SAT ] [ UNSAT ]
2 Determine expected dose with Candidate determines total shielding installation. expected dose if shielding is installed.
80 mR/hr
- 40 min * (1 hr / 60 min) + 45 mR/hr
- 1.75 hr =
132 mrem
[ SAT ] [ UNSAT ]
3 Determine if shielding should Candidate determines that the be requested. total dose with shielding is 8 mrem less than the total expected dose without shielding and therefore, temporary shielding should be requested.
[ SAT ] [ UNSAT ]
4
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA4 Rev 0 JPM
Title:
Determine if temporary shielding should be requested Termination Criteria: Candidate has calculated the total expected dose both with and without shielding and has determined that shielding should be requested.
Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA4 INITIAL Work is being planned to be performed in Room 13 CONDITIONS: near HS#23 which has a 30 cm dose rate reading of 80 mR/hr. This work is expected to take 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.
It has been determined that if shielding is installed, the dose rate will decrease to 45 mR/hr. The time to install the shielding is estimated to take 40 minutes.
INITIATING CUE: Determine the total expected dose for the work if shielding is not installed and the total expected dose if shielding is installed. Recommend whether or not temporary shielding should be requested.
Total dose if shielding is NOT installed: _____________
Total dose if shielding is installed: ______________
Recommend requesting temporary shielding (YES or NO)? ____________
Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 0 JPM
Title:
Classify Emergency Action Levels and make Protective Action Recommendations Location: Classroom Approximate Time: 12 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): 1. K/A# 000000 2.4.41 (SRO 4.6): Knowledge of the emergency action level thresholds and classifications.
- 2. K/A# 000000 2.4.44 (SRO 4.4): Knowledge of emergency plan protective action recommendations.
- 3. EPIP-OSC-1, EMERGENCY CLASSIFICATION.
- 4. TBD-EPIP-OSC-1A, Recognition Category A - Hazards and Other Conditions Affecting Plant Safety.
- 5. EPIP-EOF-7, PROTECTIVE ACTION GUIDELINES.
Task List#: 1453 Applicable Position(s): SRO Time Critical: YES Alternate Path: NO JPM Prepared by: Jerry Koske Date: 1/17/2012 Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 0 JPM
Title:
Classify Emergency Action Levels and make Protective Action Recommendations Operators Name:
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: SA5 Rev 0 JPM
Title:
Classify Emergency Action Levels and make Protective Action Recommendations TASK The SRO candidate reviewed the plant conditions, STANDARD: referred to EPIP-OSC-1A and TDB-IV.8 and classified the event as a General Emergency, IC AG1, EAL 1.
Within 15 minutes of classifying the event, the candidate determined that the Protective Action Recommendation is to evacuate all sectors 0-2 miles and completed page one of form FC-1188 so that offsite notifications can be made.
INITIAL
- A loose parts monitoring alarm came in an hour CONDITIONS: ago
- 20 minutes ago, the reactor tripped on TMLP and Radiation Monitors RM-057 and RM-054A alarmed
- Attempts to isolate Steam Generator RC-2A have been unsuccessful.
- RM-064 has been placed in service and its S/G A reading has increased from 975 cps to 990 cps over the past 15 minutes.
- The wind is from 180° @ 15 mph.
- The Met Tower T is -1.3°C/100m
- There is no precipitation INITIATING CUE You are the Shift Manager. Determine the appropriate IC and EAL, if any, in accordance with EPIP-OSC-1.
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 0 JPM
Title:
Classify Emergency Action Levels and make Protective Action Recommendations CUE #2: ***********TIME CRITICAL JPM***************
Specify any Protective Action Recommendations and Complete Form FC-1188.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refer to Emergency Plan. Refer to TBD-EPIP-OSC-1A.
[ SAT ] [ UNSAT ]
2 Classify the event. This Event should be classified as a GENERAL EMERGENCY using IC AG1, EAL 1.
[ SAT ] [ UNSAT ]
3 Determine Protective Action ***** TIME CRITICAL *****
Recommendations and fill out form FC-1188 for notifications. Provide CUE# 2 and Blank FC-1188 to Candidate Start Time: _____________
Form FC-1188 must be filled out within 15 minutes and must contain the following information:
- Initial Declaration
- General Emergency
- IC#: AG1
- EAL: 1 (Loss)
- Prognosis: Worsening Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 0 JPM
Title:
Classify Emergency Action Levels and make Protective Action Recommendations STEP ELEMENT STANDARD
- Plant Status: Shutdown
- Wind Direction:180°
- Wind Speed:15 MPH
- Precipitation: No
- Temperature difference:
-1.3 °C/100m
- Stability Class: D
- There is an airborne release
- PARs: EVACUATE all Sectors, 0-2 Miles
- Plant Status: At power
- Approval Signature, date and time.
End Time:____________
Elapsed Time:__________
[ SAT ] [ UNSAT ]
Termination Criteria: The Event has been classified and PARs have been made.
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 0 INITIAL
- A loose parts monitoring alarm came in an hour CONDITIONS: ago
- 20 minutes ago, the reactor tripped on TMLP and Radiation Monitors RM-057 and RM-054A alarmed
- Attempts to isolate Steam Generator RC-2A have been unsuccessful.
- RM-064 has been placed in service and its S/G A reading has increased from 975 cps to 990 cps over the past 15 minutes.
- The wind is from 180° @ 15 mph.
- The Met Tower T is -1.3°C/100m
- There is no precipitation INITIATING CUE: You are the Shift Manager. Determine the appropriate IC and EAL, if any, in accordance with EPIP-OSC-1.
Candidate Name: __________________________________
IC#__________________ EAL#_______________
Time of Declaration:________________
Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 0 CUE #2: ***********TIME CRITICAL JPM***************
Specify any Protective Action Recommendations and Complete Form FC-1188.
Page 7 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0107 (P-1) Rev JPM
Title:
Respond to a steam bound auxiliary feedwater pump Location: Auxiliary Building Approximate Time: 7 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A#: 000061, K3.01, A2.04 Procedures: AOP-28,Section III Revision 15 Other (tech specs, etc)
Handout(s):
Task List#:
Applicable Position(s): RO, SRO-I, SRO-U Time Critical: No Alternate Path: No JPM Prepared by: Date:
Page 1 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0107 (P-1) Rev JPM
Title:
Respond to a steam bound auxiliary feedwater pump Operators Name:
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: Take precautions in the vicinity of hot piping and steam drains Comments: This JPM will be conducted as a static JPM in the plant.
Page 2 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0107 (P-1) Rev JPM
Title:
Respond to a steam bound auxiliary feedwater pump TASK Respond to a steam bound auxiliary feedwater pump, STANDARD: take the necessary corrective actions, and restart auxiliary feedwater pump FW-6.
INITIAL When attempting to feed the steam generators using CONDITIONS: auxiliary feedwater pump FW-6, feedwater flow to the steam generators lowered. FW-6 discharge piping temperature is reported as indicating approximately 265°F.
INITIATING CUE: You have been directed to take the necessary corrective actions to restore the auxiliary feedwater pump to service using AOP-28,Section III.
Page 3 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0107 (P-1) Rev JPM
Title:
Respond to a steam bound auxiliary feedwater pump Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain a copy of AOP-28 Knowledge of where to obtain Section III. a copy of AOP-28
[ SAT ] [ UNSAT ]
CUE: Provide copy of AOP-28,Section III.
2 (AOP-28, Check discharge pipe Room 19 Section III, temperature is greater than Checks TI-1382 and TI-1383 Step 1) 260°F for either FW-6 or FW- for temperatures.
10
[ SAT ] [ UNSAT ]
CUE: TI-1382 reads approximately 265°F.
3 (Step 2) Stop FW-6. Either contacted control room to stop the pump or stopped the pump locally.
[ SAT ] [ UNSAT ]
4 (Step 4.a) Locally vent FW-6. Unlock and Room 19 close FW-171, motor driven FW-171 unlocked and closed.
aux feed pump FW-6 discharge valve. [ SAT ] [ UNSAT ]
CUE: Indications that valve is closed (stem or indicator?)
5 (Step 4.b) Locally vent FW-6. Open FW- Room 19 688, motor driven aux feed Opened FW-688.
pump FW-6 discharge drain valve. [ SAT ] [ UNSAT ]
CUE: Indications that valve is opened (stem or indicator?)
Page 4 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0107 (P-1) Rev JPM
Title:
Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD 6 (Step 4.c) Locally vent FW-6. When a Room 19 steady stream of water issues Closed FW-688 following cue from the drain valve, close the 1.
drain valve.
[ SAT ] [ UNSAT ]
CUE 1: A steady stream of water is observed.
CUE 2: Indication that valve is closed (stem or indicator?)
7 (Step 5) If EFWST level was less than 25%, vent auxiliary feedwater [ SAT ] [ UNSAT ]
suction pipe. CUE: EFWST level never fell below 25%.
8 (Note) Review NOTE. (The 43/FW Note reviewed.
switch lines up 9 pumps for [ SAT ] [ UNSAT ]
auto-start operation. Auto start is inhibited for these nine pumps if the 43/FW switch is in the off position) 9 (Step 6.a) Verify operability of FW-6. Contacted control room to Place 43/FW switch in OFF. place 43/FW switch in OFF.
[ SAT ] [ UNSAT ]
CUE: 43/FW switch is in OFF.
10 (Step 6.b) Verify operability of FW-6. Room 19 Open FW-175, motor drive aux Opened FW-175.
feed pump FW-6 discharge press indic PI-1379 root valve [ SAT ] [ UNSAT ]
CUE: FW-175 indicates open (stem or indicator?)
Page 5 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0107 (P-1) Rev JPM
Title:
Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD 11 (Step 6.c) Verify operability of FW-6. Either contacted control room Start FW-6 to start FW-6 or started locally.
[ SAT ] [ UNSAT ]
CUE: FW-6 red light is lit.
12 (Step 6.d) Verify operability of FW-6. Room 19 Allow FW-6 to run until Checks PI-1379 to determine pressure on PI-1379, FW-6 discharge pressure.
disch. pressure is greater than S/G pressure. [ SAT ] [ UNSAT ]
CUE: Indicator reads 1200 psia.
13 (Step 6.e) Verify operability of FW-6. Either contacted control room Stop FW-6. to stop FW-6 or stopped locally.
[ SAT ] [ UNSAT ]
CUE: Red light is unlit.
Green light is lit.
14 (Step 6.f) Verify operability of FW-6. Room 19 Verify FW-6 stops. Verify green light is lit.
[ SAT ] [ UNSAT ]
CUE: Green light is lit. No motor noise. Pump shaft is not moving.
15 (Step 6.g) Open and lock FW-171. Room 19 FW-171 opened and locked.
[ SAT ] [ UNSAT ]
CUE: FW-171 indicates opened (stem or indicator?)
Page 6 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0107 (P-1) Rev JPM
Title:
Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD 16 (Step 6.h) Start FW-6. Either contacted control room or started locally.
[ SAT ] [ UNSAT ]
CUE: Red light is lit.
17 (Step 6.i) Monitor PI-1379 for any Room 19 abnormal fluctuation. Checks PI-1379 for fluctuation.
[ SAT ] [ UNSAT ]
CUE: PI-1379 reads 1200 psia, with no abnormal fluctuation.
18 (Step 7) If plant is in mode 1, place N/A this step.
43/FW switch in AUTO. [ SAT ] [ UNSAT ]
19 (Step 8) Restore AFW to the desired lineup per OI-AFW-1. [ SAT ] [ UNSAT ]
CUE: Another operator will perform OI-AFW-1.
20 (Step 9) Ensure FW-175 is closed. Room 19 FW-175 is closed.
[ SAT ] [ UNSAT ]
CUE: FW-175 indicates closed (stem or indicator?)
Termination Criteria: Pump FW-6 is running and supply AFW flow to the steam generators.
Page 7 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P1 INITIAL When attempting to feed the steam generators using CONDITIONS: auxiliary feedwater pump FW-6, feedwater flow to the steam generators lowered. FW-6 discharge piping temperature is reported as indicating approximately 265°F.
INITIATING CUE: You have been directed to take the necessary corrective actions to restore the auxiliary feedwater pump to service using AOP-28,Section III.
Page 8 of 8
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM- (P-2)
Title:
Rack in GE Automatic 480-volt breaker Location: Breaker Lab Approximate Time: XX minutes Actual Time: _________________
Reference(s): OI-EE-2A Attachment 1 Revision 19 K/A JPM Prepared by: Date:
JPM Reviewed by: Date:
JPM Approved by: Date:
Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM- (P-2)
Title:
Rack in GE Automatic 480-volt breaker Operators Name:
All Critical Steps (*) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: Speedwrench/socket Safety Considerations: None Comments:
Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM- (P-2)
Title:
Rack in GE Automatic 480-volt breaker INITIATING CUE:
You have been directed to rack in GE Automatic 480 Volt breaker per OI-EE-2A Attachment 1.
CRITICAL ELEMENT STANDARD STEP 1 Obtain copy of OI-EE-2A Locates OI-EE-2A Attachment Attachment 1 1
[ SAT ] [ UNSAT ]
Provide candidate with a copy of OI-EE-2A Attachment 1 2 (Att-1, 1) Place control switch in PULL- Contact control room to verify OUT, if applicable (Control control switch in pull-out.
Room)
[ SAT ] [ UNSAT ]
CUE: Control room verifies that control switch is in pull-out.
3 (Att-1, 2) Verify breaker position indicator Breaker Lab displays OPEN. Position indicator displays open
[ SAT ] [ UNSAT ]
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM- (P-2)
Title:
Rack in GE Automatic 480-volt breaker CRITICAL ELEMENT STANDARD STEP
- 4. (Att-1, 3) Place 69 permissive switch in 69 permissive switch in PULL-PULL-OUT OUT
[ SAT ] [ UNSAT ]
- 5. (Att-1, Reviews Cautions [ SAT ] [ UNSAT ]
Cautions) 6 (Att-1, 4) Depress breaker Manual Trip Manual trip pushbutton pushbutton depressed
[ SAT ] [ UNSAT ]
7 (Att. 2, 5.a) Insert speed wrench/socket Speed wrench/socket inserted onto jackscrew shaft onto jackscrew shaft
[ SAT ] [ UNSAT ]
8 (Att. 2, 5.b) Rotate speedwrench until Socket slot is aligned with socket slot is aligned with jackscrew pin.
jackscrew pin
[ SAT ] [ UNSAT ]
9 (Att-1, 5.c) Push speedwrench IN, Interlock tube retracted and retracting interlock tube, and socket engage in square end engage socket with square end of jackscrew shaft.
of jackscrew shaft
[ SAT ] [ UNSAT ]
10 (Att-1, 5.d) Turn speedwrench clockwise Jackscrew is on its hard stop until jackscrew hits hard stop (about 17 turns) [ SAT ] [ UNSAT ]
11 (Att-1, 5.e) Turn wrench counterclockwise Interlock tube slot is aligned (less than 1/2 turn) to align with jackscrew pin interlock tube slot with jackscrew pin [ SAT ] [ UNSAT ]
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM- (P-2)
Title:
Rack in GE Automatic 480-volt breaker CRITICAL ELEMENT STANDARD STEP 12 (Att-1, 5.f) Remove speedwrench/socket Speedwrench/socket removed.
from jackscrew shaft
[ SAT ] [ UNSAT ]
13 (Att-1, 6) Verify correct breaker installation by the following:
- Breaker front panel is [ SAT ] [ UNSAT ]
flush with load center
- Cubicle position indicator displays CONN
- Jackscrew pin and interlock tube are aligned
- Interlock tube has sprung fully forward over the jackscrew shaft to allow breaker operation 14 (Att-1, 7) If breaker load is engineered Amber light is on.
safeguards, ensure 69 switch amber light is ON. [ SAT ] [ UNSAT ]
15 (Att-1, 8) Obtain control room approval to Contact control room place 69 permissive switch in AFTER-CLOSE [ SAT ] [ UNSAT ]
CUE: Control room approves placing 69 permissive switch in AFTER-CLOSE 16 (Att-1, 9) Place 69 permissive switch to 69 permissive switch in AFTER-CLOSE AFTER-CLOSE
[ SAT ] [ UNSAT ]
17 (Att-1, 10) Notify control room breaker is racked in [ SAT ] [ UNSAT ]
CUE: Control room Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM- (P-2)
Title:
Rack in GE Automatic 480-volt breaker CRITICAL ELEMENT STANDARD STEP acknowledge report.
Termination Criteria: GE Automatic 480-volt breaker is racked in.
Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM INITIATING CUE:
You have been directed to rack in GE Automatic 480 Volt breaker per OI-EE-2A Attachment 1.
START Page 7 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank Location: RCA Approximate Time: 15 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 071000 A4.05 RO IMP: 2.6 SRO IMP:2.6 Ability to manually operate and/or monitor in the control room:
Gas decay tanks, including valves, indicators, and sample line.
Procedures: OI-WDG-1 Other (tech specs, etc)
Handout(s): OI-WDG-1, Attachment 3 Task List#: 0736 Applicable Position(s): EONA/RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 2/1/2012 Page 1 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations: Requires RCA Entry Comments:
Page 2 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank TASK STANDARD: The candidate transferred waste gas from the vent header to the inservice Gas Decay Tank in accordance with OI-WDG-1, Attachment 3. Prior to starting WD-28A, the Candidate drained the moisture separator tank.
INITIAL CONDITIONS: Vent header pressure is at 2 psig. CCW cooling water is lined up and providing cooling to WD-28A. The pressure of the in-service Waste Gas Decay Tank is 45 psig. AI-110 is inoperable. The Shift Chemist is on standby to take samples when notified.
INITIATING CUE:
You have been directed to pump the vent header to the in service gas decay tank using WD-28A until vent header pressure has been reduced to 1 psig using OI-WDG-1, Attachment 3. All prerequisites are met.
Page 3 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank Critical Steps shown in gray STEP ELEMENT STANDARD 1 IF it is desired to pump the vent Determined that it was not header below 1.0 psig, THEN desired to pump below 1.0 perform Steps 1 through 4 of psig. Marked step as N/A Attachment 7.
[ SAT ] [ UNSAT ]
2 Caution on page 7 Candidate read Caution
[ SAT ] [ UNSAT ]
3 Ensure the following VCT Gas AI-110 Space Sampling valves are closed (AI-110): Verified WD-242 and WD-1080 are closed.
- WD-242
- WD-1080 Note: Inform candidate that visual indication of valve position is all that is required.
[ SAT ] [ UNSAT ]
4 Verify the Waste Gas Vent Room 13 Header is void of water by performing the following steps Examiner CUE: Before (Room 13): candidate enters room 13, tell him that The vent header in room 13 has been drained (ALARA) 5 Note and Caution on page 8 Candidate read note and caution
[ SAT ] [ UNSAT ]
Page 4 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD 6 Ensure the selected Waste Gas Room 16 Compressor is operable and primed by performing the Ensured DW-156 was following steps (Room 16): OPEN
- a. Ensure the Seal Water CUE: DW-156 is OPEN Isolation Valve to the Waste Gas Compressor Skid is open: [ SAT ] [ UNSAT ]
- WD-28A, DW-156
- WD-28B, DW-157 7 Notes on page 9 Candidate read notes
[ SAT ] [ UNSAT ]
8 IF Moisture Separator Tank is Room 16 above the pump rotor centerline, drain the tank: Checked Moisture Separator Tank Level
- WD-28A, WD-216
- WD-28B, WD-217 CUE: Water level is above the pump rotor centerline
- a. Opened WD-216
- b. CUE: Water level is below pump rotor centerline
- c. Closed WD-216
[ SAT ] [ UNSAT ]
Page 5 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD 9 IF Moisture Separator Tank level Room 16 is below the casing bottom, fill by performing the following steps: Checked Moisture Separator Tank Level CUE: Water level is above the casing bottom.
Marked step N/A
[ SAT ] [ UNSAT ]
10 If running one or more Waste Determines the CCW is Gas Compressors without CCW available to the Waste Gas cooling water, station an Compressor (Initial Conditions)
Operator to ensure seal water and marks step N/A temperature does not exceed 150 F. [ SAT ] [ UNSAT ]
- TI/WD-28A, Waste Gas Compressor WD-28A Seal Water Temperature Indicator
- TI/WD-28B, Waste Gas Compressor WD-28B Seal Water Temperature Indicator 11 IF AI-110 is operable, THEN Determined AI-110 is not perform the following: operable (Initial Condition) and Marked step as N/A.
[ SAT ] [ UNSAT ]
12 Caution on page 10 Candidate read caution
[ SAT ] [ UNSAT ]
Page 6 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD 13 Commence Waste Gas AI-100 Transfer by performing the following steps: WD-28A control switch to hand RED light ON
- a. Start the selected Waste Gas Compressor: [ SAT ] [ UNSAT ]
- WD-28A
- WD-28B 14 Monitor the following: AI-100
- WGDT Pressure
[ SAT ] [ UNSAT ]
15 Note on page 11 Candidate read note
[ SAT ] [ UNSAT ]
16 IF H2 and O2 Concentrations Examiner Note: H2 and O2 exceed 3%, THEN secure the concentrations cannot be Waste Gas Transfer by monitored with AI-110 performing the following steps: inoperable.
17 If running a Waste Gas Determines the CCW is Compressor without CCW available to the Waste Gas cooling water and seal water Compressor (Initial Conditions) temperature reaches 150°F, stop and marks step N/A the Waste Gas Compressor.
[ SAT ] [ UNSAT ]
18 Nota and Caution on page 12 Candidate read note and caution
[ SAT ] [ UNSAT ]
Page 7 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD CUE: WGDT = 50 psig Vent Header = 1.0 psig 19 WHEN the Vent Header AI-100 pressure is approximately 1.0 psig (PI-526), In Service WGDT WD-28A control switch to OFF pressure reaches full capacity and GREEN light lit (95-100 psig), or Degassing Operations are completed, or [ SAT ] [ UNSAT ]
Vent Header is at desired pressure below 1.0 psig (PI-526), THEN stop the selected Waste Gas Compressor:
- WD-28A
- WD-28B 20 IF AI-110 is operable, THEN 5 Determined AI-110 is minutes after the Waste Gas inoperable. Marked step as Transfer is secured. N/A.
[ SAT ] [ UNSAT ]
22 IF AI-110 is inoperable, CUE: Shift Chemist Acknowledges THEN notify the following:
Shift Chemist to obtain grab [ SAT ] [ UNSAT ]
samples.
Shift Manager to review Technical Specification 2.9.
22 Shift Manager to review CUE: Shift Manager Notified Technical Specification 2.9.
[ SAT ] [ UNSAT ]
CUE: JPM Complete Page 8 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 0 JPM
Title:
Waste Gas Transfer from the Vent Header to the Gas Decay Tank Termination Criteria: Waste gas has been transferred from the Vent Header to the in-service gas decay tank and the Waste Gas Compressor has been secured.
Page 9 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 INITIAL CONDITIONS: Vent header pressure is at 2 psig. CCW cooling water is lined up and providing cooling to WD-28A. The pressure of the in-service Waste Gas Decay Tank is 45 psig. AI-110 is inoperable. The Shift Chemist is on standby to take samples when notified.
INITIATING CUE: You have been directed to pump the vent header to the in service gas decay tank using WD-28A until vent header pressure has been reduced to 1 psig using OI-WDG-1, Attachment 3. All prerequisites are met.
Page 10 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic Location: Simulator Approximate Time: 20 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 010000 A2.03 RO IMP: 4.1 SRO IMP: 4.2 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures.
Procedures: OI-RC-7, Attachment 5, ARP-CB-1,2,3/A4, ARP-CB-1,2,3/A6 Other (tech specs, etc)
Handout(s): OI-RC-7, Attachment 5 Task List#: 1314 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 1/19/2012 Page 1 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic TASK STANDARD: The Candidate transferred PC-103Y to manual mode in accordance with OI-RC-7, Attachment 5. The candidate responded to a PORV PCV-102-1 leak by attempting to close block valve HCV-151. When an overload occurred on the breaker for HCV-151, the Candidate directed the Building Operator to reset the overload trip. The Candidate than closed HCV-151 and isolated the leaking PORV.
INITIAL CONDITIONS: The plant is operating at full power. Pressurizer Pressure Controller PC-103 Y is in manual for I&C testing. I&C testing is complete.
INITIATING CUE: The CRS has directed you to transfer PC-103Y to Automatic using OI-RC-7, Attachment 5.
Page 3 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic Critical Steps shown in gray STEP ELEMENT STANDARD Simulator Operator:
Fail HCV-151 Closed 1 Note Output Meter reading and CB-1,2,3 mark with moveable slide marker. Positioned movable slide
- PC-103Y, Pressurizer meter to match output meter Press Controller reading
[ SAT ] [ UNSAT ]
2 Note Read Note
[ SAT ] [ UNSAT ]
3 Adjust SET pushbuttons such CB-1,2,3 that Setpoint Meter (Blue) Use SET pushbuttons such indication is slightly greater that Blue indication is slightly than Process Meter (Red) greater than Red indication Indication
[ SAT ] [ UNSAT ]
4 Note Read Note
[ SAT ] [ UNSAT ]
5 Place controller in automatic by CB-1,2,3 pressing the A push-button and Pressed the A pushbutton monitor the output meter for and monitored the output change meter
- PC-103Y, Pressurizer Press Controller [ SAT ] [ UNSAT ]
Page 4 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT STANDARD 6 Notes Read the Notes
[ SAT ] [ UNSAT ]
7 Use SET pushbuttons and CB-1,2,3 make small setpoint Adjusted SET pushbuttons as adjustments as necessary to required to return output meter return Output Meter reading to to position indicated by original position, indicated by movable slide marker.
the movable slide marker.
- PC-103Y, Pressurizer [ SAT ] [ UNSAT ]
Press Controller Simulator Operator Fail PCV-102-1, 1% open NOTE: PORV PCV-102-1 will begin leaking Alternate Path Begins 8 Respond to PRESSURIZER Entered ARP-CB-1,2,3/A4 and PWR OPERATED RELIEF turned to Window A-2 VALVE DISCH TEMP HI alarm [ SAT ] [ UNSAT ]
9 Check the Power Operated CB-1,2,3 Relief Valves Tailpipe Determined that temperature Temperature (TIA-134, CB-3) indicated by TIA-134 has risen.
[ SAT ] [ UNSAT ]
10 If Temperature is High, THEN ERF Computer Perform the following: Determined that Containment Check the Containment temperature was below 120°F Temperature (T887, T888, T889,T890, ERF) [ SAT ] [ UNSAT ]
IF Containment Temperature is greater than 120°F, THEN provide additional cooling to the Containment.
Page 5 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT STANDARD 11 Check the VCT Level Recorder CB-1,2,3 for decreasing Level (YR-4100, Checked VCT level recorder.
CB-2) May have determined that level is decreasing slowly.
[ SAT ] [ UNSAT ]
12 Monitor Pressurizer Quench CB-1,2,3 tank Monitored Quench Tank IF temperature (TIA-133, CB-3) Temperature and Level. May approaches 120°F, THEN have determined that pressure perform OI-RC-6 Attachment 5, and level are slowly Quench Tank Temperature increasing. Determined that Control Following Safety or temperature was below 120°F.
Relief Valve Discharge.
[ SAT ] [ UNSAT ]
13 Perform RCS Leak Rate Test Examiner CUE: RCS OP-ST-RC-3001 Leakrate test indicates 4 gpm leakage 14 IF RCS Leakage is indicated, CB-1,2,3 THEN close the PORV Block Attempted to close HCV-151 Valves one at a time AND by placing Control Switch in monitor Tailpipe Temperature the CLOSE Position for decrease.
[ SAT ] [ UNSAT ]
NOTE: HCV-151 Breaker overload tripped when Candidate attempted to close the block valve.
15 Respond to HCV-151 Entered ARP-CB-1,2,3/A6 and TROUBLE Alarm turned to Window E-5
[ SAT ] [ UNSAT ]
Page 6 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT STANDARD 16 Check the indicating lights CB-1,2,3 HCV-151 Determined that valve indicating lights are off.
[ SAT ] [ UNSAT ]
17 IF the valve indicating lights are Dispatched Building Operator off, THEN Dispatch an to MCC-4A1, Breaker C05 to Operator to check the valve check if the valve breaker is breaker closed closed.
[ SAT ] [ UNSAT ]
Examiner Cue: Building Operator reports breaker is closed. Overload Trip has occurred.
18 If breaker is closed, THEN Notified Electrical Maintenance notify Electrical Maintenance to to check the Control Power check the Control Power Fuses.
Fuses.
[ SAT ] [ UNSAT ]
Examiner Cue: Electrical Maintenance reports Control Power fuses are good.
19 If the breaker is closed, THEN Directed Building Operator to reset breaker overload reset breaker overloads on MCC-4A1, Breaker C05
[ SAT ] [ UNSAT ]
Page 7 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 0 JPM
Title:
Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT STANDARD Simulator Operator:
- Clear HCV-151 Malfunction
NOTE: The HCV-151 TROUBLE alarm will reset.
20 IF RCS Leakage is indicated, CB-1,2,3 THEN close the PORV Block Closed HCV-151 by placing Valves one at a time Control Switch in the CLOSE Position, Green Light ON
[ SAT ] [ UNSAT ]
21 AND monitor Tailpipe CB-1,2,3 Temperature for decrease. Monitored TIA-134 and determined that tailpipe temperature was decreasing.
[ SAT ] [ UNSAT ]
Termination Criteria: PC-103Y is controlling in Automatic and HCV-151 is closed isolating PORV PCV-102-1.
Page 8 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 INITIAL CONDITIONS: The plant is operating at full power. Pressurizer Pressure Controller PC-103 Y is in manual for I&C testing. I&C testing is complete.
INITIATING CUE: The CRS has directed you to transfer PC-103Y to Automatic using OI-RC-7, Attachment 5.
Page 9 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification Location: Simulator Approximate Time: 15 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 006000 A3.03 RO IMP: 4.1 SRO IMP:4.1 Ability to monitor automatic operation of the ECCS, including:
ESFAS-operated valves.
Procedures: EOP/AOP Floating Step W EOP/AOP Attachment 3 Other (tech specs, etc)
Handout(s): EOP/AOP Floating Step W Task List#: 0334 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 1/18/2011 Page 1 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments: Event File: Close HPSI, Fail 86/B PPLS Page 2 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification TASK STANDARD: The Candidate verified Engineered Safeguards Actuation in accordance with EOP/AOP Floating Step W. During this verification, the Candidate determined that a PPLS Relay failed to actuate and manually initiated PPLS. The Candidate also determined that SI flow was inadequate per EOP/AOP Attachment 3 and took action to restore adequate flow by opening the HPSI Injection Valves.
INITIAL CONDITIONS: The plant was operating at full power when a reactor trip and safeguards actuation occurred.
INITIATING CUE: The CRS has directed you to verify Engineered Safeguards Actuation using EOP/AOP Attachment W.
Page 3 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification Critical Steps shown in gray STEP ELEMENT STANDARD Simulator Operator: Initiate Small LOCA Malfunction.
1 IF PPLS is blocked, THEN GO Verified PPLS was NOT TO Step 4. blocked by:
CB-1,2,3 Verified the following annunciators are NOT in alarm:
- PPLS "A" BLOCKED (CB-1/2/3, A4, E-5)
- PPLS "B" BLOCKED (CB-1/2/3, A4, E-6)
AND/OR AI-30A/B Verified the following annunciators are NOT in alarm:
- PPLS-A BLOCKED (AI-30A, A33-1, C-1)
- PPLS-B1 BLOCKED (AI-30A, A33-2, C-1)
- PPLS-B BLOCKED (AI-30B, A34-1, C-7)
- PPLS-A1 BLOCKED (AI-30B, A34-2, C-4)
[ SAT ] [ UNSAT ]
Page 4 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification STEP ELEMENT STANDARD 2 IF ALL of the following exists, Determined that all of the
- RCS pressure less than listed conditions are NOT met 1600 psia because pressure in both S/Gs
- Containment pressure is greater than 500 psia. Went greater than 5 psig to step 2.
- At least one S/G pressure less than or equal to 500 [ SAT ] [ UNSAT ]
psia 3 IF RCS pressure is less than or AI-30A/B equal to 1600 psia, THEN verify Checked the status of each of Engineered Safeguards are the listed relays. Determined actuated by performing the that 86B/PPLS did not actuate following steps:
Verify ALL of the following PPLS [ SAT ] [ UNSAT ]
relays have tripped:
- 86A/PPLS
- 86B1/PPLS
- 86B/PPLS
- 86A1/PPLS Next Step is Alternate Path 4 IF any of the PPLS relays have AI-30B NOT tripped, THEN manually initiate using the PPLS Test
- Removed key from key Switches holder
- Inserted it into the B PPLS Test Switch
- Turned key clockwise
- Verified 86/B PPLS relay actuated.
[ SAT ] [ UNSAT ]
Page 5 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification STEP ELEMENT STANDARD 5 Ensure CIAS has initiated as AI-30A/B indicated by ALL of the following CIAS relays being tripped: Verified that each of the listed
- 86A/CIAS relays was in the TRIPPED
- 86B1/CIAS position with its Amber light
- 86B/CIAS OFF
- 86A1/CIAS
[ SAT ] [ UNSAT ]
6 Ensure VIAS has initiated as AI-30A/B indicated by ALL of the following VIAS relays being tripped: Verified that each of the listed
- 86A/VIAS relays was in the TRIPPED
- 86B1/VIAS position with its Amber light
- 86B/VIAS OFF
- 86A1/VIAS
[ SAT ] [ UNSAT ]
Page 6 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification STEP ELEMENT STANDARD 7 Ensure Emergency Boration is in Verified Emergency Boration progress. in progress by:
CB-4 Ensured the following valves were open (Red light ON)
- HCV-268
- HCV-265
- HCV-258 Ensured the following pumps are running:
- CH-4B CB-1,2,3 Ensured the following pumps are running:
- CH-1C Ensured the following valves are closed:
- LCV-218-2
- LCV-218-3 CB-4 Ensured the following valve are closed:
- HCV-257
- HCV-264
[ SAT ] [ UNSAT ]
Next step is alternate path Page 7 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 0 JPM
Title:
Engineered Safeguards Actuation Verification STEP ELEMENT STANDARD 8 Ensure SI flow is acceptable AI-30A/B or ERF Computer PER Attachment 3, Safety Injection Flow vs. Pressurizer Determined that flow was Pressure. inadequate due to HPSI injection valves being closed.
Opened the HPSI Injection Valves as required by turning switches clockwise until adequate flow was established:
- HCV-311
- HCV-312
- HCV-314
- HCV-315
- HCV-317
- HCV-318
- HCV-320
- HCV-321
[ SAT ] [ UNSAT ]
Examiner Note: JPM Complete Termination Criteria: Candidate has completed EOP/AOP Floating Step W and restored adequate SI flow.
Page 8 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 INITIAL CONDITIONS: The plant was operating at full power when a reactor trip and safeguards actuation occurred.
INITIATING CUE: The CRS has directed you to verify Engineered Safeguards Actuation using EOP/AOP Attachment W.
Page 9 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (S-3)
Title:
Place a Containment Cooling Unit in Service Location: Simulator Approximate Time: 12 minutes Actual Time: _________________
Reference(s): OI-VA-1, Attachment 2 R71 NRC K/A 022000 A4.01 (RO 3.6 / SRO 3.6)
Handout(s):
Task List#:
Applicable Position(s): RO, SRO-I Time Critical: No Alternate Path: No JPM Prepared by: Jerry Koske Date: 05/05/05 JPM Reviewed by: Date:
JPM Approved by: Date:
Page 1 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (S-3)
Title:
Place a Containment Cooling Unit in Service Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: None Safety Considerations: None Comments:
Page 2 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (S-3)
Title:
Place a Containment Cooling Unit in Service INITIATING CUE: You have been directed to place VA-7C and VA-8A in service.
All prerequisites are met.
Critical Steps shown in gray STEP ELEMENT STANDARD
- 1. (1.a.1) Open HCV-402B/D CB-1,2,3 Momentarily place HCV-402B/D in OPEN. Verify RED lights lit for both valves.
[ SAT ] [ UNSAT ]
2 (1.a.2) Ensure HCV-402C is closed CB-1,2,3 Ensure controller POT in closed position (100% output),
GREEN light lit
[ SAT ] [ UNSAT ]
3 (1.a.3) Place HCV-402A/C in CIRC CB-1,2,3 Momentarily place HCV-402A/C in CIRC position and release HCV-402A RED light lit
[ SAT ] [ UNSAT ]
Page 3 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (S-3)
Title:
Place a Containment Cooling Unit in Service STEP ELEMENT STANDARD 4 (1.a.4) Throttle open HCV-402C CB-1,2,3 maintaining CCW discharge Adjust POT for HCV-402C header pressure greater than toward OPEN position.
or equal to 70 psig ENSURE pressure on PI-499 does not go below 70 psig.
[ SAT ] [ UNSAT ]
5 (1.a.5) Monitor the following parameters: CB-1,2,3
- VA-8A Flow
- FI-418
- VA-8A Temperature
- TIC-422
- PI-499 Press
- TIC-2800 Temp
[ SAT ] [ UNSAT ]
6 (1.b) Start VA-7C AI-30A VA-7C CS to AFTER-START (Red flag), RED light lit
[ SAT ] [ UNSAT ]
7 (1.b) Monitor Parameters: AI-30A
- VA-7C amps
- VA-7C ammeter AI-44 Monitor:
- VA-7C DP
- PIC-702
- VA-7C cooling coil DP
- PI-710
- VA-7C Outlet Temp
- TI-719
[ SAT ] [ UNSAT ]
Page 4 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-0718 (S-3)
Title:
Place a Containment Cooling Unit in Service Termination Criteria: VA-7C is running and CCW is being supplied to VA-8A Page 5 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No:
INITIATING CUE: You have been directed to place VA-7C and VA-8A in service.
All prerequisites are met.
START Page 6 of 6
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 0 JPM
Title:
Initiation of Shutdown Cooling Location: Simulator Approximate Time: XX minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A#
Procedures: OI-SC-1, Rev. 52 Other (tech specs, etc)
Handout(s):
Task List#:
Applicable Position(s):RO, SRO-I Time Critical: No Alternate Path: No JPM Prepared by: Date:
Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 0 JPM
Title:
Initiation of Shutdown Cooling Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 0 JPM
Title:
Initiation of Shutdown Cooling TASK Initiate shutdown cooling on shutdown cooling train A.
STANDARD:
INITIAL Reactor has been shutdown. Current reactor status CONDITIONS: meets requirements for initiating shutdown cooling.
OI-SC-1 has been completed through Step 17 of Attachment 1 for shutdown cooling train A. RCPs RC-3B and RC-3D are running.
INITIATING CUE: Continue in OI-SC-1, Attachment 1, at Step 19 to initiate shutdown cooling on train A.
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 0 JPM
Title:
Initiation of Shutdown Cooling Critical Steps shown in gray STEP ELEMENT STANDARD 1 (OI-SC-1, Place HCV-341 key switch in HCV-341, Shutdown Heat Att. 1, Step MANUAL. Exchanger Valve Flow 19.a) Controller Override Switch key switch is in MAN.
[ SAT ] [ UNSAT ]
2 (OI-SC-1, Throttle HCV-341 10% open. HCV-341 is approximately Att. 1, Step 10% open.
19.b)
[ SAT ] [ UNSAT ]
3 (OI-SC-1, Place FCV-326 override switch FCV-326 LPSI/Shutdown Att. 1, Step in MANUAL. Cooling Flow Controller FCV-19.c) 326 override switch in MAN.
[ SAT ] [ UNSAT ]
4 (OI-SC-1, Throttle FCV-326 20% open. FCV-326 is approximately Att. 1, Step 20% open. NOTE: For FCV-19.d) 326 to be 20% open, controller output must 80%)
[ SAT ] [ UNSAT ]
5 (OI-SC-1, Open HCV-347 HCV-347 is opened.
Att. 1, Step 19.e) [ SAT ] [ UNSAT ]
6 (OI-SC-1, Open HCV-348 HCV-348 is opened.
Att. 1, Step 19.f) [ SAT ] [ UNSAT ]
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 0 JPM
Title:
Initiation of Shutdown Cooling STEP ELEMENT STANDARD 7 (OI-SC-1, Vent SI-1A by opening SI-334 Directs AO to vent SI-1A Att. 1, Step until full water flow observed, 19.g) then close SI-334 (LOCAL) [ SAT ] [ UNSAT ]
(CUE)
CUE: SI-1A has been vented.
SI-334 is closed.
8 (OI-SC-1, Start SI-1A SI-1A is started.
Att. 1, Step 19.h) [ SAT ] [ UNSAT ]
9 (OI-SC-1, Place TR-346 in service. TR-346 in service.
Att. 1, Step 19.i) [ SAT ] [ UNSAT ]
10 (OI-SC-1, Crack open LPSI loop injection Gradual heatup rate obtained.
Att. 1, Step valve to loop with running RCP 19.j) (valves?) to obtain gradual [ SAT ] [ UNSAT ]
heatup rate.
11 (OI-SC-1, When TR-346 temperature Two LPSI loop injection valves Att. 1, Step stabilizes, open any two LPSI opened.
19.k) loop injection valves
[ SAT ] [ UNSAT ]
CUE: TR-346 temperature is stabilized.
12 (OI-SC-1, Throttle FCV-326 to obtain 1500 gpm flow through FIC-Att. 1, Step 1500 gpm on FIC-326 326.
20)
[ SAT ] [ UNSAT ]
13 (OI-SC-1, Place FCV-326 in AUTOMATIC FCV-326 in automatic. 1500 Att. 1, Step and verify 1500 gpm flow is gpm flow.
- 21) maintained [ SAT ] [ UNSAT ]
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 0 JPM
Title:
Initiation of Shutdown Cooling Termination Criteria: Shutdown cooling initiated on shutdown cooling train A with FCV-326 in automatic and 1500 gpm flow through FIC-326.
Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No:
INITIAL Reactor has been shutdown. Current reactor status CONDITIONS: meets requirements for initiating shutdown cooling.
OI-SC-1 has been completed through Step 17 of Attachment 1 for shutdown cooling train A. RCPs RC-3B and RC-3D are running.
INITIATING CUE: Continue in OI-SC-1, Attachment 1, at Step 19 to initiate shutdown cooling on train A.
Page 7 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
Location: Simulator Approximate Time: 12 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 061000 A2.04 RO IMP:3.4 SRO IMP:3.8 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation.
Procedures: AOP-28 Other (tech specs, etc)
Handout(s): AOP-28 Task List#: 0025 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 1/18/2012 Page 1 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
VLV/AFW/SGN_YCV1045/0%,
FW-54 will not start Page 2 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
TASK STANDARD: The Candidate responded to a loss of FW-6 in accordance with AOP-28 by attempting to start FW-10, and Tripping RCPs. Candidate established FW flow by Starting a Main Feedwater Pump and adjusting FW Bypass Valves to restore S/G Level toward 35-85% NR.
INITIAL CONDITIONS: The plant was being maintained in hot shutdown due to a chemistry hold. FW-54 was being used to feed the Steam Generators. When FW-54 tripped, FW-6 was started and is being used to feed the steam generators via the nozzles.
INITIATING CUE: You are directed to restore Steam Generator Levels 35-85% NR Page 3 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
Critical Steps shown in gray STEP ELEMENT STANDARD 1 Verify S/G levels DCS Adjusted FW Bypass valves to raise S/G Level.
[ SAT ] [ UNSAT ]
Alternate Path Begins NOTE: FW-6 Trips 2 Respond to FW-6 trip Candidate determined that FW-6 has tripped and entered AOP-28,Section I
[ SAT ] [ UNSAT ]
Examiner Note:
Provide Candidate with a copy of AOP-28, Section 1 3 Notes on page 4 Candidate read note.
[ SAT ] [ UNSAT ]
4 Start FW-10, Steam AFW Pump. AI-65/66 Candidate attempted to open the following valves by placing the Control Switches in OPEN position and verify RED light ON:
- YCV-1045
- YCV-1045A
- YCV-1045B
[ SAT ] [ UNSAT ]
Page 4 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
STEP ELEMENT STANDARD NOTE: YCV-1045 does not open 5 IF feedwater is restored, THEN Candidate determined that GO TO Section 5.0, Exit feedwater was NOT restored Conditions. and did NOT exit procedure.
[ SAT ] [ UNSAT ]
6 IF the Reactor is critical, THEN Candidate determined that the initiate shutdown of the Reactor reactor was NOT critical.
by performing the following:
[ SAT ] [ UNSAT ]
7 Stabilize RCS temperature by DCS adjusting steaming rate. Candidate MAY adjust steam dump and bypass valve position.
[ SAT ] [ UNSAT ]
8 Trip all RCPs. CB-1,2,3 Candidate tripped all four RCPs by placing ther Control Switches in the AFTER-TRIP position and verified no current on ammeter.
[ SAT ] [ UNSAT ]
9 Ensure ALL of the Blowdown CB-10/11 Isolation Valves are closed: Candidate verified ALL of the listed valves were closed.
- HCV-1388A Control Switches in the
- HCV-1388B CLOSE position and verified
- HCV-1387A Green Lights ON
- HCV-1387B
[ SAT ] [ UNSAT ]
Page 5 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
STEP ELEMENT STANDARD EXAMINER CUE: Another Operator will monitor the floating steps and the Shift Manager will implement the Emergency Plan 10 IF a SGIS has actuated, THEN CB-4 override SGIS by placing ALL of Candidate determined that the following SGIS Override SGIS has not actuated.
Switches in "OVERRIDE
[ SAT ] [ UNSAT ]
11 IF Main Feedwater is available, CB-10/11 THEN restore S/G levels to 35- Candidate ensured that the 85% NR (73-94% WR) by 43/FW switch was in the OFF performing the following: Position.
Place the "43/FW" Switch in [ SAT ] [ UNSAT ]
"OFF".
12 Ensure at least one Condensate CB-10/11 Pump, FW-2A/B/C, is operating. Candidate ensured at least one Condensate Pump was running by checking:
- Control Switch Position
- Red Light ON
- Ammeter Current
[ SAT ] [ UNSAT ]
Note to Examiner: The procedure does not direct starting the Lube Oil Pump prior to starting the Main Feed Pump. However, an interlock will prevent the start of the Feed pump unless the Lube Oil Pump is running.
Page 6 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
STEP ELEMENT STANDARD 13 Start ONE Feed Pump, FW- CB-10/11 4A/B/C.
- Candidate started Lube Oil Pump for selected FW Pump by placing Control Switch in AFTER-START (Red flag) and verifying Red Light ON.
- Candidate Started selected FW Pump by placing Control Switch in AFTER-START(Red flag), Verifying Red Light ON and verifying ammeter Current
[ SAT ] [ UNSAT ]
14 Open BOTH Feed Header CB-10/11 Isolation Valves: Verified Control Switches in
- HCV-1386 the OPEN Position with Red
- HCV-1385 Light ON.
[ SAT ] [ UNSAT ]
15 Manually control feed flow via DCS BOTH Feed Reg Bypass Valves: Adjusted HCV-1105 and HCV-
- HCV-1105 1106 to maintain S/G levels in
- HCV-1106 band.
[ SAT ] [ UNSAT ]
16 IF Feedwater flow is established, Determined Feedwater flow THEN GO TO Section 5.0, Exit was established and exited Conditions. procedure.
[ SAT ] [ UNSAT ]
Page 7 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 0 JPM
Title:
Maintain S/G Water Levels during Startup Using AFW.
Termination Criteria: The Steam Generators are being fed by a Main Feed Pump.
Page 8 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 INITIAL CONDITIONS: The plant was being maintained in hot shutdown due to a chemistry hold. FW-54 was being used to feed the Steam Generators. When FW-54 tripped, FW-6 was started and is being used to feed the steam generators via the nozzles.
INITIATING CUE: You are directed to restore Steam Generator Levels 35-85% NR Page 9 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D Location: Simulator Approximate Time: XX minutes Actual Time: _________________
Reference(s): OP-ST-CH-3005b Attachment 2 Revision 19 K/A Handout(s):
Task List#:
Applicable Positions: RO, SRO-I Time Critical: No Alternate Path: No JPM Prepared by: Date:
JPM Reviewed by: Date:
JPM Approved by: Date:
Page 1 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D Operators Name:
All Critical Steps (*) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment: Stopwatch Safety Considerations: None Comments:
Page 2 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D INITIATING CUE: The reactor is currently operating at full power.
You are directed to perform valve stroke time testing of CCW valves HCV-401C and HCV-401D per OP-ST-CCW-3005b Attachment 2. An operator has been stationed locally at the valves.
CRITICAL ELEMENT STANDARD STEP 1 Obtain copy of OP-ST-CCW- Locates OP-ST-CCW-3005b 3005b
[ SAT ] [ UNSAT ]
Provide candidate with a copy of OP-ST-CCW-3005b 2 (Att-2, 1) Record as found position for CB-1,2,3 HCV-401A and HCV-401C Red lights indicate the valves are open.
[ SAT ] [ UNSAT ]
3 (Att-2, 2) Record as found position for CB-1,2,3 HCV-401B and HCV-401D Red lights indicate the valves are open.
[ SAT ] [ UNSAT ]
Page 3 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D CRITICAL ELEMENT STANDARD STEP
- 4. (Att-2, 3) Log VA-3B as inoperable and Informs CRS to declare VA-3B enter 7 day LCO inoperable and enter 7 day LCO
[ SAT ] [ UNSAT ]
CUE: VA-3B has been declared inoperable and 7 day LCO entered
- 5. (Att-2, 4.1) Station an operator at HCV- Directs AO to HCV-401C 401C to observe for proper valve operation [ SAT ] [ UNSAT ]
CUE: Operator Is stationed at HCV-401C to observe proper valve operation 6 (Att-2, 4.2) Adjust HCV-401C controller to CB-1,2,3 CLOSED HCV-401C, Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr is CLOSED
[ SAT ] [ UNSAT ]
7 (Att. 2, 4.3) Place HCV-401A/C control CB-1,2,3 switch to ISOL HCV-401A/C, Cntmt Clg Coil VA-1B Outlt Isol Vlvs Control Sw in ISOL
[ SAT ] [ UNSAT ]
8 (Att. 2, 5.1) Station an operator at HCV- Directs AO to HCV-401D 401D to observe for proper valve operation [ SAT ] [ UNSAT ]
CUE: Operator Is stationed at HCV-401D to observe proper valve operation Page 4 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D CRITICAL ELEMENT STANDARD STEP 9 (Att-2, 5.2) Close HCV-401D and verify CB-1,2,3 valve closes by local HCV-401D, Cntmt Clg Coil observation VA-1B Outlt Isol Vlv Cntrlr is CLOSED
[ SAT ] [ UNSAT ]
CUE: Local operator states that valve is closed.
10 (Att-2, 6) Station an operator at HCV- Direct AO to HCV-401C 401C to observe for proper valve operation
[ SAT ] [ UNSAT ]
CUE : Operator is stationed at valve HCV-401C.
11 (Att-2, 7) Adjust HCV-401C controller to CB-1,2,3 OPEN HCV-401C controller in OPEN
[ SAT ] [ UNSAT ]
12 (Att-2, 8) Open HCV-401C by placing CB-1,2,3 HCV-401A/C to CIRC and Use stopwatch to time valve perform the following using control panel lights.
- Locally observe for proper valve operation Record stroke time on Att. 5
- Time valve remotely using control panel lights [ SAT ] [ UNSAT ]
- Record stroke time on Att. 5 under Test Stroke CUE: Local operator states Time that valve operated properly 13 (Att-2, 9) Close HCV-401C by placing CB-1,2,3 HCV-401A/C to ISOL and Use stopwatch to time valve perform the following using control panel lights.
- Locally observe for Page 5 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D CRITICAL ELEMENT STANDARD STEP proper valve operation Record stroke time on Att. 5
- Time valve remotely using control panel lights [ SAT ] [ UNSAT ]
- Record stroke time on Att. 5 under Test Stroke CUE: Local operator states Time that valve operated properly 14 (Att-2, 10) If initial stroke time was in the N/A step Alert Range, then perform a verification stroke time [ SAT ] [ UNSAT ]
15 (Att-2, 11- Instrument air check valve Direct AO to locally perform
- 26) exercised steps 11-26 to exercise the instrument air check valves
[ SAT ] [ UNSAT ]
CUE: Local operator has successfully completed Steps 11-26 16 (Att-2, 27) Station at operator at HCV- Direct AO to HCV-401D to 401D to observe for proper observe proper valve valve operation operation
[ SAT ] [ UNSAT ]
CUE: Operator is stationed at HCV-401D 17 (Att-2, 28) Open HCV-401D and perform CB-1,2,3 the following: Use stopwatch to time valve
- Locally observe for using control panel lights.
proper valve operation
- Time valve remotely Record stroke time on Att. 5 using control panel lights
- Record stroke time on [ SAT ] [ UNSAT ]
Att. 5 under Test Stroke Time CUE: Local operator states that valve operated properly Page 6 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D CRITICAL ELEMENT STANDARD STEP 18 (Att-2, 29) Close HCV-401D and verify CB-1,2,3 valve closes by local Closes HCV-401D observation
[ SAT ] [ UNSAT ]
CUE: Local operator states that valve is closed 19 (Att-2, 30) If initial stroke time was in the N/A step Alert Range, then perform verification stroke time [ SAT ] [ UNSAT ]
20 (Att-2, 31) If HCV-401D is open, then N/A step close HCV-401D
[ SAT ] [ UNSAT ]
21 (Att-2, 32- Exercise instrument air check Direct AO to complete steps
- 37) valve 32-37
[ SAT ] [ UNSAT ]
CUE: Local operator has successfully completed Steps 32-37 22 (Att-2, 38) Ensure HCV-401C controller is CB-1,2,3 adjusted to full closed output Adjust controller to full closed signal
[ SAT ] [ UNSAT ]
23 (Att-2, 39) Place HCV-401B and HCV- CB-1,2,3 401D in as found position Open HCV-401B/D (open). Record as left position
[ SAT ] [ UNSAT ]
24 (Att-2, 40) Place HCV-401A and HCV- CB-1,2,3 401C in as found position Open HCV-401A/C Page 7 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S6 JPM
Title:
Valve stroke time testing of CCW valves HCV-401C/D CRITICAL ELEMENT STANDARD STEP
[ SAT ] [ UNSAT ]
25 (Att-2, 41) Log exit from 7 day LCO for Inform CRS that valve stroke VA-3B testing complete for HCV-401C/D and to exit LCO
[ SAT ] [ UNSAT ]
CUE: Acknowledge report Termination Criteria: CCW valve stroke time testing for HCV-401C/D completed Page 8 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM INITIATING CUE:
You are directed to perform valve stroke time testing of CCW valves HCV-401C and HCV-401D per OP-ST-CCW-3005b Attachment 2. An operator has been stationed locally at the valves.
START Page 9 of 9
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev JPM
Title:
Dilute RCS to Estimated Critical Conditions Boron Concentration Location:
Approximate Time: minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A#
Procedures: OP-2A Revision 102, OI-CH-4 Revision 45 Other (tech specs, etc)
Handout(s): TDB-V.1.B Estimated Critical Conditions Worksheet Rev. 22 Task List#:
Applicable Position(s):
Time Critical: No Alternate Path: Yes JPM Prepared by: Date:
Page 1 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev JPM
Title:
Dilute RCS to Estimated Critical Conditions Boron Concentration Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev JPM
Title:
Dilute RCS to Estimated Critical Conditions Boron Concentration TASK Dilute to the ECC boron concentration. During dilution, STANDARD: an unexpected rise in reactivity will occur, and candidate will stop the dilution in progress.
INITIAL Plant is currently shutdown in Mode 3. A plant CONDITIONS: startup is in progress per OP-2A, PLANT STARTUP, Attachment 2, CEA Withdrawal to Criticality Mode
- 2. Actions have been taken through Step 4 of OP-2A, Attachment 2, to withdraw Shutdown Groups A and B to the ARO position. TDB-V.1.B Estimated Critical Conditions Worksheet has been completed to determine final boron concentration.
INITIATING CUE: You have been directed to dilute the RCS to the ECC Boron Concentration as calculated in TDB-V.1.B, Estimated Critical Conditions Worksheet per Step 5 of OP-2A, Attachment 2.
Provide a copy of completed TDB-V.1.B as part of initiating cue.
Page 3 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev JPM
Title:
Dilute RCS to Estimated Critical Conditions Boron Concentration Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain copy of OP-2A, Obtain copy of OP-2A, Attachment 2 Attachment 2.
[ SAT ] [ UNSAT ]
CUE: Provide copy of OP-2A, Attachment 2.
2 (OP-2A, Att. Dilute RCS per OI-CH-4 until Obtain copy of OI-CH-4.
2, Step 5) ECC Boron Concentration is obtained. [ SAT ] [ UNSAT ]
CUE: Provide copy of OI-CH-4.
3 (OI-CH-4, Review prerequisites. All prerequisites met.
Att. 4) [ SAT ] [ UNSAT ]
4 (OI-CH-4, Record the following: Obtain current boron Att. 4, Step 1)
- RCS Tave concentration from TDB-V-1.B
[ SAT ] [ UNSAT ]
5 (OI-CH-4, Determine number of gallons of Determine number of gallons Att. 4, Step 2) makeup water to be added to be added.
using ERF computer per OI-ERFCS-1 or dilution formula in [ SAT ] [ UNSAT ]
TDB-V.12 CUE: STA has determined that 500 gallons of makeup water must be added.
CUE: Independent verifier has verified calculation and 500 gallons.
Page 4 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev JPM
Title:
Dilute RCS to Estimated Critical Conditions Boron Concentration STEP ELEMENT STANDARD 6 (OI-CH-4, Record the number of gallons Record 500 gallons to be Att. 4, Step 3) of makeup water to be added added.
7 (OI-CH-4, Ensure HC-269, Makeup Water Place HC-269 in DILUTE.
Att. 4, Step 4) Mode Selector Switch, is in DILUTE. [ SAT ] [ UNSAT ]
8 (OI-CH-4, Ensure FCV-269, Makeup FCV-269 is in CLOSE.
Att. 4, Step 5) Water Control Valve, is in CLOSE. [ SAT ] [ UNSAT ]
9 (OI-CH-4, Set FQS-269X, Demin Water Sets FQS-269X to 500 gallons Att. 4, Step 6) Flow Batching Switch, to the desired number of gallons of [ SAT ] [ UNSAT ]
water to be added NOTE: Candidate may choose to batch intermittently to verify proper response.
This is allowed by procedure so long as the total will be less than 500 gallons.
10 (OI-CH-4, Record initial Demin Water Att. 4, Step 7) Makeup Flow Totalizer reading [ SAT ] [ UNSAT ]
11 (OI-CH-4, Open FCV-269 FCV-269 opened.
Att. 4, Step 8)
[ SAT ] [ UNSAT ]
12 (OI-CH-4, Place FCV-269X, Demin Water FCV-269X in AUTO Att. 4, Step 9) Makeup Flow Control Valve, in AUTO [ SAT ] [ UNSAT ]
13 (OI-CH-4, With FC-269X, Demin Water FC-269X set to desired flow Att. 4, Step Makeup Flow Controller, set rate.
- 10) Demin Water flow to the desired flow rate. [ SAT ] [ UNSAT ]
CUE: Desired flow rate is XX gallons per minute.
Page 5 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev JPM
Title:
Dilute RCS to Estimated Critical Conditions Boron Concentration STEP ELEMENT STANDARD 14 (OI-CH-4, Verify VCT level and pressure Response is as expected.
Att. 4, Step respond as expected.
- 11) [ SAT ] [ UNSAT ]
15 (OI-CH-4, If unexpected reactivity effects Stop makeup flow by closing Att. 4, Step are observed, then stop the FCV-269 per Note 1 of Step 8
- 12) makeup flow and evaluate.
Unexpected reactivity effects [ SAT ] [ UNSAT ]
occur after XX gallons added.
CUE: Acknowledge report of unexpected reactivity effects Termination Criteria: Dilution is secured due to unexpected reactivity effects at XX gallons added.
Page 6 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No:
INITIAL Plant is currently shutdown in Mode 3. A plant CONDITIONS: startup is in progress per OP-2A, PLANT STARTUP, Attachment 2, CEA Withdrawal to Criticality Mode
- 2. Actions have been taken through Step 4 of OP-2A, Attachment 2, to withdraw Shutdown Groups A and B to the ARO position. TDB-V.1.B Estimated Critical Conditions Worksheet has been completed to determine final boron concentration.
INITIATING CUE: You have been directed to dilute the RCS to the ECC Boron Concentration as calculated in TDB-V.1.B, Estimated Critical Conditions Worksheet per Step 5 of OP-2A, Attachment 2.
Provide a copy of completed TDB-V.1.B as part of initiating cue.
Page 7 of 7
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV Location: Simulator Approximate Time: 20 minutes Start Time:__________________
End Time:___________________
Actual Time: _________________
Reference(s): K/A# 062000 A4.01 RO IMP:3.3 SRO IMP: 3.1 Ability to manually operate and/or monitor in the control room: All breakers (including applicable switchyard)
Procedures: OI-EE-1 Other (tech specs, etc)
Handout(s): OI-EE-1, Attachments 2 and 4 Task List#: 0290 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Date:
Page 1 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV Operators Name:
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:
Safety Considerations:
Comments:
Page 2 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV TASK STANDARD: The Candidate transferred buses 1A1 and 1A2 from 161 KV to 345 KV in accordance with OI-EE-1, Attachment
- 2. To meet the prerequisites, the candidate opened disconnect switch DS-T1.
INITIAL CONDITIONS: The plant is in hot shutdown following a normal plant shutdown using OP-3A. 345 KV is in service per OI-EG-
- 1. Breaker 3451-5 is not available.
INITIATING CUE:
You have been directed to transfer 4160 V buses 1A1 and 1A2 from 161 KV to 345 KV using OI-EE-1, Attachment 2.
Page 3 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV Critical Steps shown in gray STEP ELEMENT STANDARD Provide Candidate with a copy of OI-EE-1, Attachment 2
1 Prerequisite 2: 345 KV is in Initial Condition service per OI-EG-1 2 IF Gen G1 is shutdown, THEN CB-20 ensure DS-T1, T1 Disconnect Switch, is open per Attachment Determined that DS-T1 is
- 4. open.
[ SAT ] [ UNSAT ]
3 IF 3451-4 and 3451-5 Breakers Examiner CUE: Line are to be operated, THEN Dispatch states all notify Line Dispatch to ensure substation personnel are all Substation Personnel are clear of breakers.
clear of breakers.
4 The following Turbine Trip Behind CB-20 Lockout Relays are RESET:
Verified listed breakers are in
- 86-1/SVG1 the RESET position
- 86-2/SVG1
[SAT ] [ UNSAT ]
5 IF open and available, THEN Determined breaker 3451-4 close 3451-4 as follows: was not available
[SAT ] [ UNSAT ]
Page 4 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 6 IF open and available, THEN CB-20 close 3451-5 as follows:
Placed switch handle in synch
- a. Turn on Synchroscope for switch 3451-5 and turned 3451-5. clockwise.
[SAT ] [ UNSAT ]
7 Verify Synchroscope is CB-20 approximately at a 12 o'clock position. Verified Synchroscope dial at 12 oclock.
[SAT ] [ UNSAT ]
8 Close 3451-5. CB-20
- Placed Control switch for breaker 3451-5 in the AFTER-CLOSE (Red flag) position
- Verified RED light ON
[SAT ] [ UNSAT ]
9 CB-20 Turn off Synchroscope.
Turned switch handle in synch switch 3451-5 counter-clockwise.
[SAT ] [ UNSAT ]
Page 5 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 10 Transfer 1A1, Non-Vital Bus, to CB-20 22 KV as follows:
Placed 43/1A1-1A3 in
- a. Ensure 43/1A1-1A3, Fast MANUAL position Transfer Switch, is in MANUAL.
[SAT ] [ UNSAT ]
11 Turn on Synchroscope for CB-20 1A11. Placed switch handle in synch switch 1A11 and turned clockwise.
[SAT ] [ UNSAT ]
12 Verify Incoming and Running CB-20 voltages are approximately Verified voltages on Incoming matched. and Running voltmeters are approximately equal
[SAT ] [ UNSAT ]
13 Verify Synchroscope is CB-20 approximately at a 12 o'clock position. Verified Synchroscope dial at 12 oclock.
[SAT ] [ UNSAT ]
14 Close 1A11. CB-20
- Placed Control switch for breaker 1A11 in the AFTER-CLOSE (Red flag) position
- Verified RED light ON
[SAT ] [ UNSAT ]
Page 6 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 15 Open 1A31. CB-20
- Placed Control switch for breaker 1A31 in the AFTER-TRIP (Green flag) position
- Verified GREEN light ON
[SAT ] [ UNSAT ]
16 Turn off Synchroscope. CB-20 Turned switch handle in synch switch counter-clockwise.
[SAT ] [ UNSAT ]
17 IF the following condition for CB-20 Fast Transfer are met, Placed 43/1A1-1A3 in AUTO
- All lock-outs on CB-20 position have amber light on
- Appropriate 4160 volt [SAT ] [ UNSAT ]
breakers are not in pull-to-lock
- Power is available to transfer to THEN place 43/1A1-1A3, Fast Transfer Switch, in AUTO.
18 Transfer 1A2, Vital Bus, to 22 CB-20 KV as follows:
Placed 43/1A2-1A4 in
- a. Ensure 43/1A2-1A4, Fast MANUAL position Transfer Switch, is in MANUAL.
[SAT ] [ UNSAT ]
Page 7 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 19 Turn on Synchroscope for CB-20 1A22. Placed switch handle in synch switch 1A22 and turned clockwise.
[SAT ] [ UNSAT ]
20 Verify Incoming and Running CB-20 voltages are approximately Verified voltages on Incoming matched. and Running voltmeters are approximately equal
[SAT ] [ UNSAT ]
21 Verify Synchroscope is CB-20 approximately at a 12 o'clock position. Verified Synchroscope dial at 12 oclock.
[SAT ] [ UNSAT ]
22 Close 1A22. CB-20
- Placed Control switch for breaker 1A22 in the AFTER-CLOSE (Red flag) position
- Verified RED light ON
[SAT ] [ UNSAT ]
23 Open 1A42. CB-20
- Placed Control switch for breaker 1A42 in the AFTER-TRIP (Green flag) position
- Verified GREEN light ON
[SAT ] [ UNSAT ]
Page 8 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 0 JPM
Title:
Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 24 Turn off Synchroscope. CB-20 Turned switch handle in synch switch counter-clockwise.
[SAT ] [ UNSAT ]
25 CB-20 IF the following condition for Fast Transfer are met, Placed 43/1A2-1A4 in AUTO position All lock-outs on CB-20 have amber light on Appropriate 4160 volt breakers [SAT ] [ UNSAT ]
are not in pull-to-lock Power is available to transfer to THEN place 43/1A2-1A4, Fast Transfer Switch, in AUTO.
26 Balance loads between T1A1 EXAMINER CUE: Another and T1A2 as plant conditions Operator will balance loads allow.
Termination Criteria: Buses 1A1 and 1A2 are powered from 345 KV.
Page 9 of 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 INITIAL CONDITIONS: The plant is in hot shutdown following a normal plant shutdown using OP-3A. 345 KV is in service per OI-EG-
- 1. Breaker 3451-5 is not available.
INITIATING CUE: You have been directed to transfer 4160 V buses 1A1 and 1A2 from 161 KV to 345 KV using OI-EE-1, Attachment 2.
Page 10 of 10
Appendix D Scenario Outline Form ES-D-1 Facility: _Fort Calhoun Station__ Scenario No.: __1____ Op-Test No.: _______
Examiners: ____________________________ Operators: _____________________________
Initial Conditions: _100% power, diesel generator #1 is tagged out for maintenance.________________
Turnover: __Reduce power to <95% per grid operator.___________________
Event Malf. No. Event Event No. Type* Description 1 R-ATCO Reduce power to <95% per OP-4, Attachment 2.
N-BOPO 2 I-ATCO PIC-244 fails, causing HCV-204 (Letdown heat exchanger isolation valve ) to close. Alarms are for VCT level low and Pressurizer level TS-CRS high (CB-1,2,3/A2 Window B-2 and CB-1,2,3/A4 Window A-8). If pressurizer level goes >69.2%, TS 2.1.7 applies. Reference OI-CH-1 to restore letdown.
3 C-ATCO Inadvertent VIAS. AOP-23 Section IV.
TS-CRS C-ATCO 4 C-BOPO HCV-153 opens, causing quench tank level to decrease. Alarm is CB-1,2,3/A4 Window C-3. Action will be to restore level and close HCV-153 C-BOPO 5 TS-CRS Loss of 161 kV line. Alarm is CB-20/A15, Window A-1, 4160V Supply Breaker from 161KV Tripped, also Windows A-2 and A-3.
Since a fast transfer will occur, the ARP states to go to AOP-31.
T.S. reference 2.7 6 M-All Loss of 345kV line (LOOP) Reactor trips, SRO enters EOP-00 and after SPTAs, transfers to EOP-07, due to below failure. Upon operator manually closing breaker, power will be restored to one vital bus.
7 C-BOPO AFW valve HCV-1108A remains closed. It can be opened from the control panel. EOP-07 Step 6.1. Critical task is to restore AFW (CT) flow using either FW-54 or FW-10 to either steam generator prior to reaching 27% wide range level.
8 C-BOPO Diesel Generator #2 breaker fails to close automatically due to diesel not reaching rated speed. Once operators increase (CT) governor, breaker will close once required speed is reached. See Step 12 of EOP-07. Critical task is to perform this action before exiting EOP-07
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description NRC Scenario #1 SCENARIO
SUMMARY
NRC #1 The crew will assume the watch at 100% power, with diesel generator #1 out of service for maintenance, and instructions to downpower to less than 95% per OP-4, LOAD CHANGE AND NORMAL POWER OPERATION, Attachment 2, "Load Reduction".
The first event is the power reduction which will continue until an observable effect on the reactor is seen (approximately 1-2% load reduction).
The next event is a failure of PIC-244 which senses pressure downstream of letdown backpressure control valve. This causes letdown to isolate. Operator actions are per ARP-CB-1,2,3/A2 and require securing charging flow. Operators will use OI-CH-1, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION, to restore letdown and charging after manually overriding the HCV-204 Interlock Override Switch in DEFEAT. SRO will refer to Technical Specifications. T.S. 2.1.7 might apply if pressurizer level goes above 69.2%.
The next event is an inadvertent ventilation isolation actuation signal. Operator actions are per ARP-AI-30A/A33 and AOP-23 and include verifying that the VIAS was inadvertent and taking actions to reset the relays and restore detector well cooling. The SRO will refer to Technical Specifications. T.S. 2.15(3) applies.
The next event is a spurious opening of HCV-153, quench tank drain valve, causing quench tank level to decrease. Operator actions are per ARP-CB-1,2,3/A4 and include closing HCV-153 and taking action to restore quench tank level using deaerated water.
The next event is a loss of the 161 KV line. Operator actions are per ARP-CB-20/A15 and AOP-31, 161 KV GRID MALFUNCTIONS and include establishing balanced 4160 V bus loading by ensuring that condensate pump FW-2A, feed pump FW-4A and heater drain pump FW-5A are operating. SRO will refer to Technical Specifications. T.S. 2.7.2(c) applies.
Once actions for the loss of the 161 KV line are complete, there will be a loss of the 345 KV line, resulting in a LOOP. Diesel generator #2 does not reach rated speed and breaker does not automatically close, causing a station blackout. Crew will enter EOP-00 and perform standard post trip actions. Following diagnosis of event, SRO will transition to EOP-07, STATION BLACKOUT.
While performing the actions for a station blackout, the crew should recognize that HCV-1108A failed to open and will open it, restoring AFW flow to the steam generators. The crew will also take actions to raise the governor speed for diesel generator #2, which will result in the breaker closing automatically. Once this occurs and diesel generator #2 is feeding its respective bus, the scenario will be terminated.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _1__ Event No.: __1__ Page _1__ of ___
Event
Description:
__Reduce power to less than 95%._____________________________________
Time Position Applicants Actions or Behavior CRS Enter OP-4, LOAD CHANGE AND NORMAL POWER OPERATION, Attachment 2, Power Reduction CRS Ensure prerequisites are met and read notes on page 23.
CRS Maximize pressurizer spray. CRS may or may not choose to do this. This step is required if a change in boron concentration of greater than 50 ppm will occur.
ATCO Maximize pressurizer spray per OI-RC-7, REACTOR COOLANT SYSTEM PRESSURE CONTROL NORMAL OPERATION, Attachment 4, Maximum Pressurizer Spray for Mixing) (OP-4, Att. 1, Step 1)
ATCO Verify PC-103Y pressurizer press controller in automatic (OI-RC-7, Att. 4, Step 1.a)
ATCO Ensure proportional heaters bank P1 group 6 and P2 group 7 are in AUTO (OI-RC-7, Att. 4, Step 1.b)
ATCO Ensure PCV-103-1, PZR spray valve from loop 2A, and PCV-103-2, PZR spray valve from loop 1B, are in AUTO (OI-RC-7, Att. 4, Step 1.c)
ATCO Energize backup heaters by placing each control switch in ON (OI-RC-7, Att. 4, Step 1.d)
ATCO Ensure spray valves open automatically to terminate pressure rise
((OI-RC-7, Att. 4, Step 1.e)
ATCO Adjust PC-103Y setpoint pushbuttons to maintain 2100 psia ((OI-RC-7, Att. 4, Step 1.f)
CRS Read Cautions on page 24 CRS Direct ATCO and BOPO to lower reactor and turbine load to 95% per step 5.a-g.
ATCO Add boric acid per the reactivity plan and as directed by CRS. Use OI-CH-4, CHEMICAL AND VOLUME CONTROL SYSTEM MAKEUP OPERATIONS, Attachment 3, Normal Boration of the RCS (OP-4, Step 5.g)
ATCO Reviews prerequisites.
ATCO Record information required in Step 1.
ATCO Determine amount of boric acid to be added and record ATCO Ensure FCV-269, Makeup Water Control Valve, is in CLOSE.
Op-Test No.: _____ Scenario No.: _1__ Event No.: __1__ Page _1__ of ___
Event
Description:
__Reduce power to less than 95%._____________________________________
Event continues on next page ATCO Set FQS-269Y, Boric Acid Flow Batching Switch to desired amount of boric acid. Record initial totalizer reading.
ATCO Ensure Boric Acid Pump Recirculation Valves, HCV-264, HCV-257 are closed.
ATCO Place HC-269, Makeup Water Mode Select Switch, in BORATE.
ATCO Open FCV-269.
ATCO Place FCV-269Y, Boric Acid Makeup Flow Control Valve, in AUTO.
ATCO Use FC-269Y, Boric Acid Makeup Flow Controller, to set boric acid flow to desired flow rate.
ATCO Verify VCT level and pressure respond as expected.
ATCO Place FCV-269Y in CLOSE. Close FCV-269. Place HC-269 in DILUTE.
BOPO Lower Turbine Generator Load to maintain RCS TAVE program per TDB Figure III.1. (OP-4, Step 5.a)
ATCO Maintain pressurizer level within 4% of programmed level per OI-RC-8.
Level control in automatic. No operator action required. (OP-4, Step 5.c)
ATCO Maintain pressurizer pressure 2075-2150 PSIA per OI-RC-7. Pressure control in automatic. No operator action required (OP-4, Step 5.d)
BOPO Maintain steam generator levels at 55-75% NR per OI-FW-3. Level control in automatic. No operator action required (OP-4, Step 5.e)
ATCO Maintain ASI per OI-RR-1, REACTOR REGULATING SYSTEM NORMAL OPERATION, Attachment 4, ASI Control (OP-4, Step 5.f)
Review prerequisites.
Use group 4 CEAs to control ASI. Insert CEAs to make ASI more positive. Withdraw CEAs to move ASI negative.
Maintain ASI per TDB Figure III.23.a.
Op-Test No.: _____ Scenario No.: _1__ Event No.: __2__ Page ___ of ___
Event
Description:
__PIC-244 fails high, causing HCV-204 to close, isolating letdown. This occurs based on lead examiner cue, following visible reactor response on event 1.________________
Time Position Applicants Actions or Behavior ATCO Respond to alarms CB-1,2,3/A2 Window B1L, INTERMEDIATE LETDOWN PRESSURE HI-LO, and CB-1,2,3/A2, A1L, RELIEF VALVE CH-223 DISCHARGE TEMPERATURE HI ATCO Enter ARP-CB-1,2,3/A2 Window A1L ATCO Check TIA-205 Letdown Relief Line Temperature (Step 1)
ATCO Ensure TCV-202 and HCV-204 are closed. (Step 2)
ATCO Monitor TIA-205 to verify CH-223 and verify temperature is trending down.
(Step 2.1)
ATCO Place HC-204-1, Letdown Flow HCV-204 Interlock Override SW-1, in DEFEAT. (Step 2.2)
ATCO Restore letdown to service per OI-CH-1. (Step 2.3)
ATCO Start packing cooling pump minimum of 30 minutes prior to starting charging pump. Cue the applicant that this has occurred or is N/A. (OI-CH-1, Attachment 1, Step 1)
ATCO If desired by SM, equalize boron concentration in charging pump. Cue that this is N/A. (Step 2)
ATCO Ensure LCV-218-2, VCT outlet valve, is open and in AUTO (Step 3)
ATCO Ensure HCV-247, charging to RC loop 1A isolation valve, is open. (Step 4)
ATCO Ensure either HCV-247 AND HCV-238 or HCV-248 AND HCV-239 are open. (Step 5)
ATCO At SMs discretion, place TCV-211-2, ion exchangers bypass valve to BYP IX. Cue this step as N/A. (Step 6)
ATCO Place HC-101-3, limiter bypass switch, in BYPASS. (Step 7)
ATCO Place HIC_101-1/101-2, letdown throttle valve controller, in MANUAL.
(Step 8)
ATCO Close LCV-101-1 and LCV-101-2, letdown heat exchanger throttle valves.
(Step 9)
ATCO Place HC-101-2, letdown heat exchanger valves selector switch in the desired position per the SM. Cue to leave it in its current position. (Step 10)
ATCO Place PIC-210, letdown pressure controller, in MANUAL. (Step 11)
ATCO Throttle PIC-210 to approximately 10% open. (Step 12)
Op-Test No.: _____ Scenario No.: _1__ Event No.: __2__ Page ___ of ___
Event
Description:
__PIC-244 fails high, causing HCV-204 to close, isolating letdown. This occurs based on lead examiner cue, following visible reactor response on event 1.________________
Event continues on next page.
ATCO Position charging pumps mode select standby switch to select the desired backup charging pumps start sequence. Cue to leave it in its current configuration. (Step 13)
ATCO Start charging pump 1C (?,whichever one was running before letdown isolated). (Step 14)
ATCO Open HCV-204, RC to letdown heat exchanger isolation valve. (Step 15)
ATCO Open TCV-202, letdown to regenerative heat exchanger isolation valve.
(Step 16)
ATCO Use HIC-101-1/101-2 to initiate letdown flow while adjusting PCV-210 to maintain letdown pressure approximately 300 psig. (Step 17)
ATCO Balance letdown and charging flows to maintain pressurizer level. (Step 18)
ATCO Place HC-101-3 in NORMAL. (Step 19)
ATCO Place HIC-101-1/1-102 in AUTO per OI-RC-8.
ATCO Manually adjust HIC-101-1/101-2 AND PIC-201 until following parameters are met:
- Indicated pressurizer level (red pen) matches programmed level setpoint (green pen) on LR-101X
- PIC-210 is maintaining 200-400 psi. (OI-RC-8, Att. 3, Step 2)
ATCO Adjust the bias on HIC-101-1/101-2 until the top scale indicates 50% (red pointer aligned with red dot). (Step 3)
ATCO Place HIC-101-1/101-2 manual/auto transfer switch to BAL, then to AUTO (Step 3)
ATCO Place PIC-210 in AUTO. (OI-CH-1, Att. 1, Step 20)
ATCO If TIA-205 temperature trends up, ensure TCV-202 and HCV-204 are closed and enter AOP-12. This step is N/A because temperature does not increase. (ARP-CB-1,2,3/A2 A1L Step 2.4)
ATCO If TIA-205 temperature continues to trend down and alarm clears, place HC-204-1 in AUTO. (Step 3)
ATCO Check PIA-210 approximately 300 psig. (Step 3.1)
ATCO Adjust PIC-210 to restore letdown pressure if required (Step 3.2)
ATCO Monitor pressurizer quench tank (Step 4)
ATCO Perform OP-ST-RC-3001 to determine RCS leakage. (Step 5)
Op-Test No.: _____ Scenario No.: _1__ Event No.: __2__ Page ___ of ___
Event
Description:
__PIC-244 fails high, causing HCV-204 to close, isolating letdown. This occurs based on lead examiner cue, following visible reactor response on event 1.________________
CRS TS 2.1.7 might apply if pressurizer level gets above 69.2%.
Op-Test No.: _____ Scenario No.: _1__ Event No.: __3__ Page ___ of ___
Event
Description:
__Inadvertent Ventilation Isolation Actuation Signal. This occurs based on lead examiner cue.___________________________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm AI-30A/A33-1 Window C-6, VENTILATION ISOLATION COMMAND.
ATCO Enter ARP- AI-30A/A33-1 Window C-6.
ATCO Verify 86B/VIAS is tripped. Verify valves isolated by VIAS are closed.
ATCO Verify that none of the following relays are tripped: 86B/CRHS, 86B/SIAS, 86B/CSAS CRS Direct entry into AOP-23, RESENT OF ENGINEERED SAFEGUARDS,Section IV, Reset of Containment Isolation Actuation Signal (CIAS) and Ventilation Isolation Actuation Signal (VIAS)
ATCO Verify VIAS is inadvertent: No PPLS, CPHS, SIAS, or CSAS. RM-051, RM-052, RM-062 not in alarm.
ATCO Ensure BOTH emergency operate THINK switches, SE-A and SE-B, are in NORM ATCO Ensure all RCP Coolers CCW valves are open.
ATCO Ensure hand controller thumbwheel is set fully counter-clockwise for any of the following valves that are open: HCV-400C, HCV-401C, HCV-402C, HCV-403C.
ATCO Ensure relays are reset: 86A/CIAS, 86B1/CIAS, 86B/CIAS, 86A1/CIAS ATCO Reset 86/AI-43A, 86/AI-43B.
ATCO Restore detector well cooling by opening HCV-467A, B, C, D, and starting any detector well cooling fan ATCO Ensure 86A/CRHS, 86B/CRHS, 86B1/CRHS, and 86A1/CRHS reset.
ATCO Ensure 86A/VIAS, 86B1/VIAS, 86B/VIAS, and 86A1/VIAS reset.
ATCO Depress both 94A/VIAS-RESET and 94B/VIAS-RESET pushbuttons.
ATCO Complete Attachment D, Equipment Operated by VIAS.
TS-CRS Enter TS 2.15(3) for loss of isolation logic subsystem (?)
Restore to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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 />; operation can continue without containment ventilation isolation signals available if ventilation isolation valves are closed.
Op-Test No.: _____ Scenario No.: _1__ Event No.: __4__ Page ___ of ___
Event
Description:
_____HCV-153 opens causing quench tank level to decrease. This occurs based on lead examiner cue.____________________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A4 Window C-3, QUENCH TANK LEVEL HI-LO ATCO Enter ARP-CB-1,2,3/A4 Window C-3 ATCO Check pressurizer quench tank level on LIA-132. (Step 1)
ATCO Restore PQT Level per OI-RC-6, PRESSURIZER QUENCH TANK NORMAL OPERATION. (Step 2)
BOPO Open dearated water header isolation valves HCV-1560A and 1560B.
(OI-RC-6, Attachment 1, Step 1)
ATCO Monitor PIA-131, Pressurizer Quench Tank pressure. (Step 2)
ATCO Open quench tank vent valve, HCV-155, as necessary to maintain pressure less than 10 psig. (Step 3)
BOPO When filled to desired level (typ. 73%), close HCV-1560A, HCV-1560B. (Step 4)
ATCO Check for leakage from PQT to RCDT and/or containment sump. (ARP-CB-1,2,3/A4, Window C-3, Step 2.1)
ATCO Determine that HCV-153 is open.
ATCO Close HCV-153. (OI-RC-6, Attachment 2, Step 5)
Op-Test No.: _____ Scenario No.: _1__ Event No.: __5__ Page ___ of ___
Event
Description:
_____Loss of 161 kV line. This occurs based on lead examiner cue.__________
Time Position Applicants Actions or Behavior BOPO Respond to alarms: CB-20/A15 Windows A-1, BREAKER 111 TRIPPED, Window A-2, 161 KV SUPPLY BKR LOCKOUT RELAY OPERATED 86/161, Window A-3, BREAKER 110 TRIPPED BOPO Enter ARP-CB-20/A15, Windows A-1, A-2, A-3 (all have the same actions)
BOPO Notify Energy Marketing and Shift Manager. Cue from Energy Marketing that the 161 kV line has been lost and no estimate for its return. (ARP-CB-20/A15 A-3, Step 2)
BOPO Verify Fast Transfer has occurred and go to AOP-31. (Step 3.1)
CRS Enter AOP-31, 161 KV GRID MALFUNCTIONS,Section II, All 4160 V Buses Fed from 22 KV BOPO Ensure 2 condensate pumps, 2 feed pumps, and 2 heater drain pumps are operating. (AOP-31, Step 1)
BOPO Adjust main generator terminal voltage less than 22,000 volts per the following: N/A. (Step 2)
BOPO Establish balanced 4160 V bus loading on T1A1 and T1A2 by ensuring all the following are operating: condensate pump FW-2A, feed pump FW-4A, and heater drain pump FW-5A. (Step 3)
BOPO Verify voltage is greater than 430 volts on all the following buses: 1B3A, 1B3B, 1B3C, 1B4A, 1B4B, 1B4C. If not, refer to attachment A to determine loads to realign. (Step 4)
CRS Notify NRC of loss of 161 KV within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. (Step 5)
BOPO Match flags on following breakers: 110, 111, 1A31, 1A33, 1A42, 1A44.
(Step 6)
CRS Enter TS 2.7.2(c) for loss of 161 kV line inop-ing both house service transformers.
May be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, after which it must be placed in a hot shutdown condition within following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Notify NRC Operations Center by phone within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of inoperability of transformers.
Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page _12__ of _12_
Event
Description:
_____Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout. AFW valve HCV-1108A remains closed but can be opened from the control panel. The loss of the 345kV line occurs based on examiner cue. The other two malfunctions are preprogrammed.___________________
Time Position Applicants Actions or Behavior CRS Enter EOP-00, STANDARD POST TRIP ACTIONS ATCO BOPO Respond to reactor trip. Perform SPTAs, EOP-00, STANDARD POST TRIP ACTIONS ATCO Verify reactivity control established: reactor power is lowering, startup rate is negative, no more than 1 regulating or shutdown CEA not inserted, and monitor for uncontrolled RCS cooldown (EOP-00 Step 1)
BOPO Verify turbine tripped as indicated by stop and intercept valves indicating closed. (EOP-00, Step 2)
BOPO Ensure all of the following generator breakers tripped: output breakers 3451-4, 3451-5, and field breaker 41E/G1F. (EOP-00 Step 3)
BOPO Verify buses 1A3 and 1A4 energized (EOP-00 Step 4). Transition to contingency column.
BOPO Minimize DC loads per attachment 6. Ensure diesel generator is started for affected bus (EOP-00 Step 4.1).
BOPO Direct an auxiliary operator to perform the following:
BOPO Place DC Bus 2 breakers EE-8G-CB12, 400 Cycle Inverter EE-21 and EE-8G-CB8, Emergency Lighting Pnl ELP-2 Transfer Switch in OFF (EOP Attachment 6, Step 1.a)
BOPO Place DC Bus 1 breaker EE-8F-CB11, Aux Bldg Emgy Lighting Panel ELP-1 in OFF (EOP Attachment 6, Step 1.b)
BOPO Place 125 VDC Panel DC-PNL-1, Breaker 15, ELP-5 Emergency Lighting Panel in OFF (EOP Attachment 6, Step 1.c)
BOPO Vent hydrogen from generator using G-03, Generator ST-2 Vent Header Isolation Valve behind AI-134 (EOP Attachment 6, Step 2)
BOPO Check that Buses 1A1 and 1A2 are energized (EOP-00 Step 6). No contingency actions.
BOPO Check that 125 VDC buses 1 and 2 are energized.
BOPO Verify instrument air is available by both of the following: IA pressure greater than or equal to 90 psig and at least one air compressor running (EOP-00, Step 8) Contingency action is to restore instrument air, but no power at this time to run the pump or compressor.
Events description continued on next page.
Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page ___ of _12_
Event
Description:
_____Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout._______________
Time Position Applicants Actions or Behavior ATCO Determine normal CCW system operation: At least one CCW pump operating, CCW pump discharge pressure is greater than or equal to 60 psig, at least one RW pump is operating, and RCP coolers CCW valves HCV-438A/B/C/D are open if CCW pump discharge pressure is greater than 40 psig (EOP-00 Step 9). Transition to contingency action.
ATCO Contingency action is to stop RCPs which has already occurred. (EOP-00 Step 9.1)
ATCO Verify all of the following: PZR level 30-70%, trending to 45-60%, RCS subcooling greater than or equal to 20°F. (EOP-00, Step 10)
ATCO Verify all of the following: RCS pressure 1800-2300 psia, trending to 2050-2150 psia, and PORVs are closed. (EOP-00, Step 11)
ATCO Verify forced circulation with at least one RCP operating, transition to contingency column (EOP-00, Step 12)
BOPO Place HIC-909, Main Steam Dump Valves MAN/AUTO CNTRLR in MAN (EOP-00, Step 12.2.a)
ATCO Verify development of natural circulation flow in at least one loop by all of the following: Core T less than or equal to 50°F, difference between CETs and RCS TH is less than or equal to 10°F, RCS subcooling greater than or equal to 20°F, and TH and TC are stable or lowering. (EOP-00, Step 12.2.b)
BOPO Verify Main Feedwater is restoring level in at least one steam generator (EOP-00, Step 13). Transition to contingency step 13.1.b, c, d, or e.
BOPO Initiate AFW using diesel driven AFW pump to Feed Ring (EOP-00, Step 13.1.b) OR BOPO Initiate AFW using FW-10, AFW pump to AFW nozzle (EOP-00 Step 13.1.c) OR BOPO Initiate AFW using FW-10 AFW pump to Feed Ring by starting FW-10 and opening HCV-1383, Aux FW/FW Header Cross Connect Valve (EOP-00, Step 13.1.d) OR BOPO Initiate AFW using FW-54, diesel AFW pump, to AFW nozzles by starting FW-54, directing an auxiliary operator to unlock and close FW-170, Aux Feedwtr X-Tie Vlv HCV-1384 Outlet Valve, and opening HCV-1384, Aux FW/FW Header Cross Connect Valve (EOP-00, Step 13.1.e)
Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page ___ of _12_
Event
Description:
_____Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout._______________
Event description continues on next page BOPO Verify Steam Dump and Bypass valves are controlling RCS TC 525-535°F and steam generator pressure 850-925 psia (EOP-00 Step 14). Transition to contingency action 14.c(?).
BOPO Operate at least one of the air assisted main steam safety valves MS-291 and/or MS 292 (EOP-00, Step 14.c)
ATCO Verify normal containment conditions: no unexpected rise in sump level; no containment area radiation monitor alarms; RM-051, RM-052, and RM-062 not in alarm; no steam generator blowdown or condenser off gas radiation monitors in alarm or trending upward; containment pressure less than 3 psig; and containment temperature less than 120°F. (EOP-00, Step 15)
CRS Determine that EOP-07 should be implemented per EOP-00 Section 6.0 (EOP-00, Step 16)
CRS Enter EOP-07, STATION BLACKOUT CRS Confirm SPTAs performed (EOP-07, Step 1)
CRS Confirm SBO diagnosis by verifying safety function status check (EOP-07, Step 2)
CRS Implement the Emergency Plan (EOP-07, Step 3)
ATCO/BOPO Monitor the Floating Steps (EOP-07, Step 4)
BOPO If condenser vacuum less than 19 inches Hg, ensure steam dump and bypass valves and turbine stop valves are closed. (EOP-07, Step 5)
BOPO If feeding through Feed Rings, verify S/G levels 35-85% NR (EOP-07, Step 6) OR BOPO If feeding through AFW nozzles, maintain S/G level 35-85% NR by ensuring FW-10 operating, both AFW isolation valves, HCV-1107A and (CT) HCV-1108A are open, and locally throttle both AFW isolation valves HCV-1107B and HCV-1108B. (EOP-07, Step 6.1) BOPO will have to take action to open HCV-1108A.
BOPO Maintain S/G pressure 850-1000 psia by performing EOP-07, Step 7.a, or c (Step B has local operator actions)
BOPO Steam S/Gs by ensuring MS-164 Main Steam Line A Steam Dump to Atmosphere Isolation Valve is open (local action), ensure MS-407, nd Atmospheric Dump Valve HCV-1040 2 Isolation is open (local action), and control HCV-1040, Atmospheric Dump Valve. (EOP-07, Step 7.a) OR BOPO Operate FW-10, Steam AFW pump (EOP-07, Step 7.c)
Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page ___ of _12_
Event
Description:
_____Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout._______________
Event description continued on next page BOPO Trip all of the following normal and standby supply feeder breakers to the vital 4160V buses: 1A13, 1A33, 1A24, 1A44. (EOP-07, Step 8)
BOPO Ensure all the following breakers tripped: CW-1C (circ water pump), FW-5C (heater drain pump), FW-2C (condensate pump), FW-6 (electric AFW pump), FW-4C (feed pump), RC-3C (RCP), RC-3D (RCP), AC-10A/B/C/D (raw water pumps), SI-1A/B (LPSI pumps) (EOP-07, Step 9)
BOPO Verify both diesels started. (Maintenance on DG#1 will preclude emergency start) (EOP-07, Step 10)
BOPO If D-2 is operating and none of the following lockout relays are tripped:
86/1A24, 86/1A44, 86/1A4-TFB, then synchronize and close breaker 1AD2 (EOP-07, Step 12)
CRS Direct exit from EOP-07 and entry into EOP-02, LOSS OF OFF-SITE POWER/LOSS OF FORCED CIRCULATION (EOP-07, Step 13)
Scenario is terminated after successful transition from EOP-07 is made.
Appendix D Scenario Outline Form ES-D-1 Facility: _ Fort Calhoun Station__ Scenario No.: __2____ Op-Test No.: _______
Examiners: ____________________________ Operators: _____________________________
Initial Conditions: 100% power. Condensate pump FW-2B is currently in service ____________
Turnover: ____. Rotate condensate pumps FW-2B and FW-2C._____________________________
Event Malf. Event Event No. No. Type* Description 1 N/A N-BOPO Rotate condensate pumps FW-2B and FW-2C per OI-FW-1 Attachment 4.
2 C-ATCO Charging pump CH1B trips. Alarm CB-1,2,3/A2, Window A-6L.
TS-CRS This isolates letdown. Another charging pump should be started per OI-CH-1. T.S. 2.15(5) requires CH-1B and required instruments for AI-179 I-BOPO 3 LT-903Y (Steam generator RC-1 level transmitter) degrades over a 10 minute period until it fails. This will shift FWCS to manual at the last good signal, requiring operator action to restore level. Alarm is ARP-DCS-FW, L0903E_AL5.
4 I-ATCO TS-CRS Pressurizer pressure instrument fails high. Possible TS if pressure falls below 2075 psia. Uses ARP-CB-1,2,3/A4 Window B-4 Pressurizer Pressure Deviation C-ATCO 5 C-BOPO Dropped CEA 4-01. Alarm CB-4/A8 Window A-5L. This will send TS-CRS the operators to AOP-02, which has actions to stabilize the plant.
T.S. 2.10. Because the rod is dropped, this will require a rapid downpower per AOP-05.
R-ATCO 6 N/A N-BOPO Rapid downpower per AOP-05.
M-All 7 RCP Seal Cooler Leak of CVC16. Due to high RCP temperatures, AOP-35 will be entered. AOP-35 will direct the operators to trip the reactor and enter EOP-00. This is an intersystem LOCA. EOP-03 will be entered after SPTAs are performed.
8 C-BOPO Turbine fails to trip. Critical task is for BOP to immediately trip the (CT) turbine before performing other SPTAs 9 C-ATCO HCV-438C fails to close on demand. This LOCA cannot be C-BOPO isolated. It will require a cooldown and depressurization to stop the LOCA. Critical task is to commence a cooldown and (CT) depressurization.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description NRC Scenario #2 SCENARIO
SUMMARY
NRC #2 The crew will assume the watch at 100% power with no equipment out of service and instructions to swap condensate pumps FW-2B and FW-2C.
The first event is swapping out the two condensate pumps per OI-FW-1, CONDENSATE SYSTEM NORMAL OPERATION, Attachment 4.
The next event is a trip of charging pump CH-1B, which secures charging flow. Operator actions are per ARP-CB-1,2,3/A2 and include securing letdown. Operator action is then to restore charging and letdown per OI-CH-1, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION. SRO will refer to the Technical Specification. T.S. 2.15(5) applies for the loss of CH-1B.
The next event is a degradation of LT-903Y to 40% over a 10 minute period before failing low, resulting in an incorrect setting on the feedwater digital control system. Operator actions are per ARP-DCS-FW, L0903E_AL5 and include the operator taking manual control of the main feed regulating valve to restore steam generator levels to program.
The next event is the controlling pressurizer pressure instrument, PT-103X failing high.
Operator actions are per ARP-CB-1,2,3/A4 and include taking the controller to manual to maintain pressurizer pressure, and shifting pressure control to PC-103Y. SRO will refer to Technical Specifications. T.S. 2.10.4(5)(a)(ii) applies if pressure falls below 2075 psia.
The next event is a CEA drop of CEA 4-01. Operator actions are per ARP-CB-4/A8 and AOP-02, CEA AND CONTROL SYSTEM MALFUNCTIONS and include stabilizing the plant and taking action to lower reactor power to less than or equal to 70% T within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per AOP-5, EMERGENCY SHUTDOWN. SRO will refer to Technical Specifications. T.S. 2.10.2(e) applies.
Once actions have been taken to start lowering reactor power to less than 70%, a 100%
severity RCP seal cooler leak on CVC 16 will be cued. Operator actions are from ARP-CB-1,2,3/A1 and AOP-35, REACTOR COOLANT PUMP MALFUNCTIONS. At this time one of the bearing temperatures will exceed the trip criteria for the RCP. Operators will manually trip the reactor and enter EOP-00. They will also trip the RCP whose trip criteria was exceeded (RCP 3A).
When the operators manually trip the reactor, the turbine will fail to trip and the operators will take action to manually trip the turbine. After actions of EOP-00 are complete, the SRO will direct entry into EOP-03 for a loss of coolant accident.
When operators attempt to isolate the leak by closing HCV-438C, it fails to close. Operators will commence a cooldown and depressurization to enable local operator action to close this valve.
The scenario can be terminated once actions have begun to cooldown and depressurize the RCS to allow local operator action to close HCV-438C.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2___ Event No.: __1___ Page ___ of ___
Event
Description:
___Rotate condensate pumps FW-2B and FW-2C.________________
Time Position Applicants Actions or Behavior BOPO Review OI-FW-1, CONDENSATE SYSTEM NORMAL OPERATION, Attachment 4, Rotating Condensate Pumps prerequisites.
BOPO Select condensate pump to be started (in this case, FW-2C). (OI-FW-1, Att. 4, Step 1)
BOPO Suspend GARDEL data feed IAW OI-ERFCS-2, CORE MONITORING SYSTEMS, Att. 6, Suspending GARDEL Data Feed (Step 2) NOTE:
GARDEL is NOT modeled in the simulator, so these steps will not be performed.
BOPO Perform the following: ensure 43/FW switch in off and verify 43/FW Transfer Switch Off-Auto (CB-10,11/A10, B-6L) is in alarm. (Step 3)
BOPO Start condensate pump FW-2C. (Step 4)
BOPO Verify ammeter returns to less than 250 amps in less than 15 seconds and stabilizes (Step 5)
BOPO Ensure condensate pump minimum flow maintained by verifying discharge pressure 490-600 psig. If recirculation valve FCV-1172 is not operating properly, then establish minimum flow by opening FCV-1172 bypass valve, FW-273 (Step 6)
BOPO Monitor FW-2C for any the following: unusual noise or vibration, lube oil level, seal water inlet pressure (70-90 psig on PI-1214), FW-2C discharge pressure (490-600 psig on PI-1232C at pump), FW-2C discharge pressure (490-600 psig on PI-1181C in CR), check ERF computer points. ERF points are F1172, T1179A, T1179B, T1184C, T1185C. (Step 7)
BOPO Stop FW-2B (Step 8)
BOPO Place FW-2B in AFTER-STOP or PULL-STOP (Step 9) (optional)
BOPO Verify FW-2B ammeter drops to zero (Step 10)
BOPO Observe check valve closure by verifying FW-2B not rotating in reverse direction (Step 11)
BOPO Ensure Post-SIAS/CSAS running condensate pump switch 43-SIAS/FW2 is positioned to FW-2C. (Step 12)
BOPO Place 43/FW Switch in AUTO and verify alarm clears (Step 13)
BOPO Restore GARDEL data feed IAW OI-ERFCS-2, Attachment 7, Restoring the GARDEL Data Feed (Step 14) NOTE: GARDEL not modeled in simulator, so these steps will not be performed.
Op-Test No.: _____ Scenario No.: __2___ Event No.: __2___ Page ___ of ___
Event
Description:
___Charging pump CH-1B trips. Lead examiner will cue the malfunction once condensate pumps have been rotated.______________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A2 Window A-6L, CHARGING FLOW LO, and Window C-6U, CHARGING PUMPS TRIP ATCO Enter ARP CB-1,2,3/A2, Window A-6L ATCO Check charging header flow on FIA-236 (ARP-CB-1,2,3/A2, A-6L, Step 1)
ATCO If charging flow lost, then isolate letdown by closing TCV-202 and HCV-204 (Step 2)
ATCO If charging flow is less than 30 gpm, then check charging pump operation, valve alignment, pipe break, and charging pump discharge or suction relief valve. (Step 3)
ATCO Rotate charging pumps per OI-CH-1, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION, Att. 1, Startup of Charging and Letdown (Step 4)
ATCO Review prerequisites (OI-CH-1, Att. 1)
ATCO Start selected packing cooling pump minimum of 30 minutes prior to starting charging pump CH-1C. (Cue operators that this is N/A or already accomplished) (OI-CH-1, Att. 1, Step 1) NOTE: Cue operators that boron concentration equalization per Step 2 is not necessary.
ATCO Ensure LCV-218-2, VCT Outlet Valve, is open with control switch in AUTO (Step 3)
ATCO Ensure HCV-247, Charg to RC Loop 1A Isolation Valve, is open. (Step 4)
ATCO Ensure either HCV-247 and HCV-238 or HCV-248 and HCV-239 are open (Step 5)
ATCO Place TCV-211-2, Ion Exchangers Bypass Valve to BYP IX. (Step 6)
ATCO Place HC-101-3, Limiter Bypass Switch, in BYPASS (Step 7)
ATCO Place HIC-101-1/101-2, Letdn Throttle Valve Controller, in MANUAL (Step 8)
ATCO Close letdown heat exchanger throttle valves LCV-101-1 and LCV-101-2 (Step 9)
ATCO Place HC-101-2, Ltdn Ht Exch Vlvs Selector Sw in the desired position per shift manager. (Step 10) CUE to leave it in current position.
Event description continues on next page
Op-Test No.: _____ Scenario No.: __2___ Event No.: __2___ Page ___ of ___
Event
Description:
___Charging pump CH-1B trips___________________________________
Time Position Applicants Actions or Behavior ATCO Place PIC-210, Letdown Pressure Cntrlr, in MANUAL (Step 11)
ATCO Throttle PIC-210 to about 10% open (Step 12)
ATCO Position charging pumps mode select standby switch to CH-1A-1B (Step 13)
ATCO Start CH-1C (Step 14)
ATCO Open HCV-204, RC to Ltdn Ht Exch Isolation Valve (Step 15)
ATCO Open TCV-202, Ltdn to Regen Ht Exch Isolation Vavle (Step 16)
ATCO Use HIC-101-1/101-2 to initiate letdown flow while adjusting PCV-210 to maintain letdown pressure around 300 psig (Step 17)
ATCO Balance charging and letdown flows to maintain pressurizer level (18)
ATCO Place HC-101-3 in NORMAL (Step 19)
ATCO If desired, place HIC-101-1/101-2 (per OI-RC-8, REACTOR COOLANT SYSTEM LEVEL CONTROL NORMAL OPERATION, Att. 3 Transferring Letdown Controller from Manual to Automatic) (Step 20)
ATCO Ensure HIC-101-1/101-2 is in MANUAL (OI-RC-8, Att. 3, Step 1)
ATCO Manually adjust HIC-101-1/101-2 and PIC-210 until indicated pressurizer level matches programmed level on LR-101Y, and PIC-210 maintaining 200-400 psi. (Step 2)
ATCO Adjust bias on HIC-101-1/101-2 until top scale indicates 50%
(Step 3)
ATCO Place HIC-101-1/101-2 Manual/Auto Transfer Switch to BAL, then to AUTO (Step 4)
ATCO Place PIC-210 in AUTO (OI-CH-1, Att. 1, Step 20)
ATCO If desired place ion exchangers in service by placing TCV-211-2 to IX (Step 21)
ATCO If desired, check letdown pulsation dampener pressures per OI-CH-1, Att.
6 (Step 22)
CRS Evaluate evolution for appropriate Equipment/System Usage Cycles (Step 23)
CRS Enter TS 2.15(5) for loss of CH-1B and controls for AI-185 Restore in 7 days or be in hot shutdown within next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Op-Test No.: _____ Scenario No.: __2___ Event No.: __3___ Page ___ of ___
Event
Description:
___LT-903Y degrades to 40% over 10 minute period before failing low. This malfunction should be entered with the charging pump trip._____________________________
Time Position Applicants Actions or Behavior BOPO Respond to alarm DCS-FW, L0903E_AL5 and H1105_AL1 BOPO Enter ARP-DCS-FW, L0903E_AL5 BOPO Ensure FWCS IN MANUAL is displayed for bad channel on feedwater regulating system display (Step 2)
BOPO Control steam generator level by either selecting OUT on level controller LC0903_1E and adjusting as necessary to control feed reg or bypass valves to maintain levels, OR take manual control of feed reg or bypass valves and adjust as necessary to maintain steam generator levels (Step 4)
BOPO Dispatch operator to verify level indication at AI-179. Level indication at AI-179 is not affected by this failure. (Step 6)
CRS Reference TDB-VIII, EQUIPMENT OPERABILITY GUIDANCE. (Step 7)
BOPO Notify system engineer and I&C of alarm condition. (Step 8)
Op-Test No.: _____ Scenario No.: _2__ Event No.: __4__ Page ___ of ___
Event
Description:
__Controlling pressurizer pressure instrument, PT 103X fails high. Lead examiner will cue malfunction._________________________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A4 Window A-4 PRESSURIZER PRESSURE OFF NORMAL HI-LO CHANNEL X.
ATCO Enter ARP-CB-1,2,3/A4 Window A-4.
CRS Apply T.S. 2.10.4(5)(a)(ii) is pressure less than or equal to 2075 psia.
(Step 2.1)
ATCO Check pressurizer heaters are energized. (Step 2.2)
ATCO Ensure pressurizer spray valves are closed. (Step 2.3)
ATCO Ensure pressurizer heater control switches are in AUTO (Step 2.4)
ATCO Check pressurizer level for decreasing trend (Step 2.5)
ATCO Check VCT level for level trend (Step 2.6)
ATCO Monitor pressurizer pressure and the operation of PC-103X. (Step 4)
ATCO If PC-103X is not controlling pressure, shift pressure control to PC-103Y (Step 4.1)
ATCO If necessary, take manual control of pressurizer pressure. (Step 4.2)
TS-CRS Possible technical specification call depending on how low pressurizer pressure falls before ATCO takes action. TS 2.10.4(5)(a)(ii) if pressure falls below 2075 psia.
CRS Notify Work Week manager of failure.
Op-Test No.: _____ Scenario No.: _2__ Event No.: __5, 6__ Page ___ of ___
Event
Description:
__CEA 4-01 drop, requiring a rapid downpower using AOP-05. Lead examiner will cue the CEA drop.__________________________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-4/A8, Window A-5L, DROPPED ROD, Window B-1U, ROD POSITION DEVIATION LOW LIMIT, Window B-1L, ROD POSITION DEVIATION LOW-LOW LIMIT, and CB-4/A20, Window B-6, ROD DROP NUCLEAR INSTRUMENTATION CHANNEL ATCO Enter ARP-CB-4/A8, Window A-5L.
ATCO Verify at least one CEA is at Lower Mechanical Stop with green rod position indicator light on. (ARP-CB-4/A8, Window A-5L, Step 1)
TS-CRS Possible momentary entry into TS 2.10.4(5)(a)(ii) for pressurizer pressure less than 2075 psia.
CRS Enter AOP-02, CEA AND CONTROL SYSTEM MALFUNCTIONS,Section III, Misaligned Group 4 CEA (ARP-CB-4/A8, Window A-5L, Step 2)
CRS Review cautions, prerequisites and notes of AOP-02.
BOPO Adjust turbine load to match reactor power (AOP-02, Step 3)
ATCO Establish steady reactor power (AOP-02, Step 4)
ATCO Ensure RCS pressure is 2075 to 2150 psia (AOP-02, Step 5)
ATCO Ensure PZR level is within 2% of program level (AOP-02, Step 6)
ATCO Reset rod drop detection circuit bistables on all RPS linear power channels and power range control channels drawers (AOP-02, Step 7)
ATCO Verify ROD DROP NUCLEAR INSTRUMENTATION CHANNEL alarm resets (AOP-02, Step 8)
CRS Notify system operations of power reduction (AOP-02, Step 9)
CRS Notify reactor engineer of CEA misalignment (AOP-02, Step 10)
CRS If CEA misaligned greater than 18 inches, go to Step 21 (AOP-02, Step 11)
ATCO Lower reactor power to less than or equal to 70% T power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of misalignment using boration from the SIRWT per AOP-05, EMERGENCY SHUTDOWN (Step 21)
ATCO Ensure one charging pump is running (AOP-05, Step 1.a)
ATCO Open LCV-218-3, Charging Pump Suction SIRWT Isolation Valve (AOP-05, Step 1.b)
ATCO Close LCV-218-2, VCT Outlet Valve (AOP-05, Step 1.c)
ATCO/BOPO Maintain the following plant parameters during power reduction: TC 527-545°F, PZR 45-60% (AOP-05 Step 3)
Op-Test No.: _____ Scenario No.: _2__ Event No.: __5, 6__ Page ___ of ___
Event
Description:
__CEA 4-01 drop, requiring a rapid downpower using AOP-05. Lead examiner will cue the CEA drop.__________________________________________________________________
Event description continued on next page Op-Test No.: _____ Scenario No.: _2__ Event No.: __5,6__ Page ___ of ___
Event
Description:
__ CEA 4-01 drop, requiring a rapid downpower using AOP-05.
Time Position Applicants Actions or Behavior ATCO Maximize pressurizer heaters and spray (AOP-05, Step 4)
CRS Direct shift chemist to sample the RCS to satisfy TS 3.2, Equipment and Sampling Tests (AOP-02, Step 22)
CRS Enter TS 2.10.2(e) for a full length CEA misaligned greater than 18 inches.
Must reduce power less than 70% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, then within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after that, realign CEA or declare CEA inoperable.
Event can be terminated once applicants have commenced the rapid downpower and reactor effects have been noted. Lead examiner will cue the next malfunction.
Op-Test No.: _____ Scenario No.: _2__ Event No.: __7__ Page ___ of ___
Event
Description:
__100% severity RCP Seal Cooler Leak on CVC 16. Lead examiner will cue the event.__________________________________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A1 Window A5U, CC WATER FROM RC-3A SEAL COOLER TEMP HI ATCO Enter ARP-CB-1,2,3/A1 Window A5U.
ATCO If alarm is not due to operation of selector switches, then check TI-48/465, CCW temperature from RC-3A seal cooler greater than 120 degrees (Step 1)
ATCO If CCW temperature is high, then raise flow through RC-3A seal cooler with HCV-442, RC-3A pump seal cir AC outlet. (Step 2)
ATCO Monitor CCW flow from RC-3A seal cooler (Step 2.1)
ATCO Monitor RC-3A parameters on ERF display 440. (Step 2.2)
ATCO ARP-CB-1,2,3/A1 Window A5U CAUTION: RCP operation must be terminated if CCW flow is not re-established within 5 minutes OR high temperature alarms are received on RCP lube oil coolers, RCP seal bleed-off or CEDM seals.
CRS Direct entry into AOP-35 for RCP malfunctions.
CRS Enter Section I if lower seal temperature exceeds 200 degrees. Enter Section II if motor radial or thrust bearing temperatures exceed 203 degrees (actions are the same).
CRS Direct ATCO to manually trip the reactor and enter EOP-00, STANDARD POST TRIP ACTIONS ATCO Trip the reactor (Step 1.1.a)
ATCO Perform SPTAs per EOP-00. (Step 1.1.b)
BOPO ATCO Stop RCP-3A. (AOP-35 Step 1.1.c)
Op-Test No.: _____ Scenario No.: _2__ Event No.: __7,8__ Page ___ of ___
Event
Description:
__100% severity RCP Seal Cooler Leak on CVC 16. Turbine fails to trip on reactor trip. The malfunction is preprogrammed and will occur when the ATCO manually trips the reactor.
Time Position Applicants Actions or Behavior ATCO Verify reactivity control is established by verifying reactor power lowering, startup rate is negative, no more than one regulating or shutdown CEA not inserted, and monitor for an uncontrolled RCS cooldown (EOP-00, Step 1)
BOPO Verify turbine tripped as indicated by stop and intercept valves indicating closed. (EOP-00, Step 2)
BOPO Trip the turbine on CB-10,11. (Step 2.1.a) OR Stop EHC pumps by placing both EHC-3A and EHC-3B in pull-to-lock. Critical task is to (CT) perform these actions before performing any other actions.
BOPO Ensure generator output breaker 3451-4, generator output break 3451-5, and generator field breaker 41E/G1F are tripped (EOP-00, Step 3)
BOPO Verify buses 1A3 and 1A4 are energized (EOP-00, Step 4)
BOPO If SIAS has occurred, then ensure both diesel generators have started (EOP-00, Step 5)
BOPO Check that buses 1A1 and 1A2 are energized (EOP-00, Step 6)
BOPO Check that 125 VDC buses 1 and 2 are energized (EOP-00, Step 7)
BOPO Verify instrument air available: instrument air pressure greater than or equal to 90 psig and at least one air compressor operating (EOP-00, Step 8)
ATCO Determine normal CCW system operation: ensure at least one CCW pump operating, CCW pump discharge pressure greater than or equal to 60 psig, at least one RW pump operating, and if CCW pump discharge pressur greater than or equal to 40 psig, ensure RCP coolers CCW valves HCV-438A/B/C/D are open (EOP-00, Step 9)
ATCO Verify RCS inventory control: PZR level 30-70%, PZR level trending to 45-60%, and RCS subcooling greater than or equal to 20°F (EOP-00, Step 10). Transition to contingency action.
ATCO Restore inventory control, manually control charging and letdown to restore pressurizer level (EOP-00, Step 10.1.a)
ATCO If HPSI stop and throttle criteria (RCS subcooling greater than or equal to 20°F, PZR level greater than or equal to 10% and not lowering, at least one steam generator available for heat removal, and RVLMS indicates level is at or above top of the hot leg), then throttle and stop any or all HPSI pumps (EOP-00, Step 10.1.b)
ATCO Verify RCS Pressure Control: RCS pressure 1800-2300 psia, trending to 2050-2150 psia, and PORVs are closed (EOP-00, Step 11)
Event description continued on next page
Op-Test No.: _____ Scenario No.: _2__ Event No.: __7__ Page ___ of ___
Event
Description:
__100% severity RCP Seal Cooler Leak on CVC 16.____________
Time Position Applicants Actions or Behavior ATCO If RCS pressure less than 1350 psia, trip one RCP in each loop (EOP-00, Step 11.2)
ATCO If RCS pressure less than or equal to 1600 psia, verify engineered safeguards actuated: emergency boration in progress, SI flow acceptable per Attachment 3, VIAS has actuated (86A/VIAS, 86B1/VIAS, 86B/VIAS, 86A1/VIAS are all tripped), and CIAS has actuated (86A/CIAS, 86B1/CIAS, 86B/CIAS, 86A1/CIAS) (EOP-00, Step 11.3)
ATCO If RCS pressure control not established, manually control PZR heaters and spray to restore pressure (EOP-00, Step 11.4)
ATCO Verify core heat removal via forced circulation by all of the following:
(EOP-00, Step 12)
RCP NPSH requirements are satisfied per Att. 2 At least one RCP is operating Core T is less than or equal to 10°F BOPO Verify Main Feedwater is restoring level in at least one steam generator to 35-85% NR by performing the following: (EOP-00, Step 13)
BOPO Ensure both feed reg valves, FCV-1101 and FCV-1102, have ramped closed (EOP-00, Step 13.a)
BOPO Ensure both feed reg bypass valves, HCV-1105 and HCV-1106, have ramped to 40-45% (EOP-00, Step 13.b)
BOPO Place the 43/FW switch in OFF (EOP-00, Step 13.c)
BOPO Ensure no more than one feed pump operating (EOP-00, Step 13.d)
BOPO Ensure no more than one condensate pump is operating (EOP-00, Step 13.e)
BOPO Stop all operating heater drain pumps, FW-5A/B/C (EOP-00, Step 13.f)
BOPO Ensure both sets of steam generator blowdown isolation valves, HCV-1387A/B and HCV-1388A/B, are closed (EOP-00, Step 13.g)
BOPO Verify steam dump and bypass valves are controlling both RCS TC 525-535°F and S/G pressure 850-925 psia (EOP-00, Step 14)
Event description continues on next page
Op-Test No.: _____ Scenario No.: _2__ Event No.: __7__ Page ___ of ___
Event
Description:
__100% severity RCP Seal Cooler Leak on CVC 16.____________
Time Position Applicants Actions or Behavior ATCO Verify normal containment conditions: no unexpected rise in sump level, no containment area alarms, RM-051, 052, and 062 not in alarm, RM-054A/B and RM-057 not in alarm or trending upward, containment pressure less than 3.0 psig and containment temperature less than 120°F(EOP-00, Step 15)
CRS Determine appropriate procedure to implement per Section 6, Diagnostic Actions(EOP-00, Step 16)
CRS Direct entry into EOP-03, LOSS OF COOLANT ACCIDENT CRS Confirm SPTAs performed (EOP-03, Step 1)
CRS Confirm diagnosis of LOCA by: verify safety function status check acceptance criteria satisfied and direct shift chemist to perform rapid activity analysis of both steam generators (EOP-03, Step 2)
CRS Implement the emergency plan (EOP-03, Step 3)
ATCO/BOPO Monitor the floating steps (EOP-03, Step 4)
ATCO If RCS pressure is less than or equal to 1600 psia, verify engineered safeguards actuated: emergency boration in progress, SI flow acceptable per Attachment 3 (EOP-03, Step 6)
ATCO If SIAS has actuated, then maximize SI and charging flow to RCS by operating all of the following pumps: HPSI pumps, SI-2A/B or SI-2B/C, LPSI pumps, SI-1A/B, and charging pumps CH-1A/C (EOP-03, Step 8)
ATCO Verify RCP operating parameters: if TC less than 500°F, ensure at least one RCP stopped; if RCS pressure less than 1350 psia following SIAS actuation, ensure no more than 1 RCP running in each loop (EOP-03, Step 9)
CRS Record time of SIAS initiation (EOP-03, Step 10)
ATCO Verify normal CCW/RW system operation by performing the following:
(EOP-03, Step 11)
ATCO Ensure at least two CCW pumps operating (EOP-03, Step 11.a)
ATCO Verify CCW pump discharge pressure greater than or equal to 60 psig (EOP-03, Step 11.b)
ATCO Ensure at least two raw water pumps operating (EOP-03, Step 11.c)
ATCO Ensure at least three CCW heat exchangers in service (EOP-03, Step 11.d)
Event description continued on next page.
Op-Test No.: _____ Scenario No.: _2__ Event No.: __7,9__ Page ___ of ___
Event
Description:
__100% severity RCP Seal Cooler Leak on CVC 16. HCV-438C fails to close on demand._________________________________________________________________________
Time Position Applicants Actions or Behavior ATCO Ensure all RCP Coolers CCW valves, HCV-438A/B/C/D are open (EOP-03, Step 11.e)
ATCO Verify PORVs and PZR code safety valves are closed by performing the following: (EOP-03, Step 12)
ATCO Check that all PZR quench tank alarms are clear (QUENCH TANK TEMP HI, QUENCH TANK PRESS HI, AND QUENCH TANK LEVEL HI-LO) (EOP-03, Step 12.a)
ATCO Check all relief header temperature alarms are clear (PRESSURIZER PWR OPERATED RELIEF VALVE DISCH TEMP HI, PRESSURIZER SAFETY VALVE RC-141 DISCH TEMP HI, PRESSURIZER SAFETY VALVE RC-142 DISCH TEMP HI) (EOP-03, Step 12.b)
ATCO Check both relief header acoustic flow alarms are clear (RC-142/PCV-102-1 VALVE FLOW and RC-141/PCV-102-2 VALVE FLOW) (EOP-03, Step 12.c)
ATCO If an RCS to CCW leak is evident, then minimize RCS leakage by performing the following: (EOP-03, Step 13)
ATCO Trip all RCPs (EOP-03, Step 13.a)
ATCO Close all RCP coolers CCW valves, HCV-438A/B/C/D (EOP-03, Step 13.b)
CRS Transition to contingency action (EOP-03, Step 13.b.1)
ATCO/BOPO Lower RCS pressure less than 380 psia (EOP-03, Step 13.b.1). Critical task is to lower RCS pressure before attempting to locally manually close (CT) HCV-438c.
Lead examiner can end scenario after the cooldown/depressurization is in progress at his discretion.
Appendix D Scenario Outline Form ES-D-1 Facility: _Fort Calhoun Station__ Scenario No.: ___3____ Op-Test No.: _______
Examiners: ____________________________ Operators: _____________________________
Initial Conditions: _Reactor is currently at approximately 90% power. TM/LP trip unit for channel A is currently in BYPASS while I&C troubleshoots erratic pressurizer pressure readings. Technical Specification 2.15(1) was entered at 0428 today.
Turnover: ___Increase power to 100%_______________________________________________
Event Malf. Event Event No. No. Type* Description R-ATCO 1 N-BOPO Increase power to 100% per OP-4 Attachment 1.
C-ATCO 2 SIT Tank level low on SI-6B. Alarm is from ARP-CB-4/A7 Window C-4L. Actions will require sluicing to SI-6B from another SIT or filling to restore level to >68% per OI-SI-1. T.S. 2.3 might apply.
C-BOPO 3 Instrument Air Compressor CA-1A fails. Standby compressor CA-1B running but not loaded. Alarm is ARP-CB-10,11/A11 Window B-3L. No entry into AOP-17.
TS-CRS 4 B/TI-112C fails high. Alarm is per ARP-CB-4/A20 Window E-6, Nuclear Power and T power deviation, only action for ATCO is to check indications and meters, and if an RCS temperature is abnormal, to notify I&C, therefore, this will not count towards an instrument failure for the ATCO.. T.S. 2.15(1) was already entered due to an inoperable TM/LP channel, so this channel must be placed in trip.
C-BOPO 5 ARP-CB-10,11/A10 Window A-6U, Iso Phase Bus Air Flow Low.
Entry into AOP-27 is directed. Operators will direct local operators to swap motor belt and start the standby motor.
TS-CRS 6 RCS oxygen levels are greater than 0.15 ppm, causing entry into T.S. 2.1.5(1).
C-BOPO 7 TS-CRS Loss of MCC 3C2 due to a ground fault. This causes a loss of boric acid pump CH-4A, boric acid gravity feed line valve HCV-265, and boric acid pumps discharge valve HCV-268. Alarm: CB-4/A7 Boric Acid Valves Trouble. T.S. 2.7 for MCC 3C2 (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). AOP-32
M-ALL 8 CVC16 (CT) ATWS - RPS pressurizer pressure channel D/PIA-102Y fails low, causing 2 out of 3 for TM/LP but no RPS trip. Critical task is for ATCO to manually trip the reactor before performing any other actions.
C-ATCO 9 Following manual trip, 5 control rods fail to insert. This will require emergency boration.
C-ATCO 10 (CT) Emergency boration problem - HCV-258 is mechanically bound when the operators attempt to open it. This results in the inability to emergency borate using the BASTs and requires use of the SIRWT to emergency borate. EOP-20. Critical task is to open LCV-218-3, Charging pump suction SIRWT isol. Valve, close LCV-218-2, VCT Outlet valve, and starting all charging pumps prior to exiting that safety function success path.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description NRC Scenario #3 SCENARIO
SUMMARY
NRC #3 The crew assumes the watch with the reactor at 90% power. TM/LP trip unit for channel A is in BYPASS due to troubleshooting efforts. The crew instructions are to increase reactor power to 100%.
The first event is to increase reactor power per OP-4, LOAD CHANGE AND NORMAL POWER OPERATION. The next event is cued after enough actions have been taken to see an effect on the plant (approximately 1-2% reactor power).
The next event is a low level alarm on SIT Tank SI-6B. Operator actions are per ARP-CB-4/A7 and OI-SI-1 and include restoring level to SIT Tank SI-6B.
The next event is a trip of instrument air compressor CA-1A. The standby is running but unloaded. Operator actions are per ARP-CB-10,11/A7 and include starting the CS air compressor.
The next event is a failure of the B channel of Tcold (B/TI-112C). Operator action is per T.S.
2.15(2) to place the channel in the tripped position within one hour. SRO will refer to Technical Specifications. T.S. 2.15(2) applies.
The next event is a trip of the isolated phase bus duct blower motor. Operator action is per AOP-27 and includes starting the standby blower after the belts have been shifted.
The next event is a high oxygen concentration in the RCS which is called in by chemistry. No operator action. SRO will refer to Technical Specifications. T.S. 2.1.5(1) applies.
The next event is a loss of MCC 3C2 due to a ground fault. Operator action is per ARP-CB-4/A7 and AOP-32, LOSS OF 4160 VOLT OR 480 VOLT BUS POWER and includes operating the primary water booster pump and steam generator blowdown transfer pump as necessary.
SRO will refer to Technical Specifications. T.S. 2.7.2(g) applies.
The D channel for RPS pressurizer pressure fails low, resulting in a 2 out of 3 trip logic for TM/LP, but no reactor trip has occurred. The crew is expected to recognize that an RPS actuation was required, and take action to manually trip the reactor.
When the operator manually trips the reactor, five CEA's fail to insert requiring emergency boration, which is unsuccessful due to HCV-258 failure to open. Following completion of standard post trip actions, SRO directs entry into EOP-20, FUNCTIONAL RECOVERY, Success Path RC-2. The crew will initiate boration using the SIRWT.
Once the crew has initiated boration using the SIRWT, the scenario can be terminated.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __1__ Page ___ of ___
Event
Description:
____Increase power to 100% per OP-4 Attachment 1._______
Time Position Applicants Actions or Behavior CRS CRS reviews prerequisites of OP-4, LOAD CHANGE AND NORMAL POWER OPERATION, Attachment 1, Power Ascension ATCO Maximize pressurizer spray per OI-RC-7, REACTOR COOLANT SYSTEM PRESSURE CONTROL NORMAL OPERATION, Attachment 4, Maximum Pressurizer Spray for Mixing) (OP-4, Att. 1, Step 1)
ATCO Verify PC-103Y pressurizer press controller in automatic (OI-RC-7, Att. 4, Step 1.a)
ATCO Ensure proportional heaters bank P1 group 6 and P2 group 7 are in AUTO (OI-RC-7, Att. 4, Step 1.b)
ATCO Ensure PCV-103-1, PZR spray valve from loop 2A, and PCV-103-2, PZR spray valve from loop 1B, are in AUTO (OI-RC-7, Att. 4, Step 1.c)
ATCO Energize backup heaters by placing each control switch in ON (OI-RC-7, Att. 4, Step 1.d)
ATCO Ensure spray valves open automatically to terminate pressure rise
((OI-RC-7, Att. 4, Step 1.e)
ATCO Adjust PC-103Y setpoint pushbuttons to maintain 2100 psia ((OI-RC-7, Att. 4, Step 1.f)
ATCO/BOPO Raise reactor power while performing the following steps: (OP-4, Att. 1, Step 3)
BOPO Raise turbine generator load to maintain RCS TAVE program per TDB Figure III.1 (OP-4, Att.1, Step 3.a)
ATCO As required, manually reset VOPT channels (OP-4, Att.1, Step 3.c)
ATCO Maintain pressurizer level within 4% of programmed level per OI-RC-8 (OP-4, Att.1, Step 3.d) Level control in automatic. No operator action required.
ATCO Maintain pressurizer pressure 2075-2150 PSIA per OI-RC-7. (OP-4, Att.1, Step 3.e) Pressure control in automatic. No operator action required.
BOPO Maintain steam generator levels at 55-75% NR per OI-FW-3. (OP-4, Att.1, Step 3.f) Level control in automatic. No operator action required.
Event description continues on next page
Op-Test No.: _____ Scenario No.: __3__ Event No.: __1__ Page ___ of ___
Event
Description:
____Increase power to 100% per OP-4 Attachment 1._______
Time Position Applicants Actions or Behavior ATCO Maintain ASI per OI-RR-1, REACTOR REGULATING SYSTEM NORMAL OPERATION, Attachment 4, ASI Control (OP-4, Att. 1, Step 3.f)
Review prerequisites.
Use group 4 CEAs to control ASI. Insert CEAs to make ASI more positive. Withdraw CEAs to move ASI negative. (OI-RR-1, Att. 4, Step 1)
Maintain ASI per TDB Figure III.23.a. (OI-RR-1, Att. 4, Step 2)
ATCO Raise reactor power by dilution using OI-CH-4 Attachment 4 ATCO Record current boron concentration, desired boron concentration, and RCS Tavg. (Step 1) Note: may use reactivity sheets to determine approximate number of gallons of water to be added instead of Steps 1-2 ATCO Determine number of gallons of makeup water to be added using ERF computer per OI-ERFCS-1 or the dilution formula in TDB-V.12. (Step 2)
ATCO Record the number of gallons of makeup water to be added to the RCS.
(Step 3)
ATCO Ensure HC-269, makeup water mode selector switch, is in DILUTE. (Step 4)
ATCO Ensure FCV-269, makeup water control valve, is in CLOSE. (Step 5)
ATCO Set FQS-269X, demin water makeup flow batching switch, to the desired number of gallons of water to be added. (Step 6) Note: will likely choose to added water in smaller batches, as allowed by note in procedure.
ATCO Record initial demineralized water makeup flow totalizer reading. (Step 7)
ATCO Open FCV-269. (Step 8)
ATCO Place FCV-269X in AUTO. (Step 9)
ATCO Set demineralized water flow to desired flow rate with FC-269X controller.
(Step 10)
ATCO Verify VCT level and pressure respond as expected. (Step 11)
ATCO Place FCV-269X in CLOSE when dilution complete. (Step 13)
ATCO Close FCV-269 and record final demineralized water makeup flow totalizer reading. (Steps 14-15)
ATCO Verify amount of demineralized water added from flow totalizer is consistent with amount of water added. (Step 16)
Event is terminated once reactor reactivity effects are seen.
Op-Test No.: _____ Scenario No.: __3__ Event No.: __2__ Page ___ of ___
Event
Description:
____SIT Tank level low on SI-6B. Lead examiner will cue this failure once reactivity effects are seen from event 1.__________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-4/A7 Window C-4L, SAFETY INJECTION TANK SI-6B HI-LO LEVEL.
ATCO Enter ARP-CB-4/A7 Window C-4L.
ATCO Check safety injection tank SI-6B level. (Step 1)
ATCO Ensure HCV-2936 is closed. (Step 2.1)
ATCO Check operation of PCV-2929. (Step 2.2)
ATCO Check the check valve leakage flow indication for excessive leakage cooler flow (FI-2981, AI-30A). (Step 2.3)
ATCO Sluice to SI-6B from another SI Tank or fill SI-6B to restore level to 68 to 72 % per OI-SI-1.
BOPO Sluicing SI Tanks OI-SI-1 Attachment 15 Open drain valves for SI Tanks to be sluiced (Step 1):
- HCV-2916, SI-6A
- HCV-2936, SI-6B
- HCV-2956, SI-6C
- HCV-2976, SI-6D If required to maintain pressure, open HCV-2603A and HCV-2603B, the outboard and inboard SI tank nitrogen supply isolation valves.
(Step 2.a)
Open nitrogen supply stop valve for selected tank (Step 2.b):
- HCV-2629, SI-6A
- HCV-2631, SI-6B
- HCV-2633, SI-6C
- HCV-2635, SI-6D When desired level reached, close SI Tank drain valves, nitrogen supply stop valves and nitrogen supply isolation valves. (Step 3)
Filling SI Tanks using HPSI OI-SI-1, Attachment 4 ATCO Ensure SIRW Tank recirculation valves HCV-385 and HCV-386 are open. (Step 1)
ATCO Ensure HCV-2983, SI check valve leakage header CVCS isolation valve, is closed. (Step 2)
Event description continues on next page.
Op-Test No.: _____ Scenario No.: __3__ Event No.: __2__ Page ___ of ___
Event
Description:
____SIT Tank level low on SI-6B. Lead examiner will cue this failure once reactivity effects are seen from event 1.__________________________________________________
Time Position Applicants Actions or Behavior ATCO If recirculation is desired, start a HPSI pump (SI-2A, SI-2B, or SI-2C). (Step 3.a)
ATCO Recirculate HPSI through the minimum flow lines for 15 minutes.
ATCO If flushing is desired, start a HPSI pump if not already running.
Open HCV-545 SIRWT/Lkg Hdr to RCDT Isolation Valve. (Step 4.a&b)
ATCO Place PCV-2929, leakage controller SI-4B discharge valve, in MANUAL and close PCV-2929. (Step 4.c)
ATCO Crack open, then fully open, either HCV-314 or HCV-315 (Loop 1A HPSI injection valves) and throttle PV-2929 to commence flushing.
(Step 4.d&e)
ATCO When flushing complete, close PCV-2929 and HCV-545. (Step 4.f&g)
ATCO If flushing NOT desired, start HPSI pump if not already running.
(Step 5.a)
ATCO Place PCV-2929 in MANUAL and close (Step 5.b)
ATCO Crack open, then fully open, either HCV-314 or HCV-315 (Loop 1A HPSI injection valves). (Step 5.c)
ATCO Open HCV-2936 SIT SI-6B Fill/Drain Valve. (Step 6)
ATCO Throttle PCV-2929 to begin filling SI tank. (Step 7)
ATCO When SI-6B is filled, close PCV-2929 and close HCV-2936. (Steps 10-11)
ATCO Close HPSI loop injection valve opened in step 4.d or 5.c (either HCV-314 or HCV-315). (Step 12)
ATCO Stop HPSI pump. (Step 13)
ATCO Open HCV-545. (Step 14)
ATCO Lower leakage cooler pressure to less than 350 psig by cracking open PCV-2929. (Step 15)
ATCO When pressure is less than 350 psig, close PCV-2929 and place in AUTO. (Step 16)
ATCO Close HCV-545. (Step 17)
Event is terminated once HCV-545 is closed if OI-SI-1 Attachment 4 is used, or when SI drain valves and nitrogen valves are closed if OI-SI-1 Attachment 15 is used.
Op-Test No.: _____ Scenario No.: __3__ Event No.: __3__ Page ___ of ___
Event
Description:
____Instrument air compressor CA-1A fails. Standby compressor CA-1B is running but unloaded. Event is initiated at lead examiners cue.
Time Position Applicants Actions or Behavior BOPO Respond to alarm CB-10,11/A11 Window B-3L, AIR COMPRESSORS BKR TRIP BOPO Enter ARP-CB-10,11/A7, Window B-3L.
BOPO Dispatch an operator to the air compressors. (Step 1.1)
BOPO Ensure AC-9A or 9B, TPCW pump, is running. (Step 1.2)
BOPO Start the CS air compressor. (Step 1.3)
BOPO Check 1B3C power supply for undervoltage, and dispatch an operator to check the air compressor breaker for overcurrent trip. (Step 2.1)
BOPO If breaker tripped, notify electrical maintenance.
BOPO Check running air compressor for proper operation. (Step 3)
Event is terminated once the CS air compressor is started and verified to be operating.
Op-Test No.: _____ Scenario No.: __3__ Event No.: __4__ Page ___ of ___
Event
Description:
____B/TI-112C fails high (B channel of Tcold). Event is initiated at lead examiners cue.______________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-4/A20 Window E-6, NUCLEAR T POWER CHANNEL DEVIATION ATCO Enter ARP-CB-4/A20 Window E-6.
ATCO Check Nuclear Pwr-T Pwr Deviation Meter indication for channel with deviation. (Step 1)
ATCO Check for a dropped rod. (Step 2)
ATCO Check for existence of hot leg flow streaming. (Step 3)
ATCO Compare each RCS loop hot leg and cold leg temperature and T for deviations between channels (Step 4)
ATCO Determine that channel B Tcold has failed high and notify I&C to check instrument loop.
CRS Enter T.S. 2.15(2) for two inoperable channels for TM/LP (Table 2-2) since 1 channel of TM/LP was inoperable at the beginning of the scenario.
One of the channels must be placed in the trip condition within one hour (since TM/LP has a bypass switch).
CRS Direct placing TM/LP channel B in trip condition (using PTTI)
ATCO Place TM/LP channel B in trip condition Event is terminated once T.S. call is made.
Op-Test No.: _____ Scenario No.: __3__ Event No.: __5__ Page ___ of ___
Event
Description:
____Isolated Phase Bus Duct Blower Motor trips. This event is initiated at the lead examiners cue._________________________________________
Time Position Applicants Actions or Behavior BOPO Respond to alarm CB-10,11/A10 Window A-6U, ISO PHASE BUS AIR FLOW LO CRS Direct entry into AOP-27,Section V BOPO Start isolated phase bus duct blower motor which is belted to the blower.
(Step 1)
BOPO Direct maintenance to shift the belts to the standby blower. (Step 1.1).
BOPO Start the standby blower motor. (Step 1.2).
BOPO Verify alarm clears (Step 2).
Event is terminated once the standby motor has been started.
Op-Test No.: _____ Scenario No.: __3__ Event No.: _6__ Page ___ of ___
Event
Description:
____High oxygen concentration (0.15 ppm) in the RCS. Report is called in by chemistry at the lead examiners cue.__________________________________________________
Time Position Applicants Actions or Behavior CRS Take report from chemistry about 0.15 ppm dissolved oxygen in RCS.
This is in Action Level 2 per CH-AD-0003.
CRS Direct entry into AOP-41,Section II RCS Chemistry CRS Direct shift manager to notify Operations Manager, Reactor Engineer, Supervisor-Reactor Performance Analysis, and Manager-Chemistry (Section II, Step 5.a)
CRS Refer to Technical Specification 2.1.5(1). T.S. 2.1.5(1) states that if the oxygen concentration exceeds 0.1 ppm during power operation, initiate corrective action within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to return oxygen levels to <0.1 ppm. If not restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after that.
If not restored within an additional 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, put in cold shutdown 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after that (2.1.5(5)). (Step 5.b)
CRS Restore chemistry to below action level 2 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Event is terminated once technical specification call is made.
Op-Test No.: _____ Scenario No.: __3__ Event No.: _7__ Page ___ of ___
Event
Description:
____Loss of MCC 3C2 due to a ground fault. This event is initiated at lead examiners cue.__________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-4/A7 Window B5U, BORIC ACID VALVES TROUBLE ATCO Enter ARP-CB-4/A7 Window B5U ATCO Check indicating lights for valves HCV-258, HCV-265, and HCV-268. (Step 1). Determine that valves HCV-265 and HCV-268 lights are off.
ATCO Dispatch equipment operator to check affected valve breakers. (Step 2)
Determine that MCC-3C2 is deenergized.
CRS Direct entry into AOP-32 for loss of 480V bus MCC-3C2.
CRS Enter AOP-32 Section I, Plant Stabilization and Diagnostics BOPO Ensure 43-1/D1 and 43-1/D2 DG mode selector switches are in AUTO.
(Step 2)
CRS Go to Step 9 because plant is not on shutdown cooling. (Step 3)
BOPO Verify at least one vital 4160 V bus is energized. (Step 9)
ATCO Verify at least one CCW pump is running with discharge pressure greater than 60 psig (Step 10)
ATCO Ensure at least one raw water pump running. (Step 11)
BOPO Ensure one bearing water pump is running (Step 12)
BOPO Verify IA operation by ensuring any air compressor is running and instrument air pressure is greater than 90 psig. (Step 13)
ATCO Ensure any or all charging pumps are running (Step 14)
ATCO Maintain RCS pressure per pressure-temperature limits. (Step 15)
ATCO Terminate all radiaoactive releases. (Step 16)
ATCO Verify at least one RCP is operating (Step 18)
BOPO Maintain S/G levels 35-85% NR. (Step 19)
ATCO If condenser vacuum greater than 19 inches, verify RCS temperature being controlled by normal turbine generator operation. (Step 20)
CRS N/A step 21 because lighting is not lost.
CRS Determine that MCC-3C2 has been lost and transition to Section XXVII (Step 22)
Event description continues on next page.
Op-Test No.: _____ Scenario No.: __3__ Event No.: _7__ Page ___ of ___
Event
Description:
____Loss of MCC 3C2 due to a ground fault. This event is initiated at lead examiners cue.__________________________________________________
Time Position Applicants Actions or Behavior ATCO Verify alarm CB-4/A7 BORIC ACID VALVES TROUBLE in alarm, Boric Acid pump CH-4A status lights out, and VA-40A and VA-40C, Aux. Bldg.
exhaust fan status lights out. (Step 1)
CRS Direct chemistry to obtain dew point readings as necessary to maintain radiation monitor operability. (Step 2)
BOPO Operate DW-41B, primary water booster pump as necessary (Step 3)
CRS Ensure all radioactive releases are terminated. (Step 4)
BOPO Operate FW-34B, steam generator blowdown transfer pump B, as necessary. (Step 5)
ATCO/BOPO Refer to Att. B for a complete list of components powered from MCC-3C2.
(Step 6)
CRS Determine the cause of the loss of power to MCC-3C2. (Step 7)
CRS Enter T.S. 2.7.2(g) for loss of MCC-3C2 8-hour shut-down action statement. (Step 8)
Either group of MCCs (3A1, 3A2, 3B1, 3C1, 3C2) or (4A1, 4A2, 4B1, 4C1, 4C2) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, then placed in a 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 />, and cold shutdown 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after that.
Event may be terminated once technical specification call is made.
Op-Test No.: _____ Scenario No.: __3__ Event No.: _8__ Page ___ of ___
Event
Description:
____ATWS. Channel D for RPS pressurizer pressure fails low. This results in a 2 of 3 logic, requiring a reactor trip. RPS fails, and no automatic RPS actuation occurs. This event is initiated at lead examiners cue._________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A4 Window D-5, PRESSURIZER SAFETY INJ SIGNAL LO-LO PRESSURE D/P102Y ATCO/CRS Determine that TM/LP meets the 2 out of 3 logic criteria, requiring a reactor trip which has not occurred.
CRS Direct ATCO to manually trip the reactor and enter EOP-00, SPTAs.
ATCO Manually trip the reactor. Critical task is to manually trip the reactor before performing any other actions.
(CT)
Op-Test No.: _____ Scenario No.: __3__ Event No.: _9, 10__ Page ___ of ___
Event
Description:
____5 control rods fail to insert, requiring emergency boration. When ATCO attempts to emergency borate, HCV-258 mechanically bounds and cannot be opened. These events are preprogrammed into the scenario and will occur automatically once the reactor is manually tripped.__________________________________________________
Time Position Applicants Actions or Behavior ATCO Verify reactor power is lowering, startup rate is negative and no more than one regulating or shutdown CEA not inserted. (Step 1). Transition to contingency action.
ATCO Manually trip reactor at AI-31, place DSS manual trip switches to TRIP, manually open the CEDM clutch power supply breakers at AI-57. (Step 1.1)
ATCO If more than one CEA not fully inserted, emergency borate by ensuring both FCV-269X and FCV-269Y are closed and attempt to open HCV-258, which fails to open. (Step 1.2a&b). Note: may direct a local operator to attempt to open boric acid gravity feed valves HCV-265 and HCV-258. If so, these actions will not be completed successfully prior to procedural direction to borate using the SIRWT.
ATCO Notify CRS of failure of emergency boration.
BOPO Verify turbine is tripped as indicated by stop and intercept valves indicating closed. (Step 2)
BOPO Ensure generator output breakers 3451-4 and 3451-5 and generator field breaker 41E/G1F are tripped. (Step 3)
BOPO Verify buses 1A3 and 1A4 are energized. (Step 4)
BOPO Check buses 1A1 and 1A2 are energized. (Step 6)
BOPO Check that 125 VDC buses 1 and 2 are energized. (Step 7)
BOPO Verify instrument air is available by both the following conditions: IA pressure greater than or equal to 90 psig and at least one air compressor is operating. (Step 8)
ATCO Ensure at least one CCW pump is operating with discharge pressure greater than or equal to 60 psig and at least on raw water pump is operating. (Step 9)
ATCO Verify RCS inventory control: pressurizer level 30-70%, trending to 45-60%, and RCS subcooling is greater than or equal to 20 degrees F. (Step 10)
ATCO Verify RCS pressure control: RCS pressure is 1800-2300 psia, trending to 2050-2150 psia and PORVs are closed. (Step 11)
ATCO Verify core heat removal via forced circulation: RCP NPSH requirements satisfied, at least one RCP is operating, and core T is less than or equal to 10 degrees F. (Step 12)
Event description continues on next page.
Op-Test No.: _____ Scenario No.: __3__ Event No.: _9, 10__ Page ___ of ___
Event
Description:
____5 control rods fail to insert, requiring emergency boration. When ATCO attempts to emergency borate, HCV-258 mechanically bounds and cannot be opened. These events are preprogrammed into the scenario and will occur automatically once the reactor is manually tripped._
Time Position Applicants Actions or Behavior BOPO Verify main feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR) by performing the following (Step 13):
- Ensure FCV-1101 and FCV-1102 feed reg valves have ramped closed.
- Ensure both feed reg bypass valves have ramped to 40-45%
- Place 43/FW switch in OFF
- Ensure no more than one feed pump operating
- Ensure no more than one condensate pump operating
- Stop all operating heater drain pumps
- Ensure both sets of S/G blowdown isolation valves are closed (HCV-1387A/B and HCV-1388A/B)
BOPO Verify steam dump and bypass valves are controlling RCS Tcold 525-535 degrees F and S/G pressure 850-925 psia. (Step 14)
ATCO Verify normal containment conditions: no unexpected rise in the containment sump level, no containment area radiation alarms, no alarms on RM-051, RM-052, and RM-062, and no S/G blowdown or condenser off-gas radiation monitors are in alarm or trending upward. (RM-054A, RM-054B, and RM-057). (Step 15a-e)
ATCO Verify containment pressure less than 3.0 psig and temperature less than 120 degrees F. (Step 15.f)
CRS Determine appropriate procedure per Section 6.0, Diagnostic Actions.
(Step 16). CRS should determine that EOP-20, Functional Recovery, must be entered due to ATWS.
CRS Determine need to and enter RC-2 success path.
BOPO Maintain RCS temperature constant by controlled steaming using steam dump and bypass valves. (RC-2, Step 1)
ATCO Verify BAST is available for boration. (Step 2) Transition to contingency action.
CRS If both BASTs are unavailable, go to Step 4. (Step 2.1)
ATCO Commence boration using the SIRWT (Step 4)
ATCO Open LCV-218-3, charging pump suction SIRWT isolation valve (Step 4.a)
Stop both boric acid pumps (Step 4.b)
Ensure HCV-268, HCV-265, HCV-258, and LCV-218-2 (VCT outlet valve) are closed (Step 4.c)
Event description continues on next page.
Op-Test No.: _____ Scenario No.: __3__ Event No.: _9, 10__ Page ___ of ___
Event
Description:
____5 control rods fail to insert, requiring emergency boration. When ATCO attempts to emergency borate, HCV-258 mechanically bounds and cannot be opened. These events are preprogrammed into the scenario and will occur automatically once the reactor is manually tripped._
Time Position Applicants Actions or Behavior ATCO Ensure charging isolation valves HCV-247, HCV-238, HCV-248, and HCV-239 are open. (Step 4.d)
ATCO Start all charging pumps (Step 4.e)
ATCO Insert CEAs into the core using MANUAL SEQUENTIAL or MANUAL GROUP Scenario can be terminated once emergency boration has been successful.
Appendix D Scenario Outline Form ES-D-1 Facility: _Fort Calhoun Station__ Scenario No.: ____4___ Op-Test No.: _______
Examiners: ____________________________ Operators: _____________________________
Initial Conditions: __Mode 2 <1% power. Next step in OP-2A is to start 1 MFW pump. Desired MFW pump is FW-4B.___________
Turnover: _____Continue in OP-2A to raise power and load turbine__________________________
Event Malf. Event Event No. No. Type* Description N-BOPO 1 Start MFW pump FW-4B per OP-2A, Attachment 3. Attachment 2 contains local operator actions and the instructions for starting the lube oil pump.
R-ATCO 2 Raise reactor power to 10% per OP-2A.
C-ATCO Wide range log NI-002 fails high. This failure should occur when 3 TS-CRS the ATC has raised power sufficient to see reactor response and when directed by lead examiner. ARP-CB-4/A20, Windows B-7 and C-1. This will send the operators to AOP-15, where they are directed to secure from raising power and stabilize reactor. T.S.
2.15 for failure of NI 4 C-BOPO MFW pump FW-4B trips, no auto start of standby pump. Alarm is ARP-CB-10,11/A12.
5 C-ATCO Controlling pressurizer level instrument 101X fails low. Alarm is ARP-CB-1,k2,3/A4 Windows A-8 and C-8 C-ATCO 6 TS-CRS CCW pump AC-3A trips, no autostart of standby pump. Alarm is ARP-CB-1,2,3/A2 Window D-3U. T.S. 2.4(b) applies.
7 C-BOPO Inadvertent AFAS. AOP-28 for inadvertent AFAS. T.S.2.5, 2.15, TS-CRS and 2.0.1 apply (Motherhood statement - 6 hr shutdown T.S.A.S.)
8 M-ALL Steam line break inside containment on RC-2A. EOP-00 to EOP-05.
(CT) 9 C-BOPO SGIS on RC-2A fails. Critical task will be for BOPO to isolate steam generator before exiting procedure step.
10 C-ATCO Containment spray pump 3B fails to autostart but can be started from control panel. Containment spray pump 3A shaft shears.
(CT) Critical task is to restore containment spray flow by either starting containment spray pump 3C or 3B.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description NRC Scenario #4 SCENARIO
SUMMARY
NRC #4 The crew assumes the watch with the reactor is Mode 2 at less than 1% reactor power. The crew instructions are to start main feedwater pump FW-4B and continue with power ascension.
The first event is to start a main feedwater pump per OP-2A, PLANT STARTUP, Attachment 3.
The next event is to raise reactor power to 10% per OP-2A. Once a reactivity effect is seen on the reactor, the next event will be cued.
The next event is a failure of wide range logarithmic NI-002 high. Operator action is per CB-4/A20 and AOP-15, and includes securing from the power ascension and stabilizing the reactor.
SRO will refer to Technical Specifications. T.S. 2.15(1) applies.
The next event is a trip of main feedwater pump FW-4B with no autostart of the standby pump.
Operator actions are per ARP-CB-10,11/A12 and include starting the standby pump, setting the post SIAS feedwater pump to FW-4C, and selecting a new standby pump.
The next event is a failure of controlling pressurizer level instrument 101X low. Operator actions are per ARP-CB-1,2,3/A4 and include placing the pressurizer level control switch to channel Y and placing the pressurizer heater cutout channel select switch to channel Y.
The next even is a trip of CCW pump AC-3A with no autostart of the standby pump. Operator actions are per ARP-CB-1,2,3/A2 and include starting the standby CCW pump. SRO will review Technical Specifications. T.S. 2.4(b) applies.
The next event is an inadvertent aux feedwater actuation signal. Operator actions are per AOP-28, AUXILIARY FEEDWATER SYSTEM MALFUNCTIONS and include actions to stop the aux feed and bypass the affected AFAS signal. SRO will refer to Technical Specifications. T.S.'s 2.5(1)D and 2.15(3) apply.
After this event a steam line break occurs inside containment on RC-2A. The crew will enter EOP-00 and perform standard post trip actions. Automatic SGIS fails and the crew should recognize this and take action to manually isolate the steam generators.
Once the containment spray is actuated, containment spray pump 3A shaft shears and pump 3B fails to automatically start. The crew should recognize that they do not have any containment spray and take actions to start containment spray pump 3B, or containment spray pump 3C, and must close one of the containment spray head valves.
Once the crew has successfully isolated the steam generator and restored containment spray, the scenario may be terminated.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _4___ Event No.: __1__ Page ___ of ___
Event
Description:
__Start MFW pump FW-4B per OP-2A Att. 4 Step 5.a.__
Time Position Applicants Actions or Behavior BOPO Start MFW pump using OI-FW-2.
BOPO Direct local operator to perform actions per OI-FW-2, Attachment 2.
(Attachment 3, Step 1). Note: Cue BOPO that Attachment 2, Step 2.h requires start of auxiliary lube oil pump FW-30B. Also cue that local actions are complete.
BOPO Start auxiliary lube oil pump FW-30B (Attachment 2, Step 2.h)
BOPO Ensure lockout relay is reset and amber indicating light is on for 86/FW-4B. (Attachment 3, Step 2)
BOPO Ensure 43/FW switch is in off and the 43/FW TRANSFER SWITCH OFF-AUTO alarm is in alarm (Step 3)
BOPO Ensure 43-SIAS/FW4 is in the FW-4B position. (Step 4)
BOPO Start FW pump FW-4B by placing control switch in AFTER-START. (Step 6)
BOPO Verify ammeter returns to less than 460 amps in less than 15 seconds and stabilizes for FW-4B. (Step 7.a)
BOPO Verify discharge isolation valve HCV-1150B opens and operates properly.
(Step 7.b)
BOPO Verify auxiliary lube oil pump FW-30B stops. (Step 7.c)
BOPO Direct local operator to ensure HCV-1150B stem indicator goes to open position. (Step 8)
BOPO At discretion of shift manager, place 43/FW switch in AUTO and verify alarm clears. (Step 9). Note: cue this if asked.
Event is terminated once the main feedwater pump is started.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __2__ Page ___ of ___
Event
Description:
__Raise reactor power to 10% per OP-2A, Attachment 4, Step 5.__
Time Position Applicants Actions or Behavior BOPO Direct local operator to secure FW-54 by performing OI-FW-2, Attachment 5, Step 13.a-f.
BOPO Place 43/FW-56 in EMERGENCY STANDBY. (Step 14)
BOPO Ensure FW-1017 is open. (Step 15)
ATCO Raise reactor power by dilution using OI-CH-4 Attachment 4 ATCO Record current boron concentration, desired boron concentration, and RCS Tavg. (Step 1) Note: may use reactivity sheets to determine approximate number of gallons of water to be added instead of Steps 1-2 ATCO Determine number of gallons of makeup water to be added using ERF computer per OI-ERFCS-1 or the dilution formula in TDB-V.12. (Step 2)
ATCO Record the number of gallons of makeup water to be added to the RCS.
(Step 3)
ATCO Ensure HC-269, makeup water mode selector switch, is in DILUTE. (Step 4)
ATCO Ensure FCV-269, makeup water control valve, is in CLOSE. (Step 5)
ATCO Set FQS-269X, demin water makeup flow batching switch, to the desired number of gallons of water to be added. (Step 6) Note: will likely choose to added water in smaller batches, as allowed by note in procedure.
ATCO Record initial demineralized water makeup flow totalizer reading. (Step 7)
ATCO Open FCV-269. (Step 8)
ATCO Place FCV-269X in AUTO. (Step 9)
ATCO Set demineralized water flow to desired flow rate with FC-269X controller.
(Step 10)
ATCO Verify VCT level and pressure respond as expected. (Step 11)
ATCO Place FCV-269X in CLOSE when dilution complete. (Step 13)
ATCO Close FCV-269 and record final demineralized water makeup flow totalizer reading. (Steps 14-15)
ATCO Verify amount of demineralized water added from flow totalizer is consistent with amount of water added. (Step 16)
BOPO Maintain RCS temperature 527-532 degrees F using steam dump and bypass valves. (OP-2A, Attachment 4, Step 5.c)
Event can be terminated once reactivity effects are seen.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __3__ Page ___ of ___
Event
Description:
__Wide range log power NI-002 fails high. This event shall be initiated at lead examiners cue.________________________________________________________________
Time Position Applicants Actions or Behavior ATCO Respond to alarms CB-4/A20 Window B-7, NUCLEAR INSTRUMENTATION CHANNEL INOPERATIVE, Window C-1, HIGH POWER RATE OF CHANGE CHANNEL TRIP, and Window E-6, NUCLEAR T POWER CHANNEL DEVIATION.
ATCO Enter ARP-CB-4/A20, Window B-7 ATCO Verify nuclear instrumentation testing in progress. (Step 1)
ATCO Check that the non-op light is on for one of the WRNI drawers. (Step 2).
Determine that NI-002 has failed high.
ATCO Check the following on the WRNI drawer (Step 3):
- Level test and rate test switches in OPR for WR NI drawers
- NI drawer power-on lights are on for WR NI drawers
-4 ATCO If a wide range channel is failed AND power is greater than 10 but less than 15%, go to AOP-15. (Step 6)
CRS Transition to AOP-15,Section II.
ATCO Stabilize the reactor. (Step 1). Note: ATCO will drive rods in slightly to counteract the positive reactivity from the dilution.
ATCO Verify at least two wide range channels are operable. (Step 2)
CRS Notify operations manager or work week manager of WR NI failure. (Step 3)
ATCO Place RPS TU-2 in either bypass or trip within one hour. (Step 4)
CRS Direct I&C to restore WR NI to service. (Step 5)
CRS Enter T.S. 2.15(1). Place inoperable channel in either bypass or tripped condition within one hour. Channel may be bypassed up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The specification applies to the wide range NI channel when reactor power is
-4 between 10 and 15% power Event is terminated once T.S. call is made.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __4__ Page ___ of ___
Event
Description:
__MFW pump FW-4B trips, no autostart of backup pump. This event shall be initiated at lead examiners cue.______________________________________________________
Time Position Applicants Actions or Behavior BOPO Respond to alarm CB-10,11/A12 Window A-6L, STEAM GEN FEED PUMP B OVERLOAD/TRIP BOPO Enter ARP-CB-10,11/A12 Window A-6L BOPO Dispatch an operator to check status of FW-4B. (Step 1)
BOPO Start standby feedwater pump. (Step 2). Note: The ARP does not contain instructions about starting the auxiliary lube oil pump prior to starting MFW pump.
BOPO Ensure 43-SIAS/FW4 Post SIAS Running Feedwater Pump is selected to FW-4C. (Step 2.2)
BOPO Check the following for the cause of the FW-4B trip (Step 2.4):
- 49/FW-4B overcurrent relay tripped at 1A2
- Motor stopped from local stop pushbutton
- Motor stopped from the 69 permissive switch
- Low voltage on 4160V Bus 1A2
- Low oil pressure on feedwater pump
- 86/FW-4B Feedwater Pump Motor Differential Overcurrent BOPO Notify electrical maintenance of feedwater pump trip. (Step 2.5)
BOPO Place running pump in AFTER-START. (Step 2.6)
BOPO If desired, align another pump to standby by placing control switch for FW-4B in AFTER-STOP and the control switch for the pump in PULL-OUT to AFTER-STOP. (Step 3)
Event is terminated once feedwater pump is operating.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __5__ Page ___ of ___
Event
Description:
__Controlling pressurizer level instrument 101X fails low. Event is intiated at lead examiners cue.________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm ARP-CB-1,2,3/A4 Window A-8, PRESSURIZER LEVEL HI-LO CHANNEL X and Window C-8, PRESSURIZER LEVEL LO-LO CHANNEL X.
ATCO Enter ARP-CB-1,2,3/A4 Window C-8.
ATCO Check pressurizer level. (Step 1)
ATCO Check RCS pressure. (Step 2)
ATCO Ensure all pressurizer heaters are deenergized. (Step 3)
ATCO Check RCS cold leg temperature for decrease (Step 4)
ATCO Check VCT level for indication of decreasing level (Step 4.1)
ATCO If VCT level is decreasing, perform RCS leak rate test. (Step 4.2)
ATCO Check letdown flow at a minimum and all available charging pumps are running and supplying flow to the RCS. (Step 5)
ATCO Place pressurizer level control to channel Y (Step 6.1)
ATCO Place PZR heater cutout channel select switch to Y (Step 6.2)
ATCO Notify I&C. (Step 7)
Event is terminated once level is controlled within band either manually or using channel Y.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __6__ Page ___ of ___
Event
Description:
__CCW pump AC-3A trips, no autostart of standby pump. Event is initiated at lead examiners cue.________________
Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A2 Window D-3U, CCW PUMPS TRIP ATCO Enter ARP-CB-1,2,3/A2 Window D-3U.
ATCO Verify standby CCW pumps have started. (Step 1)
ATCO If standby pump has not started, start a standby CCW pump. (Step 2)
ATCO Monitor CCW component temperatures and flows. (Step 3)
ATCO Direct local operator to check CCW pump breaker. (Step 5)
ATCO Notify maintenance of CCW pump trip. (Step 6)
CRS Enter T.S. 2.4(b). Restore CCW pump to operability within 7 days or place in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after that. If not restored within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, enter cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Event is terminated once CCW flow is restored and T.S. call has been made.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __7__ Page ___ of ___
Event
Description:
__Inadvertent AFAS (Aux. FW actuation signal). Event is initiated at lead examiners cue.
Time Position Applicants Actions or Behavior BOPO Respond to alarms AI-66A/A66A Window 44, AFWS STEAM GEN RC-2A CHANNEL A ACTUATED and Window 45, AFWS STEAM GEN RC-2B CHANNEL A ACTUATED BOPO Determine that AFAS actuated NOT required.
CRS Direct entry into AOP-28,Section II, Inadvertent AFW actuation BOPO Verify AFAS is inadvertent. (Section II, Step 1)
CRS Refer to both T.S.s 2.5 and 2.15. (Step 2)
BOPO Ensure both FCV-1368, FW-6 recirculation valve, and FCV-1369, FW-10 recirculation valve, are in AUTO. (Step 3)
BOPO Place control switches for AFW isolation valves HCV-1107A, HCV-1107B, HCV-1108A, and HCV-1108B in CLOSE. (Step 4)
BOPO Bypass affected channel or logic subsystem per OI-AFW-2 CRS Log entry into T.S. 2.15(3) (OI-AFW-2, Attachment 1, Step 2.a)
BOPO Bypass channel using Table 2 and record as-left information. (Step 2.b)
BOPO Stop all AFW pumps by: (AOP-28,Section II, Step 6)
BOPO Close YCV-1045, FW-10 steam inlet valve (Step 6.a)
BOPO Place isolation valve YCV-1045A override switch and isolation valve YCV-1045B override switch in OVERRIDE. (Step 6.b)
BOPO Close YCV-1045A and YCV-1045B, FW-10 steam supply valves. (Step 6.c)
BOPO Ensure FW-10 recirc flow drops to zero. (Step 6.d)
BOPO Stop FW-6, electric AFW pump, by placing HC-1367, FW-6 control switch, in PULL-TO-LOCK. (Step 6.e)
BOPO Ensure FW-6 recirc flow drops to zero.
BOPO Once affected channel is bypassed return AFW system to automatic: (Step 7)
BOPO Place control switches for HCV-1107A, HCV-1107B, HCV-1108A, and HCV-1108B in RESET. (Step 7.a)
Place control switches for HCV-1107A, HCV-1107B, HCV-1108A, and HCV-1108B in AUTO. (Step 7.b)
Event description is continued on the next page.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __7__ Page ___ of ___
Event
Description:
__Inadvertent AFAS (Aux. FW actuation signal). Event is initiated at lead examiners cue.
Time Position Applicants Actions or Behavior BOPO Place YCV-1045 control switch in RESET. (Step 7.c)
BOPO Place YCV-1045 control switch in AUTO. (Step 7.d)
BOPO Place isolation valve YCV-1045A override switch and isolation valve YCV-1045B override switch in NORMAL. (Step 7.e)
BOPO Place HC-1267, FW-6 control switch, in AFTER-STOP. (Step 7.f)
BOPO Ensure FW-64, AFW pump FW-10 back pressure trip latch and FW-64-RL, AFW pump FW-10 back-pressure trip latch reset lever, are reset. (Step 8)
CRS Enter T.S.s:
2.5(1)D for two trains of AFW inoperable due to overriding and stopping AFW. This is then exited once AFW is restored to automatic. Actions are to initiate immediate actions to restore AFW and suspend T.S.s requiring a mode change 2.15(3) for logic subsystem. 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> shutdown LCO.
Event is terminated once AFW has been restored to automatic
Op-Test No.: _____ Scenario No.: _4___ Event No.: __8__ Page ___ of ___
Event
Description:
__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue.
Time Position Applicants Actions or Behavior CRS Direct entry into EOP-00 and performance of SPTAs.
ATCO Verify reactor power lowering, startup rate negative, and no more than one regulating/shutdown CEA not inserted. (Step 1.a)
ATCO Monitor for an uncontrolled RCS cooldown. (Step 1.b). Transition to contingency action.
ATCO Emergency borate. (Step 1.2) Note: emergency boration should automatically initiate due to SIAS ATCO Ensure both FCV-269X and FCV-269Y are closed. (Step 1.2.a)
ATCO Open HCV-268, HCV-265, and HCV-258. (Step 1.2.b)
ATCO Start all boric acid and charging pumps. (Step 1.2.c)
ATCO Close LCV-218-2, VCT outlet valve. (Step 1.2.d)
ATCO Ensure LCV-218-3, HCV-257, and HCV-264 are closed. (Step 1.2.e)
ATCO Borate until adequate shutdown established. (Step 1.2.f)
BOPO Verify turbine tripped by stop and intercept valves indicating closed. (Step 2)
BOPO Ensure generator output breakers 3451-4 and 3451-5 and generator filed breaker 41E/G1F are tripped. (Step 3)
BOPO Verify buses 1A3 and 1A4 are energized. (Step 4)
BOPO If SIAS has occurred, ensure both diesel generators have started. (Step 5)
BOPO Check buses 1A1 and 1A2 are energized. (Step 6)
BOPO Check 125 VDC buses 1 and 2 are energized. (Step 7)
BOPO Verify instrument air available with IA pressure greater than or equal to 90 psig and at least one air compressor operating. (Step 8)
ATCO Ensure at least one CCW pump operating with discharge pressure greater than or equal to 60 psig and at least one raw water pump operating. (Step 9.a-c)
ATCO Ensure RCP coolers CCW valves are open. (Step 9.d)
ATCO Verify pressurizer level is 30-70%, trending to 45-60% with an RCS subcooling greater than or equal to 20 degrees. Transition to contingency.
(Step 10)
Event description is continued on next page.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9__ Page ___ of ___
Event
Description:
__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.
Time Position Applicants Actions or Behavior ATCO Manually control charging and letdown to restore pressurizer level. (Step 10.1.a)
ATCO Verify RCS pressure 1800-2300 psia, trending to 2050-2150 psia, and PORVs are closed. (Step 11). Transition to contingency actions.
ATCO If RCS pressure less than or equal to 1350 psia, trip one RCP in each loop. (step 11.2)
ATCO If RCS pressure less than or equal to 1600 psia, ensure emergency boration in progress and SI flow acceptable per Attachment 3. (Step 11.3.a-b)
ATCO If RCS pressure less than or equal to 1600 psia, ensure VIAS has initiated (86A/VIAS, 86B1/VIAS, 86B/VIAS, 86A1/VIAS) and CIAS has initiated (86A/CIAS, 86B1/CIAS, 86B/CIAS, 86A1/CIAS)
ATCO Manually control pressurizer heaters and spray to restore RCS pressure.
(Step 11.4)
ATCO Verify RCP NPSH requirements are satisfied, at least one RCP is operating, and core T less than or equal to 10 degrees F. (Step 12)
BOPO Verify MFW is restore level in at least one S/G to 35-85%. (Step 13)
BOPO Ensure both feed reg valves have ramped closed. (Step 13.a)
BOPO Ensure both feed reg bypass valves have rampted to 40-45%. (Step 13.b)
BOPO Place 43/FW switch in OFF and ensure no more than one feed pump running. (Step 13.c&d)
BOPO Ensure no more than one condensate pump running and stop all heater drain pumps. (Step 13.e&f)
BOPO Ensure both sets of S/G blowdown isolation valves are closed. (Step 13.g)
BOPO Verify steam dump and bypass valves are controlling both RCS Tcold 525-535 degrees F and S/G pressure 850-925 psia. (Step 14). Transition to contingency action.
BOPO Stop cooldown by closing steam dump and bypass valves, atmospheric dump valve, and directing a local operator to check both air assisted main steam safety valves closed. (Step 14.2.a-c)
BOPO If S/G pressure less than 700 psia, isolate main steam header by closing both MSIVs and both MSIV bypass valves. (Step 14.2.d)
Event description is continued on next page.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9__ Page ___ of ___
Event
Description:
__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.
Time Position Applicants Actions or Behavior BOPO If S/G pressure less than or equal to 500 psia, ensure SGIS closes all of the following valves: HCV-1041A, HCV-1041C, HCV-1042A, HCV-1042C, (CT) HCV-1105, HCV-1106, HCV-1386, HCV-1385, HCV-1103, HCV-1104.
(Step 14.2.e). Note: Critical task will be for the BOPO to take actions to isolate the steam generators due to a failure of SGIS prior to exiting this procedure step.
BOPO Steam S/G RC-2B prior to an uncontrolled Tcold rise of 5 degrees F or 27%WR level on RC-2A by operating air assisted main steam safety valve MS-292. (Step 14.2.f)
ATCO If Tcold is less than 500 degrees F, ensure at least one RCP is stopped.
(Step 14.3)
ATCO Verify normal containment conditions. (Step 15)
ATCO No unexpected rise in containment sump level. (Step 15.a)
ATCO Check no containment area radiation monitor alarms. (Step 15.b)
ATCO Verify RM-051, RM-052, and RM-062 not in alarm. (Step 15.c)
ATCO Verify RM-054A, RM-054B, and RM-057 are not in alarm or trending upward. (Step 15.d&e)
ATCO Verify containment pressure less than 3.0 psig and temperature less than 120 degrees F. (Step 15.f). Transition to contingency action.
ATCO Start VA-3A, VA-7C, VA-3B, VA-7D. (Step 15.f.1.1)
ATCO Ensure CCW supplied to coils of operating containment vent fans.
(Step 15.f.1.2)
ATCO If containment pressure greater than or equal to 5 psig, verify engineered safeguards are actuated. (Step 15.f.2)
ATCO Ensure emergency boration in progress. (Step 15.f.2.1)
ATCO Ensure SI flow acceptable. (Step 15.f.2.2)
ATCO Ensure VIAS has initiated. (Step 15.f.2.3)
ATCO Ensure CIAS has initiated. (Step 15.f.2.4)
BOPO Ensure SGIS has closed HCV-1041A, HCV-1041C, HCV-1042A, HCV-1042C, HCV-1105, HCV-1106, HCV-1386, HCV-1385, HCV-1103, and HCV-1104. (Step 15.f.2.5)
Event description is continued on next page.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9, 10__ Page ___ of ___
Event
Description:
__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.
When CSAS occurs, containment spray pump 3A shaft shears and pump 3B fails to automatically start, but can be started from the control room.
Time Position Applicants Actions or Behavior ATCO If containment pressure is greater than or equal to 5 psig, RCS pressure is less than or equal to 1600 psia, and at least one S/G pressure is less than (CT) or equal to 500 psia, ensure containment spray is greater than or equal to 2300 gpm with only one spray pump per header. (Step 15.f.3). Critical task is to start either containment spray pump 3B or 3C and obtain 2300 gpm flow prior to exiting this procedure step.
CRS Use Section 6.0 to determine appropriate procedure to implement. (Step 16)
CRS Determine need to transition to EOP-05, Uncontrolled Heat Extraction Event CRS Confirm SPTAs have been performed. (EOP-05, Step 1)
CRS Confirm diagnosis of UHE by verifying safety function status check acceptance criteria are being maintained. (Step 2)
CRS Implement the Emergency Plan. (Step 3)
ATCO/BOPO Monitor the floating steps. (Step 4)
ATCO If RCS pressure less than 1600 psia, containment pressure greater than 5 psig, and at least one steam generator pressure less than or equal to 500 psia, verify containment spray flow is greater than or equal to 2300 gpm with only one spray pump per header. (Step 5.a). If not performed in EOP-00, transition to contingency action.
ATCO Restore containment spray by starting the idle containment spray pumps.
(Step 5.a.1.2)
ATCO If only one CS pump is operating, ensure either HCV-344 or HCV-345 is closed. (Step 5.b). If ATCO started 3B, HCV-345 must be closed. If ATCO started 3C, either HCV-344 or HCV-345 must be closed.
ATCO Initiate containment cooling by starting all available containment vent fans and ensuring CCW is supplied to the coils of the operating vent fans. (Step 5.c)
ATCO If RCS pressure less than or equal to 1600 psia, verify emergency boration and SI flow. (Step 6)
ATCO If containment pressure greater than or equal to 5 psig, verify CPHS, CIAS, VIAS have initiated, emergency boration in progress, and SI flow is acceptable. (Step 7.a-e)
BOPO Ensure SGIS has closed valves (see above sections for list of valves).
(Step 7.f)
Event description is continued on next page.
Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9, 10__ Page ___ of ___
Event
Description:
__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.
When CSAS occurs, containment spray pump 3A shaft shears and pump 3B fails to automatically start, but can be started from the control room.
Time Position Applicants Actions or Behavior ATCO Optimize SI and charging flow to RCS by operating either HPSI pumps SI-2A/B or SI-2B/C, LPSI pumps SI-1A/B, and charging pumps CH-1A/B/C.
(Step 8).
ATCO If Tcold is less than 500 degrees F, ensure at least one RCP is stopped.
(Step 9.a)
ATCO If RCS pressure is less than or equal to 1350 psia, ensure no more than 1 RCP running in each loop. (Step 9.b)
ATCO Verify normal CCW/RW system operation with at least two CCW pumps running with discharge pressure greater than or equal to 60 psig, at least 2 raw water pumps running, 3 CCW heat exchangers in service, and all RCP cooler CCW valves are open. (Step 10)
CRS N/A step 11 since affected steam generator should be identified by this time.
CRS Transition to Step 12.1 since UHE is not isolated.
ATCO Emergency borate. (Step 12.1)
BOPO Ensure SGIS has closed required valves (see earlier portion for list). (Step 13)
BOPO Identify most affect S/G by downward trends in steam pressure, level, or RCS Tcold CRS Transition to Step 16.
BOPO Isolate RC-2A (Step 16)
BOPO Close the following valves: HCV-1041A, HCV-1041C, MS-291, FCV-1101, HCV-1105, HCV-1386, HCV-1103, HCV-1388A, HCV-1388B, HCV-1107A, HCV-1107B, MS-298. (Step 16.a)
BOPO Override and close YCV-1045A. (Step 16.b)
BOPO If sampling not in progress, close both HCV-2506A and HCV-2506B BOPO Verify most affected steam generator is isolated. (Step 17)
BOPO Direct local operator to open breaker MCC-4C1-F03, HCV-1042C main steam bypass valve and locally open HCV-1042C. (Step 18.1.b.1-2)
BOPO Steam S/G RC-2B using steam dump and bypass valves. (Step 19)
Event can be terminated once RC-2A is isolated and decay heat is being removed by RC-2B.