ML14234A357
| ML14234A357 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/04/2014 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Nebraska Public Power District (NPPD) |
| References | |
| 50-298/14-007 50-298/OL-14 | |
| Download: ML14234A357 (235) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: ____________Cooper Nuclear Station____________ Date of Examination: _____2014____
Examination Level: RO X SRO Operating Test Number: ____1_____
Administrative Topic (see Note) Type Describe activity to be performed Code*
Conduct of Operations Conduct of Operations R,M Interpret GARDEL Official Case SKL034-50-01 K/A 2.1.25 (3.9/4.2)
Equipment Control R,M Determine Tagging Order Release Requirements SKL034-50-41 K/A 2.2.13 (4.1/4.3)
Radiation Control R,D Radiation Protection Table Top SKL034-30-63 K/A 2.3.13 (3.4/3.8)
Emergency Procedures/Plan R,D Suppression Pool Temp Calculation SKL034-21-131 K/A: A295013 AA201 (3.8/4.0) 2.1.12 (2.9/4.0)
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)
Rev 1 (6/3/14)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: ____________Cooper Nuclear Station____________ Date of Examination: _____2014____
Examination Level: RO SRO X Operating Test Number: __________
Administrative Topic (see Note) Type Describe activity to be performed Code*
R,N Determine required Actions for Plant Chemistry Out of Conduct of Operations Specification SKL034-50-80 K/A 2.1.34 (SRO 3.5)
R,D Determine Shift Staffing Requirements for Mode Change Conduct of Operations K/A 2.1.4 (SRO 3.4)
SKL034-20-114 R,D Determine Post-Maintenance Testing Requirements Equipment Control K/A 2.2.7 (2.0/3.2)
SKL034-50-18 S,D Protective Action Recommendation (PAR) Table Top X Radiation Control K/A 2.4.44 (2.1 / 4.0)
SKL034-30-61 R,M Medical Emergency (#1)
Emergency Procedures/Plan K/A 2.4.38 (2.2/4.0), 2.4.43 (2.8/3.5)
SKL034-21-131 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)
Rev 1 (6/3/14)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ____Cooper Nuclear Station_______________ Date of Examination: _____2014____
Exam Level: RO X SRO-I SRO-U Operating Test No.: _____ 1 _____
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
- a. Placing SDG In Service From Control Room S, L, D, P 6 K/A 262001.K4.06 (3.6 / 3.9) and 264000.A4.04 (3.7/3.7)
- b. Shifting from Single Element to Auto (3 element) A, S, M 2 K/A 259002 A4.06 (3.1/3.2)
- c. Recover from Manual Scoop Tube Operations S, D 1 K/A A.2.05 (RO 3.1 / SRO 3.1) A 2.09 (RO3.1 / SRO 3.0)
- d. Transfer RPSPP1B from RPS MG Set B to CDP-1A S, N 7 K/A 212000 A1.11 (3.4 / 3.3) and 212000.A2.02 (3.7/3.9)
- e. RPV Depressurization with RWCU A, S, E, L, N 3 K/A 204000 A4.03 (3.2 / 3.6), 204000.A1.04 (2.8/2.8)
- g. Startup the Suppression Pool Cooling Mode of RHR (Alternate Path) A, S, D 5 K/A 219000 A4.02 (3.7 / 3.5)
- h. Separation of REC Critical Loops S, E, M 8 K/A 295018 A1A.03 (3.3 / 3.4) and AK3.07 (3.1/3.2)
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Operate the Diesel Fire Pump Manually A, E, D 8 K/A 286000; A4.06(3.4/3.4)
- j. Place 24 VDC Batteries and Associated Chargers in service D 6 K/A: 263000 K4.01(3.1/3.4) and 2.2.2 (4.6/4.1)
@ 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 Rev 1 (6/3/14)
(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 Rev 1 (6/3/14)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ____Cooper Nuclear Station_______________ Date of Examination: _____2014____
Exam Level: RO SRO-I X SRO-U Operating Test No.: _____ 1 _____
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
- a. Placing SDG In Service From Control Room S, L, D, P 6 K/A 262001.K4.06 (3.6 / 3.9) and 264000.A4.04 (3.7/3.7)
- b. Shifting from Single Element to Auto (3 element) A, S, M 2 K/A 259002 A4.06 (3.1/3.2) c.
- d. Transfer RPSPP1B from RPS MG Set B to CDP-1A S, N 7 K/A 212000 A1.11 (3.4 / 3.3) and 212000.A2.02 (3.7/3.9)
- e. RPV Depressurization with RWCU A, S, E, L, N 3 K/A 204000 A4.03 (3.2 / 3.6), 204000.A1.04 (2.8/2.8)
- f. Start HPCI From The ASD Room S, D, EN 4 K/A 206000 A1.02 (4.2/4.2) g Startup the Suppression Pool Cooling Mode of RHR (Alternate Path) A, S, D 5 K/A 219000 A4.02 (3.7 / 3.5)
- h. Separation of REC Critical Loops S, E, M 8 K/A 295018 A1A.03 (3.3 / 3.4) and AK3.07 (3.1/3.2)
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Operate the Diesel Fire Pump Manually A, E, D 8 K/A 286000; A4.06(3.4/3.4)
- j. Place 24 VDC Batteries and Associated Chargers in service D 6 K/A: 263000 K4.01(3.1/3.4) and 2.2.2 (4.6/4.1)
@ 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 Rev 1 (6/3/14)
(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 Rev 1 (6/3/14)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ____Cooper Nuclear Station_______________ Date of Examination: _____2014____
Exam Level: RO SRO-I SRO-U X Operating Test No.: _____ 1 _____
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 a.
b.
c.
- d. Transfer RPSPP1B from RPS MG Set B to CDP-1A S, N 7 K/A 212000 A1.11 (3.4 / 3.3) and 212000.A2.02 (3.7/3.9)
- e. RPV Depressurization with RWCU K/A 204000 A4.03 (3.2 / 3.6), 204000.A1.04 (2.8/2.8) A, S, E, L, N 3
h.
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Operate the Diesel Fire Pump Manually A, E, D 8 K/A 286000; A4.06(3.4/3.4) j.
@ 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 Rev 1 (6/3/14)
Nebraska Public Power District SKL0345001 Cooper Nuclear Station Page 1 of 5 Job Performance Measure for Operations Revision 0 Task No: 283016S0101
Title:
Interpret a Thermal Limits (Gardel) Report (Alt. Path)
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / Classroom
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 20 minutes
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to review and Interpret a Thermal Limits (Gardel)
Report in accordance with procedure 6.LOG.601, Daily Surveillance Log - Modes 1, 2, and 3. (Provide a copy of the latest revision of Procedure 6.LOG.601 to the candidate)
- 2. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 3. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 4. Brief the trainee and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL0345001 Cooper Nuclear Station Page 2 of 5 Job Performance Measure for Operations Revision 0 Task No: 283016S0101
Title:
Interpret a Thermal Limits (Gardel) Report (Alt. Path)
Directions to Trainee:
When I tell you to begin, you are to perform a Thermal Limits check in accordance with procedure 6.LOG.601, Daily Surveillance Log - Modes 1, 2, and 3, Attachment 2, Thermal Limits Check.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
The Plant has been Operating at 100% power for the past 120 days.
General
References:
- 1. Procedure 6.LOG.601, Daily Surveillance Log - Modes 1, 2, and 3.
- 2. Procedure 10.7, Core Thermal Limits
- 3. Procedure 10.1, APRM Gain Adjustment
- 4. Tech Spec LCO 3.9.2, General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Procedure 6.LOG.601, Daily Surveillance Log - Modes 1, 2, and 3.
- 2. Procedure 10.7, Core Thermal Limits
- 3. Critical checks denoted by bold steps.
- 4. Cues denoted by "#".
Nebraska Public Power District SKL0345001 Cooper Nuclear Station Page 3 of 5 Job Performance Measure for Operations Revision 0 Task No: 283016S0101
Title:
Interpret a Thermal Limits (Gardel) Report (Alt. Path)
Task Standards:
- 1. The operator recognizes that MFLPD is out of specification and informs the CRS that procedure 10.7, Core Thermal Limits must be performed and entry into Tech Specs LCO 3.9.2 is required.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
The Control Room Supervisor directs you to perform a Thermal Limits check in accordance with procedure 6.LOG.601, Daily Surveillance Log - Modes 1, 2, and 3, Attachment 2, Thermal Limits Check.
Record the results of your check and turn in the results to the examiner.
Nebraska Public Power District SKL0345001 Cooper Nuclear Station Page 4 of 5 Job Performance Measure for Operations Revision 0 Task No: 283016S0101
Title:
Interpret a Thermal Limits (Gardel) Report (Alt. Path)
Start Time: ____________
Performance Checklist Standards Sat Unsat Obtained the current revision of Procedure
- 1. Obtain Procedure 6.LOG.601. Selects Attachment 2. ____ ____
- 2. Reviews a GARDEL Reviewed the GARDEL Periodic Report.
print out. ____ ____
3.1The Operator entered the data from the report
- 3. Enters data on the Thermal limit checks sheet (Att. 2). ____ ____
3.2 Operator indicated MFLPD was above the limit and continued to 10.7, Core Thermal
- 4. Thermal Limit Out Limits, in accordance with note at bottom ____ ____
of Specification of page.
Operator recorded that reactor MFLPD 5 Notifies the CRS thermal limit was out of specification and ____ ____
of Thermal Limit must be returned to within limit in accordance out of Spec and with procedure 10.7, section 5, Operation required Tech Above MFLPD (LHGR) Limit.
Spec Entry Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL0345001 Cooper Nuclear Station Page 5 of 5 Job Performance Measure for Operations Revision 0 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to perform a Thermal Limits check in accordance with procedure 6.LOG.601, Daily Surveillance Log - Modes 1, 2, and 3, Attachment 2, Thermal Limits Check.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
The Plant has been Operating at 100% power for the past 120 days.
Initiating Cue(s):
The Control Room Supervisor directs you to perform a Thermal Limits check in accordance with procedure 6.LOG.601, Daily Surveillance Log - Modes 1, 2, and 3, Attachment 2, Thermal Limits Check.
Record the results of your check and turn in the results to the examiner.
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 1 of 9 Job Performance Measure for Operations Revision 0 Task No.: None
Title:
Determine Tagging Order Release Requirements Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM /Classroom
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 20 minutes
- 5. NRC K/A 2.2.13 (3.6/3.8)
Directions to Examiner:
- 1. This JPM evaluates the candidates ability to determine the proper sequence for the release of a Tagging Order and the required release positions in accordance with procedure 0.9 Tagout.
- 2. Only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Provide trainee with Attachments 2 and 3.
- 6. Brief the trainee, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 2 of 9 Job Performance Measure for Operations Revision 0 Task No.: None
Title:
Determine Tagging Order Release Requirements Directions to Trainee:
When I tell you to begin, you are to determine the proper sequence for the release and the required release positions for a Tagging Order in accordance with procedures 0.9, Tagout and 2.2.30, Fire Protection System.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
General Conditions:
- 1. The Plant is operating at 100 % power.
- 2. Maintenance has completed replacement of Fire Pump C motor.
- 3. Maintenance has requested that it be returned to service.
General
References:
- 1. Procedure 2.2.30
- 2. Procedure 0.9, Tagout General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Clearance OrderDGDO-01-4896306 FO TRANSFER.
- 2. Critical checks denoted by bold steps.
Task Standards:
- 1. The operator determine the proper sequence for the release and the required release positions for a Tagging Order in accordance with procedures 0.9 Tagout and 2.2.30, Fire Protection System.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 3 of 9 Job Performance Measure for Operations Revision 0 Task No.: None
Title:
Determine Tagging Order Release Requirements Initiating Cue(s):
Determine the proper Sequence for the release of a Tagging Order and the Required Release Positions in accordance with procedures 0.9 Tagout and 2.2.30, Fire Protection System.
Notify the CRS when the release sequence and the required release positions of the Tagging Order is complete.
NOTE: Tell the trainee to begin.
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 4 of 9 Job Performance Measure for Operations Revision 0 Task No.: None
Title:
Determine Tagging Order Release Requirements Start Time: ____________
Performance Checklist Standards Sat Unsat The Operator obtained the current revision of
- 1. Obtain Procedures Procedure 0.9, Tagout. Selected Section 16 ____ ____
Tagout Section Release and Procedure 2.2.30 The Operator recognized the current plant
- 2. Verifies current plant conditions were appropriate to place in standby ____ ____
conditions lineup.
- 3. Determine Release 16.1.1 Obtain Clearance Section: FP position for 4907476 FR-P-C and recorded component ____ ____
components positions matching Key.
16.2 Determined Clearance return sequence
- 4. Determine release per 0.9 and 2.2.30 and recorded sequence sequence numbers matching Key.
- 5. Returned order. Returned completed order to examiner. ____ ____
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 5 of 9 Job Performance Measure for Operations Revision 0 Task No.: None
Title:
Determine Tagging Order Release Requirements ATTACHMENT 1 Examiner=s copy of component positions (Answer Key)
Section: FP-1-4907476 FR-P-C Tag Type Equipment Pla Placement Place. 1st Place. 2nd Rest Rest. Config. Rest. 1st Verif Rest. 2nd Verif
--------------- Seq Config Verif Verif Seq *As left ( If Diff) Date/Time Date/Time Serial No *Equip Desc ------------ Date/Time Date/Time ------------------------
- Equip Loc *Notes *Notes Caution FP-SW-(FP-P-C) 1 Pull to Operator 1 WCO 7 AUTO
---------------------- Lock 4/1/14 0100 4/1/14 0200 ---------------------
154602 *Elec Fire Pump C *Restored per step Control Switch 6.1 of 2.2.30
- FP Panel Danger FP-CB-(FP-P-C) 2 OFF Operator 2 WCO 5 OFF
-------------------------- 4/1/14 0110 4/1/14 0211 -------------------------
152518 *FP Pump C Circuit Breaker (Disconnect Means)
- SW Pump Rm North East Danger FP-DSC-(ISO- 3 OFF Operator 2 WCO 6 ON
MEANS)C ------------- 4/1/14 0110 4/1/14 0212 -------------------------
152519 ------------------------- *Operate
- C FP Isolating Isolating Means Disconnect Means
- SW Pump Room per step North East 8.2 of 2.2.30 Danger FP-V-469 4 CLOSED Operator 2 WCO 4 Sealed OPEN
--------------------------- ------------- 4/1/14 0115 4/1/14 0216 -------------------------
152589 *Fire Pump 1C *Sealed Disch Valve *Sealed valve
- IS-SWP Rm (East)
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 6 of 9 Job Performance Measure for Operations Revision 0 Task No.: None
Title:
Determine Tagging Order Release Requirements Danger FP-V-470 5 CLOSED Operator 2 WCO 3 Sealed CLOSED
-------------------------- ------------- 4/1/14 0117 4/1/14 0216 -------------------------
152590
- Hose Nozzle *Sealed Supply From Pump Valve *Sealed valve 1C
- IS-SWP Rm (East)
Danger EE-CB-480E (FP-C) 6 RACKED Operator 2 WCO 2 Racked in/CLOSED
--------------------------- OUT 4/1/14 0121 4/1/14 0222 -------------------------
152604 *C Fire Pump ------------
- This Component *Rack Has A Motor breaker Heater*** per 2.2.19
- 480 SWGR-E IS-903 Danger EE-PNL-SPIS (11) 7 OFF Operator 2 WCO 1 ON
--------------------------- 4/1/14 0122 4/1/14 0222 -------------------------
152605 *FP 1C Motor Heater
- IS-WEST WALL-(South of Roll Up Door)
Component Note No. Note Text EE-CB-480E(FP-C) 76 CAUTION - Normal Breaker position is Racked In AND Closed
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 7 of 9 Job Performance Measure for Operations Revision 0 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to determine the proper sequence for the release and the required release positions for a Tagging Order in accordance with procedures 0.9, Tagout and 2.2.30, Fire Protection System.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
General Conditions:
- 1. The Plant is operating at 100 % power.
- 2. Maintenance has completed replacement of Fire Pump C motor.
- 3. Maintenance has requested that it be returned to service.
Initiating Cue(s):
Determine the proper Sequence for the release of a Tagging Order and the Required Release Positions in accordance with procedures 0.9 Tagout and 2.2.30, Fire Protection System.
Notify the CRS when the release sequence and the required release positions of the Tagging Order is complete.
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 8 of 9 Job Performance Measure for Operations Revision 0 Attachment 3 Candidates copy of Component positions Section: FP-1-4907476 FR-P-C Tag Type Equipment Pla Placement Place. 1st Place. 2nd Rest Rest. Config. Rest. 1st Verif Rest. 2nd Verif
--------------- Seq Config Verif Verif Seq *As left ( If Diff) Date/Time Date/Time Serial No *Equip Desc ------------ Date/Time Date/Time
- Equip Loc *Notes Caution FP-SW-(FP-P-C) 1 Pull to Operator 1 WCO
---------------------- Lock 4/1/14 0100 4/1/14 0200 154602 *Elec Fire Pump C Control Switch
- FP Panel Danger FP-CB-(FP-P-C) 2 OFF Operator 2 WCO
-------------------------- 4/1/14 0110 4/1/14 0211 152518 *FP Pump C Circuit Breaker (Disconnect Means)
- SW Pump Rm North East Danger FP-DSC-(ISO- 3 OFF Operator 2 WCO
MEANS)C ------------- 4/1/14 0110 4/1/14 0212 152519 ------------------------- *Operate
- C FP Isolating Isolating Means Disconnect Means
- SW Pump Room per step North East 8.2 of 2.2.30 Danger FP-V-469 4 CLOSED Operator 2 WCO
--------------------------- ------------- 4/1/14 0115 4/1/14 0216 152589 *Fire Pump 1C *Sealed Disch Valve
- IS-SWP Rm (East)
Danger FP-V-470 5 CLOSED Operator 2 WCO
-------------------------- ------------- 4/1/14 0117 4/1/14 0216 152590
- Hose Nozzle *Sealed Supply From Pump Valve 1C
- IS-SWP Rm (East)
Nebraska Public Power District SKL034-50-41(11754)
Cooper Nuclear Station Page 9 of 9 Job Performance Measure for Operations Revision 0 Danger EE-CB-480E (FP-C) 6 RACKED Operator 2 WCO
--------------------------- OUT 4/1/14 0121 4/1/14 0222 152604 *C Fire Pump ------------
- This Component *Rack Has A Motor breaker Heater*** per 2.2.19
- 480 SWGR-E IS-903 Danger EE-PNL-SPIS (11) 7 OFF Operator 2 WCO
--------------------------- 4/1/14 0122 4/1/14 0222 152605 *FP 1C Motor Heater
- IS-WEST WALL-(South of Roll Up Door)
Component Note No. Note Text EE-CB-480E(FP-C) 76 CAUTION - Normal Breaker position is Racked In AND Closed
Nebraska Public Power District SKL034-30-63 (44051)
Cooper Nuclear Station Page 1 of 5 Job Performance Measure for Operations Revision 00 Task No.:
Task
Title:
Radiation Protection Table Top Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR, SIM, Classroom
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 10 minutes
- 5. NRC K/A 2.3.13 (3.4/3.8)
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to determine if certain work can be performed within the confines of the Code of Federal Regulations and CNS procedures.
- 2. This JPM can be performed any place the operator can access appropriate procedures.
- 3. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes section below.
- 4. Give the trainee his copy of the Directions to the Trainee (Attachment 1) when ready to start the JPM.
- 5. Brief the trainee and tell the trainee to begin.
Notes: ______________________________________________________________________
Directions to Trainee:
When I tell you to begin, you are to determine whether John Doe can perform in-vessel work for which he is specially qualified. If you find he cannot perform the work state the reason why.
If John Doe can perform the work, state what authorization, if any is required prior to performing the work. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
Nebraska Public Power District SKL034-30-63 (44051)
Cooper Nuclear Station Page 2 of 5 Job Performance Measure for Operations Revision 00 Task No.:
Task
Title:
Radiation Protection Table Top General Conditions:
- 1. The plant is shutdown to perform in-vessel work.
- 2. John Doe has been selected for a particular job in vessel.
General
References:
- 1. 10CFR20
- 2. 9.ALARA.1, PERSONNEL DOSIMETRY AND OCCUPATIONAL RADIATION EXPOSURE PROGRAM.
General Tools and Equipment:
- 1. None.
Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted in bold.
Task Standards:
- 1. The student determines the work can be performed and the department personnel that must approve the dose.
- 2. 100% of critical elements successfully completed without error.
Initiating Cue(s):
John Doe has unique skills to perform special in vessel work. Performance of the work is expected to result in a whole body dose of 550 mRem. The Shift Manager directs you to determine based on John Doe's dose history, whether he is capable of performing this work.
When I tell you to begin, you are to determine whether John Doe can perform the in-vessel work. If you find he cannot perform the work state the reason why. If John Doe can perform the work, state what authorization, if any is required prior to performing the work. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
Nebraska Public Power District SKL034-30-63 (44051)
Cooper Nuclear Station Page 3 of 5 Job Performance Measure for Operations Revision 00 Task No.:
Task
Title:
Radiation Protection Table Top Time Start: _________
Performance Checklist Standards Sat Unsat
- 2. Pertinent personal Dose 9.ALARA.1 step 6.7.2.1 .Dose History is history is reviewed. reviewed.
- 3. Pertinent job dose projections for the job are Dose projections are reviewed.
reviewed.
- 4. Compares the job requirements to the amount Job requirements are reviewed.
of dose that can be received.
9.ALARA.1 step 6.2.1.2.
- 5. Calculates expected Expected cumulative dose is calculated cumulative dose. at 2.050 Rem on-site and 2.250 Rem total.
9.ALARA.1 step 6.2.1.2.
- 6. Off-site dose verified Operator verifies off-site dose does not within limit.
exceed 1.5 Rem (1500 mrem).
9.ALARA.1 step 6.2.1.2.
The Operator informs the Shift Manager that the work can be done, but the
- 7. Informs the SM that he Department Manager, RP Technical can perform this job. Supervisor, Radiation Protection Manager, and the GMPO must authorize the dose extension above 2,000 mRem.
Time Stop: __________ Total Time: ___________
Nebraska Public Power District SKL034-30-63 (44051)
Cooper Nuclear Station Page 4 of 5 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to determine whether John Doe can perform in-vessel work for which he is specially qualified. If you find he cannot perform the work state the reason why.
If John Doe can perform the work, state what authorization, if any is required prior to performing the work. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
General Conditions:
- 1. The plant is shutdown to perform in-vessel work.
- 2. You have been selected for a particular job in vessel.
Initiating Cue(s):
John Doe has unique skills to perform special in vessel work. Performance of the work is expected to result in a whole body dose of 550 mRem. The Shift Manager directs you to determine based on John Doe's dose history, whether he is capable of performing this work.
When I tell you to begin, you are to determine whether John Doe can perform the in-vessel work. If you find he cannot perform the work state the reason why. If John Doe can perform the work, state what authorization, if any is required prior to performing the work. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
Nebraska Public Power District SKL034-30-63 (44051)
Cooper Nuclear Station Page 5 of 5 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 Your Pertinent Statistics John Doe's Age: 35 years Lifetime TEDE: 32 Rem On-Site TEDE so far this year: 1.5 Rem Off-Site TEDE so far this year: 0.2 Rem Pertinent Job Dose Projections for the one individual performing this job Projected Whole Body Dose: 550 mRem Results:
Perform the Job: Yes No Circle one If allowed to perform the work, whos authority is needed first?
Signature
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 1 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
ALTERNATE PATH JPM Additional Program Information:
- 1. Appropriate Performance Locations: Control Room / Classroom / Simulator
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 10 minutes
- 5. K/A: A295013 AA201 (3.8/4.0) 2.1.12 (2.9/4.0)
NOTE: THIS IS AN ALTERNATE PATH JPM. Some temperatures are upscale and an alternate method must be used to obtain the average temperature.
Directions to Examiner:
- 1. The intent of this JPM is to present a trainee a set of conditions for determination of average Torus temperature upon loss of SPDS and to make expected recommendations to the Control Room Supervisor, in accordance with procedure 5.8.9, Average Suppression Pool Temperature Calculation.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 4. Give the trainee his copy of the Directions to the Trainee (Attachment 2) when ready to start the JPM.
- 5. IF NOT performing in the simulator, give the trainee a copy of Attachment 3.
- 6. Brief the trainee and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 2 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
Directions to Trainee:
When I tell you to begin, you are to use the provided attachment to determine average Torus temperature and make expected recommendations to the Control Room Supervisor, in accordance with procedure 5.8.9, Average Suppression Pool Temperature Calculation.
Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. RHR A Loop is in Torus cooling
- 2. Activities have been in progress that added significant heat to the torus.
- 3. PMIS/SPDS is unavailable.
General
References:
- 1. Procedure 5.8.9; Average Suppression Pool Temperature Calculations General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by "*".
- 2. Simulator cues denoted by "#".
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 3 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
Task Standards:
- 1. 100% of critical elements successfully completed without error.
- 2. 100% of safety and radiological work practices.
Initiating Cue(s):
You are to determine average Torus temperature per ESP 5.8.9. Average Suppression Pool Temperature Calculation.
Return the completed Attachment 1 of 5.8.9 to the Control Room Supervisor when you have completed this task.
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 4 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
Start Time: ___________
Performance Checklist Standards Sat Unsat
- 1. Obtains Procedure Obtained Procedure 5.8.9, Attachment 1.
5.8.9, SP Temperature ____ ____
Calculations
- 2. Record time. The operator recorded the current time on Attachment 1 of 5.8.9. ____ ____
- 3. Notes that two The operator recorded the four (4) highest temperatures are suppression pool temperatures but notes ____ ____
upscale and proceeds that two are upscale and proceeds to Step to Step 3.2. 3.2.
CUE: When the Operator finds the correct recorders provide them with the marked up pictures of the recorders (Attachment 3) and tell him to use them instead of the values on the panel mounted recorders.
- 4. Recognizes that A The operator noted that A RHR is in Torus RHR is in Torus Cooling and performs step 3.2.1. ____ ____
Cooling.
CUE: When the Operator finds the correct recorder provide them with the marked up picture of the recorder (Attachment 3) and tell him to use them instead of the values on the panel mounted recorder.
- 5. Finds temperature on The operator noted that the temperature for PC-TR-131 for RHR A the suction of the RHR loop in SPC is 1200F ____ ____
Loop. on RHR-TR-131 CH1.
Allowable values: 1200F
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 5 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
Performance Checklist Standards Sat Unsat
- 6. Returns the completed The operator returned the completed Attachment 1 to the Attachment 1 to the Control Room Supervisor. ____ ____
examiner.
Stop Time: __________ Stop Time: __________
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 6 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in any IC that has or had the reactor at power (IC-18, 19 or 20 suggested)
Batch File name - None.
C. Change the Simulator conditions from those of the IC as follows:
- 1. Triggers Number File Name Description None
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial None
- 3. Remotes Number Title Trigger Value Ramp None
- 4. Overrides
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 7 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
Instrument Tag Trigger TD Value Ram p
PC-TR-24 Channel 1 20A1AR1 Chan 1 N/A N/A 115.10F N/A PC-TR-24 Channel 2 20A1AR1 Chan 2 N/A N/A 250.00F N/A PC-TR-24 Channel 3 20A1AR1 Chan 3 N/A N/A 121.90F N/A PC-TR-24 Channel 4 20A1AR1 Chan 4 N/A N/A 124.90F N/A PC-TR-24 Channel 5 20A1AR1 Chan 5 N/A N/A 118.20F N/A PC-TR-24 Channel 6 20A1AR1 Chan 6 N/A N/A 120.30F N/A PC-TR-24 Channel 7 20A1AR1 Chan 7 N/A N/A 121.00F N/A PC-TR-24 Channel 8 20A1AR1 Chan 8 N/A N/A 118.10F N/A PC-TR-25 Channel 1 20A1AR2 Chan 1 N/A N/A 118.10F N/A PC-TR-25 Channel 2 20A1AR2 Chan 2 N/A N/A 128.20F N/A PC-TR-25 Channel 3 20A1AR2 Chan 3 N/A N/A 124.90F N/A PC-TR-25 Channel 4 20A1AR2 Chan 4 N/A N/A 250.00F N/A PC-TR-25 Channel 5 20A1AR2 Chan 5 N/A N/A 115.20F N/A PC-TR-25 Channel 6 20A1AR2 Chan 6 N/A N/A 124.30F N/A PC-TR-25 Channel 7 20A1AR2 Chan 7 N/A N/A 117.00F N/A PC-TR-25 Channel 8 20A1AR2 Chan 8 N/A N/A 125.10F N/A RHR-TR-131 Channel 1 07A1AR6 Chan 1 N/A N/A 1200F N/A RHR-TR-131 Channel 2 07A1AR6 Chan 2 N/A N/A 950F N/A RHR-TR-131 Channel 3 07A1AR6 Chan 3 N/A N/A 1180F N/A RHR-TR-131 Channel 4 07A1AR6 Chan 4 N/A N/A 880F N/A RHR-TR-131 Channel 5 07A1AR6 Chan 5 N/A N/A 980F N/A RHR-TR-131 Channel 6 07A1AR6 Chan 6 N/A N/A 980F N/A
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 8 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 Task
Title:
Suppression Pool Temp Calculation (Alternate Path)
- 5. Panel Set-up (suggested. Any setup is allowed that supports performance of this JPM.
- a. Place the Simulator in RUN.
- b. Insert Batch File Note: If this JPM is to be performed more than once, snap the Simulator into an IC after the panel set-up is complete.
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 9 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to use the provided attachment to determine average Torus temperature and make expected recommendations to the Control Room Supervisor, in accordance with procedure 5.8.9, Average Suppression Pool Temperature Calculation.
Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. RHR A Loop is in Torus cooling
- 2. Activities have been in progress that added significant heat to the torus.
- 3. PMIS/SPDS is unavailable.
Initiating Cue:
You are to determine average Torus temperature per ESP 5.8.9. Average Suppression Pool Temperature Calculation.
Return the completed Attachment 1 of 5.8.9 to the Control Room Supervisor when you have completed this task.
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 10 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 ATTACHMENT 3 SUPPR POOL TEMP RECORDER PC-TR-24
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 11 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 ATTACHMENT 3 SUPPR POOL TEMP RECORDER PC-TR-25
Nebraska Public Power District SKL034-21-131 (41928)
Cooper Nuclear Station Page 12 of 12 Job Performance Measure for Operations Revision 03 Task No.: 200225A0501 ATTACHMENT 3 RHR HEAT EXCHANGER TEMPERATURE RECORDER RHR-TR-131
Nebraska Public Power District SKL0345080 Cooper Nuclear Station Page 1 of 5 Job Performance Measure for Operations Revision 0 Task No.: 344077S0403
Title:
Determine the Action for Plant Chemistry Out of Specification (Alt. Path)
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Classroom
- 2. Appropriate Trainee level: SRO
- 3. Evaluation Method: Simulate
- 4. Performance Time: 20 minutes
- 5. NRC K/A 2.1.34 (SRO 3.5)
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to review Reactor Coolant Chemistry parameters and take actions for plant chemistry out of specifications in accordance with Procedure 2.4CHEM.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL0345080 Cooper Nuclear Station Page 2 of 5 Job Performance Measure for Operations Revision 0 Task No.: 344077S0403
Title:
Determine the Action for Plant Chemistry Out of Specification (Alt. Path)
Directions to Trainee:
When I tell you to begin, you are to perform a Shift Manager review of Reactor Coolant Chemistry data and inform me when actions are complete. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. The Plant has been Operating at 100% power for the past 120 days.
General
References:
- 1. Procedure 2.4 CHEM, Chemistry Parameter Out of Limit
- 2. TRM Section 3.4.1, Reactor Coolant System
- 3. Chemistry Procedure 8.3, Control Parameters and Limits General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
Procedure 2.4 CHEM, Chemistry Parameter Out of Limit TRM Section 3.4.1, Reactor Coolant System Chemistry Procedure 8.3, Control Parameters and Limits Critical checks denoted in bold.
Simulator cues denoted by "#".
Task Standards:
- 1. The operator recognizes that plant chemistry is out of specification and determines that TLCO 3.4.1 has been exceeded and TRM entry is required.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
Nebraska Public Power District SKL0345080 Cooper Nuclear Station Page 3 of 5 Job Performance Measure for Operations Revision 0 Task No.: 344077S0403
Title:
Determine the Action for Plant Chemistry Out of Specification (Alt. Path)
When I tell you to begin, you are to perform a Shift Manager review of Reactor Coolant Chemistry data and inform me when actions are complete.
Chemistry has conducted a reactor coolant sample in accordance with Chemistry Procedure 8.3, Control Parameters and Limits, and notified you of the following results:
Conductivity 10.0 umho/cm Chlorides 12.0 ppb pH 6.9 Sulfates 0.77 ppb Silica 25 ppb Sodium 2.1 ppb Calcium 2.0 ppb Zinc 2.6 ppb Tritium Non Detectable Boron Non Detectable Notify the Shift Manager when your review is complete, including any action taken.
Nebraska Public Power District SKL0345080 Cooper Nuclear Station Page 4 of 5 Job Performance Measure for Operations Revision 0 Start Time: ____________
Performance Checklist Standards Sat Unsat The Operator recognizes that conductivity is
- 1. Reviews data. out of specification and enters Procedure 2.4CHEM.
Obtained the current revision of Procedure
- 2. Obtain Procedure.
2.4CHEM. Selects Section 1.0.
1.1.1 Operator recognized Reactor power > 10%
RTP and Reactor water conductivity > 1.0
- 3. Entry Condition met. µmho limit was exceeded and continued to Section 4.0 Subsequent Operator Actions.
- 4. Date and Time 4.1 Operator records the current date and time.
entered.
4.2 Operator determined the TRM limit for TLCO 3.4.1 are exceeded and refers to TRM
- 5. TRM limit condition B and determines Action B.1 is exceeded. required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time the limits were exceeded for required condition.
4.3 Operator notifies Chemistry that Conductivity is out-of-limit.
- 6. Notify Chemistry.
Operator notifies Operations Manager that reactor coolant chemistry is out of specification and 5 Notifies Operations exceeded the limit for Conductivity in table 3.4.1-1 Manager. and must be returned to within limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time the limit was exceeded.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL0345080 Cooper Nuclear Station Page 5 of 5 Job Performance Measure for Operations Revision 0 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to perform a Shift Manager review of Reactor Coolant Chemistry data and inform me when actions are complete. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
General Conditions:
The Plant has been Operating at 100% power for the past 120 days.
Initiating Cue(s):
The Shift Manager directs you, as the CRS, to review Reactor Coolant Chemistry sample parameters below and record any take action, if required, for continued plant operation.
Chemistry has conducted a reactor coolant sample in accordance with Chemistry Procedure 8.3, Control Parameters and Limits, and notified you of the following results:
Conductivity 10.0 umho/cm Chlorides 12.0 ppb pH 6.9 Sulfates 0.77 ppb Silica 25 ppb Sodium 2.1 ppb Calcium 2.0 ppb Zinc 2.6 ppb Tritium Non Detectable Boron Non Detectable Notify the CRS when your review is complete, including any action taken.
Record your actions/findings below:
Signature
Nebraska Public Power District SKL034-20-114 (29981)
Cooper Nuclear Station Page 1 of 6 Job Performance Measure for Operations Revision 03 Task No.: 341033W0303
Title:
Determine Shift Staffing Requirements for Mode Change Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM / Classroom
- 3. Evaluation Method: Perform
- 4. Performance Time: 10 minutes
- 5. K/A 2.1.4 (3.4)
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to determine shift staffing requirements for a mode change.
- 2. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 3. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes section below.
- 4. Give the examinee Attachment 1.
- 5. Brief the trainee, and tell the trainee to begin.
Notes: ______________________________________________________________________
Nebraska Public Power District SKL034-20-114 (29981)
Cooper Nuclear Station Page 2 of 6 Job Performance Measure for Operations Revision 03 Task No.: 341033W0303
Title:
Determine Shift Staffing Requirements for Mode Change Directions to Trainee:
When I tell you to begin, you are to evaluate the staff available and determine if a change in Modes is allowed. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
General Conditions:
- 1. The plant conditions are as follows:
- Reactor Pressure is 0 psig and steady.
- Coolant temperature is 200°F and steady.
- All reactor vessel head closure bolts are fully tensioned.
- Mode Switch is in Shutdown
- 2. Your Shift complement is comprised of:
- One SRO (you)
- Two ROs
- Three Non-Licensed Nuclear Plant Operators
- One RP/Chem Tech General
References:
- 1. Conduct of Operations Procedure 2.0.3 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted in bold.
Task Standards:
- 1. Determines current staffing is adequate, and additional staffing will be required when the mode change is made.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Nebraska Public Power District SKL034-20-114 (29981)
Cooper Nuclear Station Page 3 of 6 Job Performance Measure for Operations Revision 03 Task No.: 341033W0303
Title:
Determine Shift Staffing Requirements for Mode Change Initiating Cue(s):
During your shift Reactor Coolant temperature is expected to rise to 215°F as a result of Shutdown Cooling being removed from service. As the Senior Licensed person on your shift, you are to determine two things;
- 1. Do you have sufficient staff now, and
- 2. will you have sufficient staff to allow you to raise Coolant Temperature to 215°F during your shift. If not determine how many additional staff types are needed and document your findings on Attachment 1.
NOTE: Tell the trainee to begin.
Nebraska Public Power District SKL034-20-114 (29981)
Cooper Nuclear Station Page 4 of 6 Job Performance Measure for Operations Revision 03 Task No.: 341033W0303
Title:
Determine Shift Staffing Requirements for Mode Change Start Time: ____________
Performance Checklist Standards Sat Unsat
- 1. Obtain Procedure Current revision of 2.0.3 obtained.
2.0.3.
- 2. Determines the The SRO may use Tech Specs to confirm that the current mode. Unit is in MODE 4.
- 3. Determines the mode to be The SRO may use Tech Specs to confirm that entered when the Unit will be entering Mode 3 within the temperature rises shift.
to 215ºF.
Your Shift complement is comprised of:
- 4. Determines that
- One SRO (you) the current shift
- Two ROs staff is adequate
- Three Non-Licensed Nuclear Plant until the mode Operators change.
- One RP/Chem Tech For Mode 3 the SRO determines the following staff types are needed:
- 5. Determines which
- Three Non-Licensed Nuclear Plant Operators
- One STE
- One RP/Chem Tech SRO records the additional needed staff on Attachment 1.
- 6. Records the needed Staff on
Attachment 1.
- One STE
Nebraska Public Power District SKL034-20-114 (29981)
Cooper Nuclear Station Page 5 of 6 Job Performance Measure for Operations Revision 03 Task No.: 341033W0303
Title:
Determine Shift Staffing Requirements for Mode Change Performance Checklist Standards Sat Unsat
- 7. Turns in completed Returns completed Attachment 1 to evaluator.
paperwork.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-20-114 (29981)
Cooper Nuclear Station Page 6 of 6 Job Performance Measure for Operations Revision 03 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to evaluate the staff available and determine if a change in Modes is allowed. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
General Conditions:
- 1. The plant conditions are as follows:
- Reactor Pressure is 0 psig and steady.
- Coolant temperature is 200°F and steady.
- All reactor vessel head closure bolts are fully tensioned.
- Mode Switch is in Shutdown
- 3. Your Shift complement is comprised of:
- One SRO (you)
- Two ROs
- Three Non-Licensed Nuclear Plant Operators
- One RP/Chem Tech Initiating Cue(s):
During your shift Reactor Coolant temperature is expected to rise to 215°F as a result of Shutdown Cooling being removed from service. As the Senior Licensed person on your shift, you are to determine two things;
- 1. Do you have sufficient staff now, and
- 2. will you have sufficient staff to allow you to raise Coolant Temperature to 215°F during your shift. If not determine how many additional staff types are needed and document your findings on Attachment 1.
Current Staff:
(Check one) Adequate in current mode Inadequate in current mode Additional needed staff:_________________________________________________________
Staff required at 215ºF:
(Check one) Current staff adequate Additional staff needed.
Additional needed staff: ________________________________________________________
Nebraska Public Power District SKL034-50-18 (8783)
Cooper Nuclear Station Page 1 of 4 Job Performance Measure for Operations Revision: 00 Task No.: 200302G0203
Title:
Determine Post-Maintenance Testing Requirements Trainee: Examiner:
Pass: Fail: Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Classroom
- 3. Evaluation Method: Perform Simulate
- 4. Performance Time: 10 minutes
- 5. NRC K/A 2.2.7 (2.0/3.2)
Directions to Examiner:
- 1. This JPM evaluates the trainees ability to determine the post maintenance testing for RHR-MOV-MO26A following bonnet gasket replacement per Maintenance Procedure 7.0.5, Post-maintenance Testing.
- 2. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 3. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 4. Give the trainee his copy of the Directions to the Trainee (Attachment 1) when ready to start the JPM.
- 5. Brief the trainee and tell the trainee to begin.
Directions to Trainee:
When I tell you to begin, you are to determine the post maintenance testing for RHR-MOV-MO26A following bonnet gasket replacement. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using.
State the position of controls as you would have manipulated them in order to complete the assigned task.
Nebraska Public Power District SKL034-50-18 (8783)
Cooper Nuclear Station Page 2 of 4 Job Performance Measure for Operations Revision: 00 Task No.: 200302G0203
Title:
Determine Post-Maintenance Testing Requirements General Conditions:
- 1. The Reactor is shutdown with an outage in progress.
General
References:
- 1. Procedure 7.0.5, POST MAINTENANCE TESTING
- 2. Procedure 0.26, SURVEILLANCE PROGRAM General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Critical steps denoted in bold text.
Task Standards:
- 1. 100% of critical elements successfully completed without error.
- 2. 100% of safety and radiological work practices.
Initiating Cue(s):
The Shift Manager directs you to determine the post maintenance testing requirements to assign to RHR-MOV-MO26A following bonnet gasket replacement. Inform the Shift Manager when you have determined the requirements.
Performance Standard SAT Unsat Checklist
- 1. Obtains Procedure 7.0.5, Post The Operator obtained the current revision of 7.0.5.
Maintenance Testing.
- 2. Identify component Determines that RHR-MOV-MO26A is a motor operated type for RHR-MOV- gate valve MO26A.
- 3. Locate the general Candidate locates the Component Test Matrices for component from Motor Operated Valve (Gate/Globe).
Procedure 7.0.5 Attachment 1 index.
Nebraska Public Power District SKL034-50-18 (8783)
Cooper Nuclear Station Page 3 of 4 Job Performance Measure for Operations Revision: 00 Task No.: 200302G0203
Title:
Determine Post-Maintenance Testing Requirements Performance Standard SAT Unsat Checklist
- 4. Identify, on the Candidate Identifies Bonnet Gasket Replacement on the matrices, the type of Matrices.
corrective and/or preventive maintenance to be performed on RHR-MOV-MO26A.
- 5. Determine the test From attachment 1, the candidate assigns Leak Test, activities for the Static VOTES test. (Open/Closed Flow test is not bonnet gasket required for this valve.
replacement on RHR-MOV-MO26A.
NOTE: In the following step the student MAY elect to perform only portions of the following surveillances as indicated in Procedure 0.26, Surveillance Program.
6.PC.501 is overall procedure. 6.PC.518 is the RHR LLRT procedure.
- 6. Determine the test Candidate assigns 6.PC.501 (LLRT), 6.1RHR.201 procedures (Timed IST FSO/FSC), and 6.MISC.401 (Position indicated by Indication) to post maintenance testing.
Procedure 7.0.5, Attachment 2.
Informs the Shift Manager of the post maintenance testing requirements to assign to the work package
- 7. Shift manager informed.
Nebraska Public Power District SKL034-50-18 (8783)
Cooper Nuclear Station Page 4 of 4 Job Performance Measure for Operations Revision: 00 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to determine the post maintenance testing for RHR-MOV-MO26A following bonnet gasket replacement. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using.
State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The Reactor is shutdown with an outage in progress.
Initiating Cue(s):
The Shift Manager directs you to determine the post maintenance testing requirements to assign to RHR-MOV-MO26A following bonnet gasket replacement. Inform the Shift Manager when you have determined the requirements.
Nebraska Public Power District SKL034-30-61(29980)
Cooper Nuclear Station Page 1 of 6 Job Performance Measure for Operations Revision 01 Task No.: 200335G0503
Title:
PAR Table Top X Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Classroom / SIM
- 3. Evaluation Method: Perform
- 4. Performance Time: 10 minutes
- 5. K/A: 2.4.44 (2.1 / 4.0)
Directions to Examiner:
- 2. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 3. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes section below.
- 4. Brief the trainee, and tell the trainee to begin.
Notes: ______________________________________________________________________
Nebraska Public Power District SKL034-30-61(29980)
Cooper Nuclear Station Page 2 of 6 Job Performance Measure for Operations Revision 01 Task No.: 200335G0503
Title:
PAR Table Top X Directions to Trainee:
When I tell you to begin, you are to determine Protective Action Recommendations for the provided conditions. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
During task performance, it is recommended that you limit your discussion/demonstration to the minimum required. The examiner may ask questions of you if necessary to understand your actions.
General Conditions:
- 2. There IS a radioactive release in excess of ODAM limits at this time.
- 3. ERP release rate is 1.33E9 Ci/sec
- 4. A steam leak from HPCI is occurring.
- 5. CNS-DOSE is NOT available due to software error.
- 6. The core is degraded.
- 7. The stability class is F.
- 8. The wind is at 5 mph.
- 9. The wind is from 270°
- 10. There is NO precipitation 11 The below information has been determined a using hand calculation from EPIP 5.7.17 DOSE Projection Data Distance From Projected Integrated Dose (Rem) Projected Dose Rate (Rem/hr)
Plant TEDE CDE (Thyroid) TEDE CDE (Thyroid)
Site Boundary 1.63E-05 4.39E-05 4.08E-6 1.10E-05 2 Miles 5.64E-02 1.52E-01 1.41E-02 3.80E-02 5 Miles 7.57E-01 2.04E-00 1.89E-01 5.10E-01 10 Miles 1.25E-00 2.69E-00 205E-01 6.73E-01
Nebraska Public Power District SKL034-30-61(29980)
Cooper Nuclear Station Page 3 of 6 Job Performance Measure for Operations Revision 01 Task No.: 200335G0503
Title:
PAR Table Top X General
References:
- 1. Procedure 5.7.1, EAL Matrix
- 2. Procedure 5.7.6, Attachment 3
- 3. Procedure 5.7.20 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted in bold.
Task Standards:
- 1. The trainee correctly determines affected Sectors and determines evacuation and sheltering Sectors.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
You are to determine the appropriate Protective Action Recommendations (PARs) for the provided conditions. Complete the PAR table and return it to the examiner when you have completed this task.
NOTE: Tell the trainee to begin.
Nebraska Public Power District SKL034-30-61(29980)
Cooper Nuclear Station Page 4 of 6 Job Performance Measure for Operations Revision 01 Task No.: 200335G0503
Title:
PAR Table Top X Start Time: ____________
Performance Checklist Standards Sat Unsat
- 1. Refer to Procedure The operator may refer to Procedure 5.7.2.
5.7.2. Determines 5.7.20 must be used for PARs.
- 2. Refer to Procedure The operator refers to Procedure 5.7.20.
5.7.20.
- 3. Determines The operator determines the affected sectors affected sectors. for wind direction of 270°.
Sectors D, E, F EVACUATE
- 4. Determine Sectors 0-2 miles ALL that must be 2-5 miles Sectors D,E,F evacuated.
5-10 miles Sectors D,E,F The Operator determines the following GO INDOORS sectors:
- 5. Determines Sectors that must GO INDOORS Go Indoors and 2 - 5 miles All Remaining Sectors monitor EAS/EBS.
5-10 miles All Remaining Sectors
- 6. Turns in completed paperwork. Returns completed Attachment 1 to evaluator.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-30-61(29980)
Cooper Nuclear Station Page 5 of 6 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 (Page 1 of 2)
Directions to Trainee:
When I tell you to begin, you are to determine Protective Action Recommendations for the provided conditions. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
During task performance, it is recommended that you limit your discussion/demonstration to the minimum required. The examiner may ask questions of you if necessary to understand your actions.
General Conditions:
- 2. There IS a radioactive release in excess of ODAM limits at this time.
- 3. ERP release rate is 1.33E9 Ci/sec
- 4. A steam leak from HPCI is occurring.
- 5. CNS-DOSE is NOT available due to software error.
- 6. The core is degraded.
- 7. The stability class is F.
- 8. The wind is at 5 mph.
- 9. The wind is from 270°
- 10. There is NO precipitation 11 The below information has been determined a using hand calculation from EPIP 5.7.17 DOSE Projection Data Distance From Projected Integrated Dose (Rem) Projected Dose Rate (Rem/hr)
Plant TEDE CDE (Thyroid) TEDE CDE (Thyroid)
Site Boundary 1.63E-05 4.39E-05 4.08E-6 1.10E-05 2 Miles 5.64E-02 1.52E-01 1.41E-02 3.80E-02 5 Miles 7.57E-01 2.04E-00 1.89E-01 5.10E-01 10 Miles 1.25E-00 2.69E-00 205E-01 6.73E-01 Initiating Cue(s):
You are to determine the appropriate Protective Action Recommendations (PARs) for the provided conditions. Complete the PAR table and return it to the examiner when you have completed this task.
Nebraska Public Power District SKL034-30-61(29980)
Cooper Nuclear Station Page 6 of 6 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 (Page 2 of 2)
Protective Action Recommendations (PARS)
None Evacuate Sectors Go indoors and monitor EAS/EBS in Sectors 0-2 Miles 2-5 Miles 5-10 Miles REMARKS for 5.7.6 Attachment 3:
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 1 of 8 Job Performance Measure for Operations Revision 1 Task No.: 34401400303
Title:
Medical Emergency (#1)
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: SIM / Classroom
- 3. Evaluation Method: Perform
- 4. Performance Time: 15 minutes
- 5. NRC K/A 2.4.38 (2.2/4.0);2.4.43 (2.8/3.5)
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to perform the required actions for an injured contaminated person who must be taken to the local hospital for treatment in accordance with Procedure 5.7.24, Medical Emergency.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 2 of 8 Job Performance Measure for Operations Revision 1 Task No.: 34401400303
Title:
Medical Emergency (#1)
Directions to Trainee:
When I tell you to begin, you are to perform the required actions for an injured contaminated person who must be taken to the local hospital for treatment, in accordance with Procedure 5.7.24, Medical Emergency.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. A plant transient is in progress.
- 2. The Shift Manager is unavailable and has delegated you to handle this situation in his place.
- 3. The board operators are busy with the plant transient and are unavailable to support your evolution. You must personally perform any communications required for this situation.
General
References:
- 1. Procedure 5.7.24, Medical Emergency General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by bold steps.
- 2. Simulator cues denoted by "#".
Task Standards:
- 1. The Operator must perform the required actions for an injured contaminated person who must be taken to the local hospital for treatment, in accordance with Procedure 5.7.24, Medical Emergency.
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 3 of 8 Job Performance Measure for Operations Revision 1 Task No.: 34401400303
Title:
Medical Emergency (#1)
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
At 2:35 p.m. you are informed by a station operator that Bob Smith was working in the radwaste basement next to the spent resin storage tank when he fell from a scaffold. He is bleeding from the head and appears to have broken his left arm.
The Control Room Supervisor directs you to perform the required actions for an injured contaminated person who must be taken to the local hospital for treatment in accordance with Procedure 5.7.24, Medical Emergency.
Notify the SM when you have performed the required control room actions for this situation.
NOTE: Tell the trainee to begin.
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 4 of 8 Job Performance Measure for Operations Revision 1 Start Time: ____________
Performance Checklist Standards Sat Unsat The Operator obtained the current revision of
- 1. Obtain Procedure Procedure 5.7.24, Medical Emergency Selected Attachment 2, Shift Manager.
1.0 The Operator notified the EMTs and dispatched them to the medical emergency by one of the following methods:
- a. EMT pager group via the ANS phone; select EMT PAGE button followed by the Callback CR button. (primary method)
- 2. Alert the EMTs b. EMT pager group (402) 633-0930; put in call-back phone number. (alternate method)
- c. Gaitronics announcement. (alternate method)
CUE: EMTs acknowledge the notification and are reporting to the location.
2.0 Informed EMTs that an individual working in the Radwaste basement next to the
- 3. Inform all EMTs of spent resin storage tank has fallen from a the emergency. scaffold, is bleeding and appears to have a broken left arm.
CUE: Second EMT acknowledges the information and is in route to the scene.
3.0 Directed the third EMT to obtain keys from Access Control if necessary, start the
- 4. Designate the third ambulance, and monitor Frequency 3 for responding EMT to directions.
obtain keys to the ambulance. CUE: EMT states he will obtain the keys, start the ambulance and will await further instructions by monitoring Frequency 3.
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 5 of 8 Job Performance Measure for Operations Revision 1 Performance Checklist Standards Sat Unsat 6.0 Directs the Chem/RP Technician to report to the scene with instrumentation suitable for frisking.
- 5. Dispatch the on-shift Chem/RP Technician CUE: Chem/RP technician reports he is at the to the scene. scene already. The victim is contaminated and reads 200 mr/hr at six inches.
7.0 Directs Incident Commander to report to
- 6. Dispatch the the scene with a communication device.
Incident Commander to the CUE: Fire Brigade Leader reports that he has scene. arrived on the scene awaiting further instructions.
8.0 Made announcement similar to Attention all station personnel, MEDICAL EMERGENCY, MEDICAL EMERGENCY, all personnel stay off Gaitronics unless
- 7. Makes Gaitronics emergency-related. Repeat.
announcement Evaluator Note: Do not have the person make the announcement if any person who also will be taking this JPM is within earshot. Have the person tell you what announcement he would make.
9.0 Directed the General Manager of Operations or Operations manager to notify the victims
- 8. Notify the General family.
Manager of Operations or CUE: The Operations manager acknowledges Operations Manager. the information and will make the necessary contact.
10.0 Established communications by radio using Frequency 3 or by F2 on console
- 9. Establish with the Incident Commander.
communication with the Incident Commander. CUE: Incident Commander acknowledges via the radio that he hears you loud and clear.
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 6 of 8 Job Performance Measure for Operations Revision 1 Performance Checklist Standards Sat Unsat 11.0 Asked the Incident Commander if the victim will be transported as
- 10. Determine if the contaminated or non-contaminated.
victim will be transported as CUE: As the Incident Commander state The contaminated or victim will be transported contaminated, non-contaminated. he is bleeding from a large cut on his head and has a compound fracture of his left arm.
12.0 Directed the CNS ambulance crew to transport victim to the Nemaha County Hospital and verifies the ambulance crew has an EMT, Chem/RP, and driver
- 11. Coordinate with available. (This is sub step 12.2.1)
CNS ambulance to transport the victim. CUE: As the Incident Commander (FBL) state An EMT as driver and the EMT and CHEM/RP personnel are at the ambulance and will be transporting the patient to the hospital.
- 12. Coordinate 12.3 Coordinates with Security and Verified ambulance ambulance has left CNS.
departure with station security CUE: Ambulance has left CNS.
14.0 Contacts hospital and informs the Emergency Room Supervisor or Floor Supervisor of the victims conditions (bleeding from head, compound fracture
- 13. Contact the of left arm and contaminated). Gave the Nemaha County hospital an ETA.
Hospital.
CUE: Hospital acknowledges receiving the communication and will be prepared to treat the victim upon arrival.
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 7 of 8 Job Performance Measure for Operations Revision 1 Performance Checklist Standards Sat Unsat 15.0 Makes Gaitronics announcement similar to Attention all station personnel, the medical emergency is terminated, resume normal operations. Repeat.
- 14. Make Gaitronics Evaluator Note: Do not have the person make announcement.
the announcement if any person who also will be taking this JPM is within earshot. Have the person tell you what announcement he would make.
16.0 Verify contact has been made with the victims immediate family by the General Manager of Operations or Operations Manager.
- 15. Verify family notification. Note: When asked by the trainee if the victims family has been notified provide the following:
CUE: The Operations Manager has contacted the victims family.
The Operator informed the Shift Manager that all
- 16. Notifies the Shift required control room actions for this situation.
Manager Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-21-131 Cooper Nuclear Station Page 8 of 8 Job Performance Measure for Operations Revision 1 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to perform the required actions for an injured contaminated person who must be taken to the local hospital for treatment, in accordance with Procedure 5.7.24, Medical Emergency.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. A plant transient is in progress.
- 2. The Shift Manager is unavailable and has delegated you to handle this situation in his place.
- 3. The board operators are busy with the plant transient and are unavailable to support your evolution. You must personally perform any communications required for this situation.
Initiating Cue(s):
At 2:35 p.m. you are informed by a station operator that Bob Smith was working in the radwaste basement next to the spent resin storage tank when he fell from a scaffold. He is bleeding from the head and appears to have broken his left arm.
The Control Room Supervisor directs you to perform the required actions for an injured contaminated person who must be taken to the local hospital for treatment in accordance with Procedure 5.7.24, Medical Emergency.
Notify the SM when you have performed the required control room actions for this situation.
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 1 of 8 Job Performance Measure for Operations Revision 02 Task No.: None
Title:
Placing SDG In Service From Control Room Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 20 minutes
- 5. NRC K/A 262001.K4.06 (3.6 / 3.9) and 264000.A4.04 (3.7/3.7)
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to start and place in service the Supplemental Diesel Generator from the Control Room in accordance with Procedure 2.2.99.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 2 of 8 Job Performance Measure for Operations Revision 02 Task No.: None
Title:
Placing SDG In Service From Control Room Directions to Trainee:
When I tell you to begin, you are to place the Supplemental Diesel Generator in service from the Control Room. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The Plant is Shutdown.
- 2. Critical 4160 Bus 1F is de-energized
- 3. Emergency Diesel Generator #1 is Inoperable and cannot be placed in service.
- 4. The Emergency Transformer is Unavailable.
General
References:
- 1. Procedure 2.2.99 Supplemental Diesel Generator System General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by bold steps.
- 3. Simulator cues denoted by "#".
Task Standards:
- 1. The operator starts the Supplemental Diesel Generator and ties it to Critical Bus 1F and re-energizes the bus per Procedure 2.2.99.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 3 of 8 Job Performance Measure for Operations Revision 02 Task No.: None
Title:
Placing SDG In Service From Control Room Initiating Cue(s):
The Control Room Supervisor directs you to place the Supplemental Diesel Generator in service from the Control Room in accordance with Procedure 2.2.99 Supplemental Diesel Generator System and supply Critical Bus 1F.
Notify the CRS when the SDG is running and has energized the Bus.
NOTE: Ensure the Simulator is in RUN and tell the trainee to begin.
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 4 of 8 Job Performance Measure for Operations Revision 02 Task No.: None
Title:
Placing SDG In Service From Control Room Start Time: ____________
Performance Checklist Standards Sat Unsat Obtained the current revision of Procedure 2.2.99
- 1. Obtain Procedure Supplemental Diesel Generator System. Selects Section 5.
- 2. Place the SDG 5.1 Placed the SUPPLEMENTAL DIESEL switch to Start GENERATOR control switch to START.
- 3. Close the SDG 5.2 Closed SDG OUTPUT BKR SG1 and check Output breaker that the switch is red flagged.
5.3.1 On Switchgear Display Screen, the
- 4. Open Breaker Operator transferred Bus 480S to the 480S(12.5)
SDG by Opening Breaker 480S (12.5).
5.3.2 On Switchgear Display Screen,
- 5. Close Breaker transferred Bus 480S to the SDG by 480S(4160S)
Closing Breaker 480S (4160S).
Note to Examiner: The student will transfer to Section 8 to energize the 4160F Bus.
Checked following Annunciators clear:
- 6. Checks 8.2.1 C-1/C-6, 4160V BUS 1F BKR 1FA annunciators in 8.2.2 C-1/C-7, 4160V BUS 1F BKR 1FS section 8 8.2.3 C-1/E-7, 4160V BUS 1F BKR 1FE LOCKOUTs.
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 5 of 8 Job Performance Measure for Operations Revision 02 Task No.: None
Title:
Placing SDG In Service From Control Room Performance Checklist Standards Sat Unsat 8.3 At Panel 9-3, placed the following switches to PULL-TO-LOCK:
- 7. Pulls to lock the
- RHR PUMP A.
pumps on 9-3.
- CS PUMP A.
- RHR PUMP B.
8.4 At Panel A, placed the following switches to
- 8. Pulls to lock the PULL-TO-LOCK:
pumps on Panel A
- SERVICE WATER PUMP A.
- SERVICE WATER PUMP C.
8.5 At Panel C, placed the following breaker switches to PULL-TO-LOCK:
- 9. Pulls to lock the
- BUS 1A TIE BKR 1FA.
pumps on Panel C
- EMERGENCY XFMR BKR 1FS.
- DIESEL GEN 1 BKR EG1.
- EMERGENCY XFMR BKR 1GS.
8.6.1 At SUPPLEMENTAL DIESEL GENERATOR
- 10. Places MODS PANEL placed the MODS POWER switch to Power to ON ON.
- 11. Places XFMR 8.6.2 Placed EMERGENCY XFMR MODS switch MODS switch to to OPEN.
Open
- 12. Places SDG MODS 8.6.3 Placed SDG MODS switch to CLOSE.
switch to Close
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 6 of 8 Job Performance Measure for Operations Revision 02 Task No.: None
Title:
Placing SDG In Service From Control Room Performance Checklist Standards Sat Unsat
- 13. Places MOD 8.6.4 Placed MODS POWER switch to OFF.
POWER to OFF 8.6.5 Closed BUS 1S TIE BKR 1SS and check
- 14. Close Breaker 1SS switch spring returns to NORMAL AFTER CLOSE (red flagged).
8.7 At Panel C; placed EMERGENCY XFMR BKR
- 15. Closes Emergency 1FS to CLOSE, then release and check XFRM BKR 1FS switch spring returns to NORMAL AFTER CLOSE (red flagged).
The Operator informed the CRS that the Supplemental Diesel Generator has been started
- 16. Notifies the CRS and is aligned to the bus.
- CUE: As the CRS, acknowledge the report.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 7 of 8 Job Performance Measure for Operations Revision 02 Task No.: None
Title:
Placing SDG In Service From Control Room ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC IC 1 (IC-240)
C. Run Batch File D. Change the simulator conditions as follows:
- 1. Triggers Number File Name Description
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial DG02A Diesel Generator #1Trip N/A 0 N/A 0 N/A Loss of Emergency ED06 N/A 0 N/A 0 N/A Transformer
- 3. Remotes Number Title Trigger TD Value Ramp 0 N/A
- 4. Overrides Instrument Tag Trigger TD Value Ramp None
- 5. Panel Setup Ensure Breaker 1FA is open.
Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.
Nebraska Public Power District SKL034-21-77(44532)
Cooper Nuclear Station Page 8 of 8 Job Performance Measure for Operations Revision 02 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to place the Supplemental Diesel Generator in service from the Control Room. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The Plant is Shutdown.
- 2. Critical 4160 Bus 1F is de-energized
- 3. Emergency Diesel Generator #1 is Inoperable and cannot be placed in service.
- 4. The Emergency Transformer is Unavailable.
Initiating Cue(s):
The Control Room Supervisor directs you to place the Supplemental Diesel Generator in service from the Control Room in accordance with Procedure 2.2.99 Supplemental Diesel Generator System and supply Critical Bus 1F.
Notify the CRS when the SDG is running and has energized the Bus.
Nebraska Public Power District SKL034-20-123 (33001)
Cooper Nuclear Station Page 1 of 8 Job Performance Measure for Operations Revision 02 Task No: 259042P0101 SHIFTING FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL (Alternate Path) #1 Trainee: Examiner:
Pass Fail Examiner Signature: Date:
THIS IS AN ALTERNATE PATH JPM Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 15 minutes
- 5. NRC K/A 259002 A4.06 (3.1/3.2)
Directions to Examiner:
Note: This JPM is an Alternate Path JPM. This JPM requires restoring 3 steam flow signals to RVLC.
- 1. This JPM evaluates the trainee's ability to SHIFT FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL in accordance with Procedure 4.4.1, Reactor Level Control System. (Alternate Path)
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes comments section below.
- 5. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-20-123 (33001)
Cooper Nuclear Station Page 2 of 8 Job Performance Measure for Operations Revision 02 Task No: 259042P0101 SHIFTING FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL (Alternate Path) #1 Directions to Trainee:
When I tell you to begin, you are to SHIFT FROM SINGLE ELEMENT TO AUTO (3 ELEMENT)
CONTROL on the RVLC System. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
If being simulated In-Plant or Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The plant is stable at 100% Power.
- 2. Single Element Control due to RVLC Maintenance that is complete.
General
References:
- 1. Procedure 4.4.1 Reactor Vessel Level Control System, Rev. 06 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by BOLD text.
- 3. Simulator cues denoted by "#".
- 4. Alternate path denoted by.
Task Standards:
- 1. The operator shifts Reactor Water Level Control from one element to three element control per procedure 4.4.1, Reactor Water Level Control System.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
The CRS Orders you to SHIFT RVLC FROM SINGLE ELEMENT TO AUTO (3 ELEMENT)
Nebraska Public Power District SKL034-20-123 (33001)
Cooper Nuclear Station Page 3 of 8 Job Performance Measure for Operations Revision 02 Task No: 259042P0101 SHIFTING FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL (Alternate Path) #1 CONTROL per procedure 4.4.1, Reactor Vessel Level Control System.
Notify the CRS when Reactor Water Level Control is in three element control.
NOTE: Ensure the Simulator is in RUN and tell the trainee to begin.
Nebraska Public Power District SKL034-20-123 (33001)
Cooper Nuclear Station Page 4 of 8 Job Performance Measure for Operations Revision 02 Task No: 259042P0101 SHIFTING FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL (Alternate Path) #1 Start Time: ____________
Performance Checklist Standards SAT UNSAT 12.1 At RVLC/RFPT HMI, selected RVLC system.
- 1. Select RVLC system
- CUE: RVLC Selected 12.2 Select CONTROL screen and verify on Master Controller that the PERMISSIVE ball is yellow.
- 2. Select CONTROL screen #CUE: The PERMISSIVE ball is NOT yellow.
12.3 If PERMISSIVE ball is not YELLOW, ensured the following conditions are met:
12.3.1 Master Level Controller is in AUTO.
12.3.2 Wide range FW flow transmitter is valid when associated RFP is in AUTO.
12.3.3 At least two steam flow elements are valid.
12.3.4 Turbine 1st stage flow is valid if less
- 3. Check Conditions than four steam flow elements are valid 12.3.5 At least one individual RFP controller is in AUTO 12.3.6 Total steam flow greater than 1 Mlbm.
12.3.7 At least one Reactor Vessel Level indicator is valid.
- CUE: Three steam flow elements are invalid
- 4. Contact System 12.4 If PERMISSIVE ball is still not YELLOW, Engineer or CRS contacted System Engineer.
Nebraska Public Power District SKL034-20-123 (33001)
Cooper Nuclear Station Page 5 of 8 Job Performance Measure for Operations Revision 02 Task No: 259042P0101 SHIFTING FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL (Alternate Path) #1 Performance Checklist Standards SAT UNSAT
- CUE: System Engineer says to restore all Bypassed Steam flows.
Referred to section 9 Restoring RVLC Input To
- 5. Restoring Input Service 9.1 At a RVLC/RFPT HMI, selected RVLC system
- 6. Select RVLC system
- CUE: RVLC system selected 9.2 Selected MIMIC screen and verified affected parameters are ready to be returned to service
- 7. Select MIMIC screen
- CUE: All four Steam flows are reading ~ the same 9.3 Selected MAINT screen
- 8. Select MAINT Screen #CUE: MAINT screen selected.
9.4 On MAINT. screen, selected desired parameter
- 9. Select Steam Flow parameter. #CUE: One Steam flow selected 9.5 On pop-up menu, pressed RESET button
- 10. Press RESET button. #CUE: Reset button depressed 9.6 Verified steam flow parameter tile turned green.
- 11. Verify affected parameter tile green #CUE: Selected steam flow parameter turned GREEN.
Repeats Steps 9 and 10 for the other 2 Steam
- 12. Repeat Steps 8 and 9 Flows
Nebraska Public Power District SKL034-20-123 (33001)
Cooper Nuclear Station Page 6 of 8 Job Performance Measure for Operations Revision 02 Task No: 259042P0101 SHIFTING FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL (Alternate Path) #1 Performance Checklist Standards SAT UNSAT for the other 2 Steam Flows #CUE: The Other two Steam flows are reset
- 13. Returns to section 12 of Returned to section 12.5 of procedure to complete procedure actions.
12.5 Placed RFC-SW-S2, 1 OR AUTO ELEMENT LEVEL CONTROL SWITCH is in "1" position
- 14. Check RFC-SW-S2 (Panel 9-5).
Position
- CUE: In 1 position 12.6 Placed RFC-SW-S2, 1 OR AUTO ELEMENT LEVEL CONTROL SWITCH to AUTO position.
- 15. Place RFC-SW-S2 in Auto. #CUE: In Auto Position 12.7 At CONTROL screen, verified THREE ELEMENT ball is yellow
- 16. Check Control Screen
- CUE: THREE ELEMENT ball is yellow Informed CRS The RVLC system is in AUTO (3
- 17. Informs CRS ELEMENT) CONTROL.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-20-123 (33001)
Cooper Nuclear Station Page 7 of 8 Job Performance Measure for Operations Revision 02 Task No: 259042P0101 SHIFTING FROM SINGLE ELEMENT TO AUTO (3 ELEMENT) CONTROL (Alternate Path) #1 ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC IC-234 C. Run Batch File None D. Change the simulator Number Title TRG TD Sev Ramp Initial conditions as follows:
- 1. Triggers None
- 2. Malfunctions None N/A N/A N/A N/A N/A N/A N/A N/A
- 3. Remotes None N/A N/A
- 4. Overrides None N/A N/A Place simulator in Run and Bypass 3 of 4 Steam Flows from the
- 5. Panel Setup Maintenance Screen Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.
Nebraska Public Power District SKL034-20-123(33001)
Cooper Nuclear Station Page 8 of 8 Job Performance Measure for Operations Revision 01 Task No.: 259042P0101 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to SHIFT FROM SINGLE ELEMENT TO AUTO (3 ELEMENT)
CONTROL on the RVLC System. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
If being simulated In-Plant or Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The plant is stable at 100% Power.
- 2. Single Element Control due to RVLC Maintenance that is complete.
Initiating Cue(s):
The CRS Orders you to SHIFT RVLC FROM SINGLE ELEMENT TO AUTO (3 ELEMENT)
CONTROL per procedure 4.4.1, Reactor Vessel Level Control System.
Notify the CRS when Reactor Water Level Control is in three element control.
Nebraska Public Power District SKL034-20-116 (29983)
Cooper Nuclear Station Page 1 of 7 Job Performance Measure for Operations Revision 00 Task No. 200182A0501:
Recover From Manual Scoop Tube Operations Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 10 minutes
- 5. NRC K/A A.0 Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to recover from manual scoop tube operations in accordance with 2.2.68.1, Reactor Recirculation System.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-20-116 (29983)
Cooper Nuclear Station Page 2 of 7 Job Performance Measure for Operations Revision 00 Task No. 200182A0501:
Recover From Manual Scoop Tube Operations Directions to Trainee:
When I tell you to begin, you are to RESET the SCOOP TUBE LOCKOUT in accordance with 2.2.68.1, Reactor Recirculation System Operations from the Control Room. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The plant is operating at 100% power.
- 2. The A Reactor Recirc Pump had been being controlled locally
- 3. All repairs are completed and the Scoop Tube is available.
General
References:
- 1. Procedure 2.2.68.1, Rev. 74, Reactor Recirculation System Operations General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by BOLD text.
- 3. Simulator cues denoted by "#".
Nebraska Public Power District SKL034-20-116 (29983)
Cooper Nuclear Station Page 3 of 7 Job Performance Measure for Operations Revision 00 Task No. 200182A0501:
Recover From Manual Scoop Tube Operations Task Standards:
- 1. The operator resets the SCOOP TUBE LOCKOUT in accordance with 2.2.68.1, Reactor Recirculation System Operations from the control room per procedure.
- 2. 100% of critical elements successfully completed without error.
- 2. 100% of safety and radiological work practices.
Initiating Cue(s):
The Control Room Supervisor directs you to recover from manual scoop tube operations on the A Reactor Recirc Pump controller and match it to within 5 % of the speed of the B Reactor Recirculation Pump. Inform the CRS when the MG Set control has been restored and matched to the B Reactor Recirculation Pump.
Nebraska Public Power District SKL034-20-116 (29983)
Cooper Nuclear Station Page 4 of 7 Job Performance Measure for Operations Revision 00 Task No. 200182A0501:
Recover From Manual Scoop Tube Operations Performance Checklist Standards SAT UNSAT
- 1. Obtain procedure The Operator obtained a copy of 2.2.68.1 Section 17. procedure 2.2.68.1 Section 17.
16.1 The Operator selected Parameter
- 2. Ensures S is S on RRFC-SIC-16A.
selected.
- Cue: S is displayed in the window.
16.2 The Operator adjusted RRFC-SIC-16A manual control knob (Parameter
- 3. Adjust S to make S S), as necessary, until S and L and L lights are off. lights are off. ______
- Cue: Both S and L lights are off.
16.3 The Operator verified that Parameter V and P are within 2.0 of each other, by
- 4. Verify Parameter V selecting each parameter one at a time.
value is within 2.0 of Parameter P.
- Cue: The values are within 2.0 of each other.
16.4 The Operator pressed RRMG Set A
Lock Reset.
- Cue: The lockout light and alarms clear.
16.5 The Operator rotated the manual control knob counterclockwise and lowers
- 6. Adjusts speed to within speed on the A RR Pump.
5% of A RR Pmp. ______ ______
- Cue: Speed is lowering, and is down within 5% of B RR Pmp.
Nebraska Public Power District SKL034-20-116 (29983)
Cooper Nuclear Station Page 5 of 7 Job Performance Measure for Operations Revision 00 Task No. 200182A0501:
Recover From Manual Scoop Tube Operations Performance Checklist Standards SAT UNSAT The Operator notified the CRS that the B RR Pump Scoop Tube Lockout has been reset and matched A and B
- 7. Notifies the CRS.
Recirculation Pump Speeds. ______ ______
Cue: Respond as the CRS.
Nebraska Public Power District SKL034-20-116 (29983)
Cooper Nuclear Station Page 6 of 7 Job Performance Measure for Operations Revision 00 Task No. 200182A0501:
Recover From Manual Scoop Tube Operations ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC IC-234 C. Run Batch File None D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:
- 1. Triggers None Recirc Pump A
- 2. Malfunctions RR17A 1 0 78 0 84 Runback N/A N/A
- 3. Remotes None N/A N/A
- 4. Overrides None N/A N/A
- a. Place the simulator to RUN.
- 5. Panel Setup
- d. Rotate the controller for the RR Pump a few rotations to ensure a mismatch between parameters.
Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.
Nebraska Public Power District SKL034-20-116 (29983)
Cooper Nuclear Station Page 7 of 7 Job Performance Measure for Operations Revision 00 Task No.: 200182A0501 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to RESET the SCOOP TUBE LOCKOUT in accordance with 2.2.68.1, Reactor Recirculation System Operations from the Control Room. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The plant is operating at 100% power.
- 2. The A Reactor Recirc Pump had been being controlled locally
- 3. All repairs are completed and the Scoop Tube is available.
The Control Room Supervisor directs you to recover from manual scoop tube operations on the A Reactor Recirc Pump controller and match it to within 5 % of the speed of the B Reactor Recirculation Pump. Inform the CRS when the MG Set control has been restored and matched to the B Reactor Recirculation Pump.
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 1 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A FerTrainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 20 minutes
- 5. NRC K/A 212000 A1.11 (3.4 / 3.3) and 212000.A2.02 (3.7/3.9)
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to Transfer RPSPP1B from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 2 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Directions to Trainee:
When I tell you to begin, you are to Transfer RPSPP1B from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The Plant is operating at 100% steady state power.
- 3. RWCU has been removed from service General
References:
- 1. Procedure 2.2.22, Vital Instrument Power System, Rev. 70 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by bold steps.
- 3. Simulator cues denoted by "#".
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 3 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Task Standards:
- 1. The operator is to Transfer RPSPP1B from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
The Control Room Supervisor directs you to Transfer RPSPP1B from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System.
Notify the CRS when RPSPP1B has been transferred from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System NOTE: Ensure the Simulator is in RUN and tell the trainee to begin.
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 4 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Start Time: ____________
Performance Checklist Standards Sat Unsat The Operator obtained the current revision of
- 1. Obtain Procedure. Procedure 2.2.22, Vital Instrument Power System.
Selected Section 7.
7.6 Operator determined that step 7.6 is the
- 2. Determines the task beginning step for this task.
begins at step 7.6.
7.6.1 At Panel 9-16 (Control Room), checked white ALT SOURCE AVAIL light above RPS BUS
- 3. Determine alt power B POWER TRANSFER switch is on source is available.
CUE: The white light is on.
- 4. Ensure step 7.3 is 7.6.1 Operator determined that this step is not N/A. applicable due to white light being lit.
7.6.2 In Panel 9-42 (Auxiliary Relay Room), for
- 5. Verify MSIV DC each open MSIV, checked MSIV DC solenoid Solenoids are ammeters are in green band.
energized.
- CUE: All solenoids are in green band.
Operator determined that this step is not applicable due to RWCU being removed from
- 6. Step 7.6.3 is N/A. service. (initial conditions)
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 5 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Performance Checklist Standards Sat Unsat
- 7. Secure Rx. Bldg. 7.6.4 Operator Obtained procedure 2.2.47 to secure Ventilation. Reactor Building Ventilation.
- 8. Determines Operator selected Section 9 of 2.2.47 to remove appropriate section Reactor Building Ventilation from service.
of 2.2.47 to perform.
- 9. N/A steps not 9.1 Operator determined Steps 9.1, 9.2, are not required. required due to RWCU being removed from service.
9.3 Operator notified the RP Dept. that ventilation was being secured.
- 10. Notify RP Dept.
CUE: RP acknowledges Rx Bldg. Ventilation is being secured and will perform necessary controls.
9.4 Operator notified the Safety Dept. that ventilation was being secured.
- 11. Notify Safety Dept.
CUE: Safety representative acknowledges Rx Bldg.
Ventilation is being secured and will perform necessary monitoring and controls.
9.5 - 9.7 Operator dispatched an operator to secure local Hood Exhaust Fans HF-R-1A, HF-R-1B, and
- 12. Secure Exhaust HF-R-1C.
Fume Hoods.
CUE: Operator has been dispatched and secured the local Hood Exhaust Fans.
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 6 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Performance Checklist Standards Sat Unsat 9.8 Operator Secured one Reactor Building Exhaust Fan by the following:
9.8.1. Ensure controller in MANUAL and controller in AUTOMATIC 9.8.2. Established communications and FCV room.
9.8.3. Placed control switch to RUN for Supply fan selected to AUTO 9.8.4. Placed control switch to RUN for SUPPLY FAN EF-R-1A 9.8.5. Placed control switch to RUN for SUPPLY
- 13. Secure One Rx. FAN EF-R-1B Building Exhaust 9.8.6. Placed control switch to RUN for EXH Fan. BSTR FAN selected to AUTO.
9.8.7. Adjusted controller in AUTOMATIC to -0.4 and allow pressure to stabilize.
9.8.8. Adjusted HV-FCV-1013 flowrate to 30K -
50K, with output of 10 - 80%, maintaining 0.30 to -0.33 wg.
9.8.9 When controller reaches 10%, Stopped selected EXHAUST FAN by placing control switch to OFF.
CUE: Exhaust Fan secured.
9.8.10 Operator placed the control switch for the
- 14. Place non-running non-running EXHAUST FAN to STBY.
fan to standby.
CUE: Non-running Exhaust Fan in STBY.
9.8.11 Operator adjusted setpoint of controller in AUTOMATIC to -.30 to -0.43 wg and
- 15. Adjust setpoint. allows building pressure to stabilize.
CUE: Building pressure has stabilized.
9.8.12 Operator ensured Reactor Building Pressure
- 16. Ensure Building is being maintained at -.30 to -0.43 wg.
pressure is maintained. CUE: Building pressure is -0.35" wg.
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 7 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Performance Checklist Standards Sat Unsat 9.8.13 Ensured output signal (V value) for
- 17. Ensures controller controller selected to MANUAL matches output of Man / Auto setpoints controller in AUTOMATIC balanced.
CUE: Output signals match.
9.8.14 Placed control switch for running SUPPLY
- 18. Supply Fan to FAN to AUTO.
AUTO.
CUE: Control switch is in AUTO.
9.8.15 Placed control switch for running EXHAUST
- 19. Exhaust Fan to FAN to AUTO.
AUTO.
CUE: Control switch is in AUTO.
9.8.16 Placed control switch for running EXH
- 20. Exhaust Booster BSTR FAN to AUTO Fan to Auto.
CUE: Control switch is in AUTO.
- 21. Start SGTS per 9.9 Start SGT System per Procedure 2.2.73 to maintain Reactor Building pressure negative.
procedure 2.2.73.
6.1 At VBD-R, placed SGT-DPIC-546, RX BLDG/SGT DP, in AUTO with setpoint adjusted to
- 23. Select control maintain -0.25" wg.
setting.
CUE: SGT-DPIC-546 is in AUTO and setpoint is adjusted.
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 8 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Performance Checklist Standards Sat Unsat 6.2 At VBD-K, placed SGT in service:
6.2.1 SGT A
- a. Started EF-R-1E, SGT A EXHAUST FAN
- b. Check SGT-AO-249, SGT A INLET, opens
- a. Started EF-R-1F, SGT B EXHAUST FAN
- b. Check SGT-AO-250, SGT A INLET, opens
- 24. Places SGT train in
- c. Check SGT-AO-252, SGT A DISCHARGE, service.
opens Adjusted SGT-DPIC-546, RX BLDG/SGT DP, as necessary, to obtain 800 scfm on SGT-FI-545, SGT DISCHARGE HEADER FLOW and maintained at
-0.25" wg.
CUE: Flow is 800 scfm and Reactor Building pressure is -0.25" wg.
9.10 Placed control switches for the following fans to OFF in order listed:
- a. EXHAUST FAN selected to STBY, EF-R-1A or EF-R-1B
- 25. Continue in 2.2.47 b. EXH BSTR FAN selected to STBY, BF-R-1A or to secure Rx. Bldg. BF-R-1B Ventilation. c. SUPPLY FAN selected to STBY, SF-R-1A-A or SF-R-1A-B CUE: Fans are OFF
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 9 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Performance Checklist Standards Sat Unsat 9.11Perform the following in rapid succession:
- a. Place control switch for operating EXH BSTR FAN to OFF
- b. B. Place control switch for operating SUPPLY FAN to OFF
- c. C. Place control switch for operating
- 26. Secure Rx Bldg EXHAUST FAN to OFF Fans.
- d. Close AO-257, HV-R-1A DISCH VLV
9.12 Closed the following Secondary Containment Isolation Valves:
- 27. Close Secondary a. MO-272, HV-R-1A DISCH VLV Containment b. MO-258, EXH FANS DISCH VLV Isolation Valves. c. MO-260, EXH FANS DISCH VLV CUE: Valves are CLOSED 9.13 Informed CRS that Reactor Building Kaman may be removed from service per Procedure
- 28. Inform CRS Reactor 4.15.4, if desired Kaman may be secured.
CUE: CRS acknowledges and replies that it will remain in service.
9.14 Operator recognized that unit will not be secured for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and informs CRS that step may be N/A.
- 29. Step 9.14 N/A.
CUE: CRS acknowledges and agrees that step is N/A.
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 10 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Performance Checklist Standards Sat Unsat 7.6.5.1 Operator notifies SM that RHR-MO-921 will be inoperable.
CUE: SM acknowledges RHR-MO-921 will be
- 30. Prevent AOG from INOP.
Isolating.
7.6.5.2 At Panel BB3, open breaker 7 for RHR-MO-921.
CUE: Another operator will open breaker 7 at BB3, and the action is complete.
7.6.6. Operator notified SM that Drywell Vent Monitor and Reactor water conductivity monitoring
- 31. Notify SM of will be INOP due to group isolations.
systems INOP due to group isolations. CUE: SM acknowledges Drywell Vent Monitor and Rx. Water conductivity monitoring are INOP.
7.6.7 Operator determined that this step is not applicable due to RWCU being removed from
- 32. Step 7.6.7 is N/A. service. (initial conditions)
- CUE: RWCU has been removed from service.
7.6.8 Operator requested another operator be stationed at the RPS MG Set B Room, to perform
- 33. Station Operator at step 7.6.9.3.
CUE: Another operator is stationed at the RPS MG Set B Room.
7.6.9 At panel 9-16, Operator placed RPS BUS B POWER TRANSFER switch to ALT FEED, and verified:
7.6.9.1 Checked Red ALT SOURCE ON light is on.
7.9.6.2 Checked Red GEN B ON light is off 7.6.9.3 Checked with operator at RPS MG SET
- 34. Transfer power to ROOM B that Red LOAD CONNECTED TO alternate source.
EMERGENCY light is on, and Red LOAD CONNECTED TO NORMAL light is off.
CUE: Red LOAD CONNECTED TO EMERGENCY light is on, and Red LOAD CONNECTED TO NORMAL light is off
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 11 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A Performance Checklist Standards Sat Unsat
- 35. Release Transfer Operator released RPS BUS B POWER Switch. TRANSFER switch.
The Operator informed the CRS that the RPSPP1B has been transferred from RPS MG Set B to CDP-1A in accordance with Procedure
- 36. Notifies the CRS.
2.2.22, Vital Instrument Power System.
- CUE: Respond as CRS.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 12 of 13 Job Performance Measure for Operations Revision 00 Task No.: 262072P0101
Title:
Transfer RPSPP1B from RPS MG Set B to CDP-1A ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC IC 234 C. Run Batch File D. Change the simulator conditions as follows:
- 1. Triggers Number File Name Description
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial None N/A 0 N/A 0 N/A
- 3. Remotes Number Title Trigger TD Value Ramp None 0 N/A
- 4. Overrides Instrument Tag Trigger TD Value Ramp None
- 1. Place simulator in RUN.
- 5. Panel Setup 2. Remove RWCU from service Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.
Nebraska Public Power District SKL034-21-145(57055)
Cooper Nuclear Station Page 13 of 13 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to Transfer RPSPP1B from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The Plant is operating at 100% steady state power.
- 3. RWCU has been removed from service Initiating Cue(s):
The Control Room Supervisor directs you to Transfer RPSPP1B from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System.
Notify the CRS when RPSPP1B has been transferred from RPS MG Set B to CDP-1A in accordance with Procedure 2.2.22, Vital Instrument Power System.
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 1 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
ALTERNATE PATH Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 20 minutes
- 5. NRC K/A 204000 A4.03 (3.2 / 316) and 204000 A1.04 (2.8/2.8)
Directions to Examiner:
Note: This JPM is an Alternate Path JPM. The valve will not operate when aligning blowdown to the condenser and blowdown to Radwaste must be used.
- 1. This JPM evaluates the trainee's ability to perform RPV Depressurization with RWCU from the Control Room in accordance with Procedure 5.8.2.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 2 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Directions to Trainee:
When I tell you to begin, you are to perform RPV Depressurization with RWCU from the Control Room in accordance with Procedure 5.8.2. RPV Depressurization Systems (Table 2) from the Control Room. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The Plant has scrammed.
- 2. EOPs have been entered.
- 3. Reactor Depressurization is required per the EOPs.
General
References:
Procedure RPV Depressurization with RWCU from the Control Room in accordance with Procedure 5.8.2., RPV Depressurization Systems (Table 2).
General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by bold text.
- 3. Simulator cues denoted by "#".
- 4. Alternate path denoted by.
Task Standards:
- 1. The operator performs RPV depressurization with RWCU by attempting to blow down to the main condenser and transition to blowing down to Radwaste in accordance with
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 3 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Procedure 5.8.2., RPV Depressurization Systems (Table 2) from the control room.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
The Control Room Supervisor directs you to depressurize the RPV with RWCU from the control room in accordance with procedure 5.8.2, RPV Depressurization Systems (Table 2). Preferred discharge path is to the Main Condenser.
Notify the CRS when you are depressurizing the RPV with RWCU.
NOTE: Ensure the Simulator is in RUN and tell the trainee to begin.
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 4 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Start Time: ____________
Performance Checklist Standards Sat Unsat The Operator obtained the current revision of
- 1. Obtain Procedure Procedure 5.8.2, RPV Depressurization Systems.
Selected Section 15.
15.1 Operator referred to Section 3 for
- 2. Refer to Section 3 dispatching personnel when actions outside for dispatching the Control are required.
personnel 15.2 Operator determined that Step 15.2 can be N/Ad since it is not required by plant conditions.
- 3. N/A Steps CUE: If Operator chooses to install PTMs, respond that another operator will install the PTMs and they are complete.
15.3 Operator verified Group 3 Isolation was present per procedure 2.1.22. (Hard Card)
CUE: Group 3 Channel A and B lights are out on Panel 9-5.
RWCU-MO-18, OUTBD ISOL VLV indicates CLOSED on Panel 9-4.
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 5 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Performance Checklist Standards Sat Unsat 15.3.1-3 Operator reset Group 3 Isolation signal by
- a. turning GROUP ISOL RESET CHANNEL A and CHANNEL B, switches to the right RESET position and then releasing to NOR at panel 9-5.
- c. Opened RWCU-MO-18, OTBD ISOL
Isolation Signal CUE: Group 3 Channel A and B lights are ON at Panel 9-5.
RWCU-MO-15, INBD ISOL VLV, indicates OPEN at panel 9-4.
RWCU-MO-18, OTBD ISOL VLV, indicates OPEN at panel 9-4.
15.4 Placed running RWCU PUMP switch to STOP, if running.
15.5 Closed RWCU-MO-68, RETURN LINE TO
- 7. Closes return to RX VLV.
RPV CUE: RWCU-MO-68 is CLOSED.
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 6 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Performance Checklist Standards Sat Unsat 15.6 Verified RWCU F/Ds are in hold by having operator at local F/D panel 12-4-98A/B place
- 8. Verify RWCU F/Ds the F/D in Hold.
in Hold A or B or both #CUE As local operator acknowledge the divisions?? Is it on direction to place F/Ds in Hold until the the setup page if action is complete.If asked, steps 15.6.1.1 preferred train? thru 15.6.1.4 are complete (A division).
What about B division steps 15.6.2.1 thru 15.6.2.4?
15.7 Operator ensured the following:
- a. RWCU-RMC-143, BD VLV 55 FLOW CONTROL, was adjusted to zero.
- b. RWCU-MO-74, DEMIN SUCTION BYPASS VLV, was open.
- c. RWCU-MO-53, BLOWDOWN ORIFICE BYPASS VLV was open.
- 9. Verify Flowpath CUE:
- a. RWCU-RMC-143, BD VLV 55 FLOW CONTROL, is set to zero.
- b. RWCU-MO-74, DEMIN SUCTION BYPASS VLV, is open.
- c. RWCU-MO-53, BLOWDOWN ORIFICE BYPASS VLV is open.
15.8 Operator aligned blowdown to the Main
- 10. Align Blowdown Condenser by opening RWCU-MO-56.
Flowpath to Main Condenser CUE: RWCU-MO-56 will NOT OPEN.
Note to Examiner: Operator may choose to continue and redirect blowdown to Radwaste without CRS approval but will inform CRS afterward.
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 7 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Performance Checklist Standards Sat Unsat Operator reports failure of MO-56 to open to the CRS.
CUE: CRS acknowledges.
- CUE: If asked what to do, the examiner should
- 11. Report failure of ask the applicant what he/she recommends. The MO-56 to open.
operator should recommend to blowdown to Radwaste. If the applicant doesnt have a recommendation, the examiner should role play as the CRS and inform the applicant that we need to blowdown.
15.8 Operator aligns blowdown to Radwaste
- 12. Align Blowdown by opening RWCU-MO-57.
Flowpath to Radwaste CUE: RWCU-MO-57 is OPEN.
15.9 Placed and held RWCU Pump A(B) switch to START at panel 9-4.
15.12 Throttled RWCU-FCV-55, BLOWDOWN FLOW CONTROL VLV, using RWCU-RMC-143, BD VLV 55 FLOW CONTROL to achieve desired cooldown rate and did not exceed 70 GPM, and maintain
>200 psig above RPV pressure by throttling RWCU-MO-68, RETURN LINE
- 14. Set Blow down TO RX VLV.
Flow rate CUE: Pressure on RWCU-PI-131 indicates approximately 220 psi above reactor pressure.
Blowdown flow is less than70 gpm.
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 8 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
Performance Checklist Standards Sat Unsat 15.13 Inform CRS that RWCU is being utilized to
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 9 of 10 Job Performance Measure for Operations Revision 00 Task No.: 200185A0501
Title:
RPV Depressurization with RWCU (Alternate Path)
ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC IC-235 C. Run Batch File None D. Change the simulator conditions as follows:
- 1. Triggers Number File Name Description
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial None N/A 0 N/A 0 N/A N/A 0 N/A 0 N/A
- 3. Remotes Number Title Trigger TD Value Ramp CU16 PTM 44 &45 N/A 0 N/A
- 4. Overrides Override RWCU-MO-56 in the CLOSED position.
Instrument Tag Trigger TD Value Ramp None
- 5. Panel Setup 1. Ensure the simulator is in RUN and PTMs are active.
Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.
ATTACHMENT 2
Nebraska Public Power District SKL034-21-146 (57056)
Cooper Nuclear Station Page 10 of 10 Job Performance Measure for Operations Revision 00 Directions to Trainee:
When I tell you to begin, you are to perform RPV Depressurization with RWCU from the Control Room in accordance with Procedure 5.8.2., RPV Depressurization Systems (Table 2) from the Control Room. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The Plant has scrammed.
- 2. EOPs have been entered.
- 3. Reactor Depressurization is required per the EOPs.
Initiating Cue(s):
The Control Room Supervisor directs you to depressurize the RPV with RWCU from the control room in accordance with procedure 5.8.2, RPV Depressurization Systems (Table 2). Preferred discharge path is to the Main Condenser.
Notify the CRS when you are depressurizing the RPV with RWCU.
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 1 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
START HPCI FROM THE ASD ROOM Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Plant/SIM
- 3. Evaluation Method Simulate Perform
- 4. Performance Time: 15 minutes
- 5. NRC K/As: 295016 AK2.01 4.4/4.5 Directions to Examiner:
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes section below.
- 5. Give the trainee Attachment 2.
- 6. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes:
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 2 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
START HPCI FROM THE ASD ROOM Directions to Trainee:
When I tell you to begin, you are to start HPCI from the ASD room. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to start HPCI from the ASD room. During performance, state the actions you are taking, e.g.:
repositioning controls and observing instrumentation.
General Conditions:
- 1. 0% Reactor Power, Reactor Scrammed
- 2. Main turbine tripped.
- 3. Control Room is filled with toxic gas, non-fire source.
- 4. CSCS systems are all in standby status.
- 5. The RCIC system is INOPERABLE for a maintenance outage.
- 6. The Control Room has been evacuated.
General
References:
- 1. Emergency Procedure 5.1ASD.
General Tools and Equipment:
- 1. Key for ASD Room
- 2. Emergency Procedure 5.1ASD, Attachment 1 Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by "*".
- 3. Simulator cues denoted by "#".
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 3 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
START HPCI FROM THE ASD ROOM Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to perform control level and pressure with HPCI from the ASD room per Procedure 5.1ASD.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
You are the ASD Operator and the Shift Manager has directed you to start the HPCI System from the ASD Panel per 5.1ASD, Att.1. Steps 1 through 7 of Attachment 1 have been completed. The Shift Manager is in the TSC; inform him when HPCI is running and available to be lined up for injection.
Note: Place the simulator in RUN and tell the trainee to begin.
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 4 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
START HPCI FROM THE ASD ROOM Start Time: _____________
Performance Checklist Standard Sat Unsat 7.2 Observed 0 speed on HPCI-SI-2793,
- 1. Determine HPCI not running. TURBINE SPEED.
AOP MO-20 MO-24 MO-25 MO-21 MO-14 MO-19 FCU GSCB/P MO-58 MO-17 CUE: (As operated) each switch is in ISOLATE.
- 3. Ensure HPCI 14, 7.3.2 Ensured CLOSED the following valves:
19, 25, & 58 are CLOSED: HPCI-MO-14, STEAM TO TURBINE HPCI-MO-19, INJECTION HPCI-MO-25, MINIMUM FLOW BYPASS HPCI-MO-58, TORUS PUMP SUCTION CUE (As checked): GREEN light ON. RED light OFF.
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 5 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
START HPCI FROM THE ASD ROOM Performance Checklist Standard Sat Unsat
- 4. Ensure HPCI 17, 20, 7.3.3 Ensured OPEN the following valves:
24, and 21 are OPEN: HPCI-MO-17, ECST Pump Suction HPCI-MO-20, Pump Discharge HPCI-MO-24, ECST Test Line Shutoff HPCI-MO-21, Test Bypass to ECST CUE (As checked): RED light ON. GREEN light OFF.
FCU CUE: RED light ON. GREEN light OFF.
- 6. Place GSCB in 7.3.5 Placed GLAND SEAL CNDSR BLOWER AUTO control switch in AUTO.
CUE: Switch is in mid-position.
- 7. Place GSCCP in 7.3.6 Placed GLAND SEAL CNDSR COND AUTO PUMP control switch in AUTO.
CUE: Switch is in mid-position.
- 8. Set HPCI Flow 7.3.7 Set HPCI-FIC-1108, HPCI FLOW Controller and place CONTROLLER to 4250 gpm and placed in in MANUAL MANUAL.
CUE: The red line on the FIC is on 4250 gpm and tab is to the left.
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 6 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
START HPCI FROM THE ASD ROOM Performance Checklist Standard Sat Unsat
- 9. OPEN HPCI-MO-14, 7.3.8 Placed control switch for HPCI-MO-14 Steam to Turbine to OPEN.
CUE: RED light ON, GREEN light OFF.
- 10. Start the Auxiliary 7.3.9 Placed control switch for the auxiliary Oil Pump oil pump to START.
CUE: RED light ON, GREEN light OFF.
- 11. Ensure the Turbine 7.3.10 Ensured the speed of the HPCI pump is Speed is >2050 rpm >2050 RPM by adjusting Flow Controller HPCI-FIC-1108 OPEN and CLOSE pushbuttons.
CUE: Speed is 3500 RPM.
- 12. Inform the Shift Inform the Shift Manager the HPCI pump is Manager the task is running and available to be lined up for injection.
complete.
- CUE: The Shift Manager acknowledges the report.
Stop Time: _____________ Stop Time: _____________
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 7 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
START HPCI FROM THE ASD ROOM ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC-18 or LOR equivalent. (IC-237)
Batch File Name - JPM/342056.
C. Change the simulator conditions as follows:
- 1. Triggers - None
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial RC01 RCIC System Failure to N/A N/A N/A N/A N/A Auto Start RP02 Rx Scram N/A N/A N/A N/A N/A FW01a RFP A Trip N/A N/A N/A N/A N/A FW01b RFP B Trip N/A N/A N/A N/A N/A TC01 Main Turbine Trip N/A N/A N/A N/A N/A HP01 HPCI System Failure to N/A N/A N/A N/A N/A Start RP08a Spurious Group 1 Isol. N/A N/A N/A N/A N/A Signal Channel A-1 RP08c Spurious Group 1 Isol. N/A N/A N/A N/A N/A Signal Channel B-1
- 3. Remotes - None
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 8 of 9 Job Performance Measure for Operations Revision 10 Task No.: 206033P0201 Task
Title:
- 4. Overrides - None
- 5. Panel Setup
- a. Insert Batch File jpm/342056.
- b. Place Simulator in RUN.
- c. Trip all but one Condensate and Condensate booster pump.
- d. Place following HPCI Isolation switches to ISOL.
LEVEL INDICATORS HPCI CONTROL AND INDICATION MO-15 MO-16
- e. Place Simulator in FREEZE.
Note: If this JPM is to be performed more than once, snap the simulator into IC-0 after the Panel setup is complete.
Nebraska Public Power District SKL034-20-56 (2139)
Cooper Nuclear Station Page 9 of 9 Job Performance Measure for Operations Revision 10 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to start HPCI from the ASD room. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to start HPCI from the ASD room. During performance, state the actions you are taking, e.g.:
repositioning controls and observing instrumentation.
General Conditions:
- 1. 0% Reactor Power, Reactor Scrammed
- 2. Main turbine tripped.
- 3. Control Room is filled with toxic gas, non-fire source.
- 4. CSCS systems are all in standby status.
- 5. The RCIC system is INOPERABLE for a maintenance outage.
- 6. The Control Room has been evacuated.
Initiating Cue(s):
You are the ASD Operator and the Shift Manager has directed you to start the HPCI System from the ASD Panel per 5.1ASD, Att.1. Steps 1 through 7 of Attachment 1 have been completed. The Shift Manager is in the TSC; inform him when HPCI is running and available to be lined up for injection.
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 1 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
ALTERNATE PATH JPM Additional Program Information:
- 1. Appropriate Performance Locations: Simulator
- 2. Appropriate Trainee level: RO/SRO
- 3. Evaluation Method: Perform
- 4. Performance Time: 23 minutes
- 5. NRC K/A 219000 A4.01 (3.8/3.7)
Directions to Examiner:
NOTE: THIS IS AN ALTERNATE PATH JPM. The first RHR Pump will TRIP when it is started.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes section below.
- 5. Give the trainee Attachment 2.
- 6. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes:
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 2 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
Directions to Trainee:
When I tell you to begin, you are to startup the suppression pool cooling mode of RHR.
Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to startup the suppression pool cooling mode of RHR. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 2. The RHRSW system is in standby status per procedure 2.2.70.
- 4. Suppression Pool cooling is NOT required by the EOPs.
- 5. All procedure prerequisites have been met for placing RHR Loop A in suppression pool cooling.
- 6. The NLO has completed venting loop A (2.2.69.3 through Step 4.13).
- 7. ALARA has determined the suction drain flush is not required.
- 8. The RPs have been notified of the system start.
- 9. Another operator is to perform 2.2.69.3 Section 3.
General
References:
- 1. Procedure 2.2.69.3
- 2. Procedure 2.2.70 General Tools and Equipment:
- 1. Key 2235 Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical steps denoted in bold.
- 3. Simulator cues denoted by "#".
- 4. Alternate path denoted by.
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 3 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
Task Standards:
- 1. The operator begins placing RHR Loop A in SPC and after the pump trips, starts another pump and completes placing the loop into service per Procedure 2.2.69.3.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 4 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
Initiating Cue(s):
The Control Room Supervisor directs you to startup RHR Loop A in suppression pool cooling and establish maximum cooldown rate using the A RHR pump per procedure 2.2.69.3. The hard card is NOT to be used. Inform the CRS when the A loop of RHR is in suppression Pool Cooling at maximum cooldown rate.
NOTE: Place the Simulator in RUN and tell the trainee to begin.
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 5 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
Start Time _________
Performance Checklist Standards Sat Unsat
- 1. Obtained Procedure Obtained Procedure 2.2.70.
NOTE to Examiners: Candidate may place A or C SWBP in service.
5.1.1 Held SWBP A (C) switch to
- 2. Place SWBP in START until pump starts. (Panel service 9-3)
- 3. Check AMPS 5.1.2 Checked AMPS normal. (Panel 9-3)
- 5. Adjust flow. 5.1.4 Adjusted SW-SW-MO89A to maintain close to 4000gpm.
- 6. Check AMPS Ensured AMPS 136.
5.1.5 Ensured d/p on SW-DPI-359A 17.0 psid. (HX Room)
- 7. Check HX d/p.
- CUE: When contacted as NLO report SW-DPI-359A indicates 4 psid.
NOTE to Examiners: Tell candidate another operator will record HX d/p in narrative logs.
4.15 Informed SM LPCI Mode of RHR
- 8. Inform SM LPCI A Subsystem A is inoperable.
- CUE: SM acknowledges.
NOTE to Examiners: Steps 4.16 through 4.18 are N/A.
4.19 Obtained Key and opened
- 9. Open MO-39A RHR-MO-39A, SUPPR POOL COOLING/TORUS SPRAY VLV.
- 10. 4.20 Step is N/A.
4.21 Placed control switch for RHR
- 11. Start Pump A Pump A to START. (Panel 9-3)
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 6 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
Performance Checklist Standards Sat Unsat
- 12. Notices pump did Observe the RHR Pump A did not start.
not start.
Notify the CRS or SM that RHR Pump A did not start.
Refer to alarm cards 9-3-1/B-4, RHR Pump
- 14. Refer to Alarm A Trip and 9-3-1/C4, RHR Pump A Card.
Ovld/Ground.
4.21 Placed control switch for RHR Pump C to START. (Panel 9-3)
4.22 Placed control switch for RHR-MO-34A, SUPPR POOL
- 16. Throttle OPEN COOLING INBD THROTTLE VLV, RHR-MO-34A . to OPEN to obtain desired flow on RHR-FI-133A or RHR-FR-143.
- 17. Ensure RHR-MO-16A 4.23 Ensured RHR-MO-16A, LOOP A CLOSES. MIN Flow BYP VLV, CLOSES as flow increases >2500 gpm.
NOTE to Examiners: Candidate may perform ONE of following steps.
4.24.1Direct the Reactor Building NLO to CLOSE CM-296, LOOP A
- 18. CLOSE CM-296. INJECTION LINE PRESSURE MAINTENANCE SHUTOFF.
- CUE: The Station Operator reports CM-296 is CLOSED.
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 7 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
Performance Checklist Standards Sat Unsat
- 19. Maintain system 4.24.2Maintain RHR Subsystem A pressure >
pressure > Condensate Transfer Condensate Transfer System pressure.
System pressure .
4.25 Hold in the CLOSE position the
Informed CRS RHR Loop A is in Suppression Pool Cooling with maximum
- 21. Inform the CRS that cooldown rate established.
the task is Complete.
- CUE: The CRS acknowledges the report.
Stop Time __________ Total Time __________
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 8 of 9 Job Performance Measure for Operations Revision 09 Task No.: 219001O0101 Task
Title:
Startup the Suppression Pool Cooling Mode of RHR (Alternate Path)
ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in any IC with Torus Temperature below 95°F. (IC-234)
Batch File Name - none.
C. Change the simulator conditions as follows:
- 1. Triggers None
- 2. Malfunctions RH01A, RHR Pump A Trip None
- 3. Remotes None
- 4. Overrides None
- 5. Panel Setup
- a. Initialize the Simulator and place in FREEZE.
- b. Insert IMF RH01A.
- c. Place Simulator in RUN.
Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel is complete.
Nebraska Public Power District SKL034-20-24(34969)
Cooper Nuclear Station Page 9 of 9 Job Performance Measure for Operations Revision 09 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to startup the suppression pool cooling mode of RHR.
Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to startup the suppression pool cooling mode of RHR. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 2. The RHRSW system is in standby status per procedure 2.2.70.
- 4. Suppression Pool cooling is NOT required by the EOPs.
- 5. All procedure prerequisites have been met for placing RHR Loop A in suppression pool cooling.
- 6. The NLO has completed venting loop A (2.2.69.3 through Step 4.13).
- 7. ALARA has determined the suction drain flush is not required.
- 8. The RPs have been notified of the system start.
- 9. Another operator is to perform 2.2.69.3 Section 3.
Initiating Cues:
The Control Room Supervisor directs you to startup RHR Loop A in suppression pool cooling and establish maximum cooldown rate using RHR Pump A per procedure 2.2.69.3. The hard card is NOT to be used. Inform the CRS when RHR Loop A is in suppression Pool Cooling at maximum cooldown rate.
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 1 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 5 minutes
- 5. K/A 295018; AA1.03 (3.3/3.4), AK3.07 (3.1/3.2)
Directions to Examiner:
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes section below.
- 5. Give the trainee Attachment 2.
- 6. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes: ______________________________________________________________________
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 2 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops Directions to Trainee:
When I tell you to begin, you are to separate the REC Critical Loops. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. A large leak has developed in the REC system.
- 2. Emergency Procedure 5.2REC, Loss of REC, has been entered and actions taken up to separating the REC Critical Loops.
General
References:
- 1. Procedure 5.2REC
- 2. Procedure 2.2.65.1 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted in bold.
- 3. Simulator cues denoted by "#".
Task Standards:
- 1. Separates the REC critical loops per Procedure 5.2REC.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 3 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops Initiating Cue(s):
The Control Room Supervisor directs you to separate the REC Critical Loops per 5.2REC, using the NORTH Critical Loop. RMP-RM-351A, SW A EFFLUENT RAD MON, is operable.
Inform the CRS when you have separated the REC Critical Loops.
NOTE: Ensure the Simulator is in RUN and tell the trainee to begin. (Delete malfunction SW12B)
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 4 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops Start Time: ____________
Performance Checklist Standards Sat Unsat 1.1 Closed REC-MO-695, CRITICAL LOOP SUPPLY CROSSTIE.
- 1. Close REC-MO-695.
CUE: GREEN light ON, RED light OFF.
1.2 Closed REC-MO-694, CRITICAL LOOP SUPPLY CROSSTIE.
- 2. Close REC-MO-694.
CUE: GREEN light ON, RED light OFF.
1.3 Closed REC-MO-721, NON CRITICAL HEADER RETURN.
- 3. Close REC-MO-721.
CUE: GREEN light ON, RED light OFF.
1.4 Closed REC-MO-722, NON CRITICAL
- 4. Close REC-MO- HEADER RETURN.
722.
CUE: GREEN light ON, RED light OFF.
1.5 Directed NLO to ensure REC-19 is open.
REC HX B INLET (R-931-N REC Hx area).
- 5. Ensure REC-19 is open.
- CUE: As the NLO report REC-19 is open.
1.6 Directed NLO to ensure REC-21 is open.
REC HX A INLET (R-931-N REC Hx area).
- 6. Ensure REC-21 is open.
- CUE: As the NLO report REC-21 is open.
NOTE to Examiner: Booth operator must insert TRIGGER 2 to close the valves in next two steps.
1.7 Directed NLO to Close REC-18, REC HX A
- 7. Remove seal and INLET (R-931-N REC Hx area).
close REC-18.
- CUE: As NLO, report REC-18 is closed.
1.8 Directed NLO to Close REC-20, REC HX B
- 8. Remove seal and INLET (R-931-N REC Hx area).
close REC-20.
- CUE: As NLO, report REC-20 is closed.
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 5 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops Performance Checklist Standards Sat Unsat
- 9. Select a critical 1.9 Selects a critical subsystem to align. (North is subsystem. assumed).
1.10.1 Ensured REC-TCV-451A, REC HX A SW
- 10. Ensure REC-TCV- OUTLET TEMPERATURE CONTROL, 451A switch is in switch is in OPEN.
open.
CUE: Point to switch indicating it is pointing to OPEN.
1.10.2 Throttled open SW-MO-650 to obtain 400 to 1200 gpm flow on SW-FI-387A, REC HX A SW OUTLET.
- 11. Throttle open SW-MO-650.
CUE: Point indicating SW-FI-387A indicates 600 gpm.
1.10.3 Ensured REC-MO-712, HX A OUTLET
- 12. Ensure REC-MO- VLV, is closed.
712 is closed.
CUE: GREEN light On, RED light OFF.
1.10.4 Ensured REC-MO-711, NORTH CRITICAL LOOP SUPPLY is open.
- 13. Ensure REC-MO-711 is open. CUE: GREEN light OFF. RED light ON.
CUE: If asked as the NLO report no visible leaks exist on the system.
1.10.5 If REC Surge Tank is available, opened REC-MO-722.
- 14. Open REC-MO-722. CUE: IF student chooses to open REC-MO-722, the red light is ON and green light is OFF.
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 6 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops Performance Checklist Standards Sat Unsat 1.10.6 Started REC PUMP:
______ C
______D CUE: REC PUMP C (D) red light came ON.
Inform the CRS the REC Critical loops are
- 16. Inform CRS the task separated.
is complete.
- CUE: CRS acknowledges the report.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 7 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC Any power IC. (IC-235)
DO NOT LOAD BATCH FILE UNTIL DIRECTED BY SETUP!!
C. Run Batch File Jpm/342144 D. Change the simulator conditions as follows:
- 1. Triggers Number File Name Description None
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial SW12B REC HX 1B Tube Leak A N/A 60% N/A N/A Rp05 Group 2 isolation failure A N/A N/A N/A N/A RP14 CREFS Auto Initiation failure A N/A N/A N/A N/A RP15 Group 6 isolation failure A N/A N/A N/A N/A
- 3. Remotes Number Title Trigger TD Value Ramp SW02 REC HX1B Inlet Isol Vlv (REC-V-18) 2 N/A CLOSE N/A SW04 REC HXA Inlet Isol Vlv (REC-V-20) 2 N/A CLOSE N/A RR03 RRMG A DC Oil Pump STOP N/A RR04 RRMG B DC Oil Pump STOP N/A
- 4. Overrides Instrument Tag Trigger TD Value Ramp None
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 8 of 9 Job Performance Measure for Operations Revision 02 Task No.: 208028P0101
Title:
Separation of REC Critical Loops
- a. Place the Simulator in RUN.
- b. Insert batch file (JPM/342144).
- c. Run the simulator long enough for the surge tank level to drop.
- d. Perform actions of EP 5.2REC up to the point of splitting the REC Critical Loops (all REC pumps off). These actions include scramming the reactor, tripping the RR pumps, stopping the RRMG
- 5. Panel Setup oil pumps, and stopping the running CRD pump.
- e. DELETE SW11c and SW11d, REC pump C and D trips.
- f. FREEZE the simulator.
- g. When JPM begins and simulator is taken to RUN, DELETE the malfunction SW12b.
Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.
Nebraska Public Power District SKL034-21-44(6354)
Cooper Nuclear Station Page 9 of 9 Job Performance Measure for Operations Revision 02 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to separate the REC Critical Loops. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. A large leak has developed in the REC system.
- 2. Emergency Procedure 5.2REC, Loss of REC, has been entered and actions taken up to separating the REC Critical Loops.
Initiating Cue(s):
The Control Room Supervisor directs you to separate the REC Critical Loops per 5.2REC, using the NORTH Critical Loop. RMP-RM-351A, SW A EFFLUENT RAD MON, is operable.
Inform the CRS when you have separated the REC Critical Loops.
Nebraska Public Power District SKL034-10-94 (7415)
Cooper Nuclear Station Page 1 of 5 Job Performance Measure for Operations Revision 02 Task No.: 286005I0102 Task
Title:
Operate the Diesel Fire Pump Manually (Alternate Path)
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
THIS IS AN ALTERNATE PATH JPM Additional Program Information:
- 1. Appropriate Performance Locations: Plant
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 12 minutes
- 5. NRC K/A 286000 A4.06(3.4/3.4)
Directions to Examiner:
THIS IS AN ALTERNATE PATH JPM. The First Method Of Starting The Diesel Will Be Unsuccessful.
- 1. This JPM evaluates the trainee's ability operate the diesel fire pump manually.
- 2. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 3. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 4. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments:
Nebraska Public Power District SKL034-10-94 (7415)
Cooper Nuclear Station Page 2 of 5 Job Performance Measure for Operations Revision 02 Task No.: 286005I0102 Task
Title:
Operate the Diesel Fire Pump Manually (Alternate Path)
Directions to Trainee:
When I tell you to begin, you are to operate the diesel fire pump manually. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The plant has experienced a fire.
- 2. The "C" fire pump is out of service.
- 3. The electric fire pump is unable to maintain system pressure.
- 4. The Diesel Fire Pump has failed to auto start.
General
References:
- 1. Procedure 2.2.30 General Tools and Equipment:
- 1. Master key for building access Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by bold text.
- 2. Alternate path denoted by.
Task Standards:
- 1. The operator attempts to start the diesel fire pump normally but must start it by selecting emergency run and closing contactor A per Procedure 2.2.30.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
The Control Room Supervisor directs you to start the diesel fire pump at FP-PNL-F2 in the diesel fire house AND check engine parameters per procedure 2.2.30. Notify the CRS when the task is complete.
Nebraska Public Power District SKL034-10-94 (7415)
Cooper Nuclear Station Page 3 of 5 Job Performance Measure for Operations Revision 02 Task No.: 286005I0102 Task
Title:
Operate the Diesel Fire Pump Manually (Alternate Path)
Performance Checklist Standards Sat UNSAT
- 1. Check the engine oil level. 9.1 Checked the engine oil level is normal.
CUE: Engine oil level is at normal.
- 2. Check the engine cooling reservoir 9.2 Checked the engine cooling water reservoir is full.
NOTE: The reservoir is above the control panel. CUE: The water level is at the top of the reservoir.
- 3. Start Exhaust Fan 9.3 If room exhaust fans are not running (above small damper in Fire Pump D Room ceiling),
adjust Fire Pump D Room thermostat (west wall) to start fans.
CUE: Exhaust Fan is running.
9.4.1 At Panel FA, placed DIESEL FIRE PUMP
- 4. Start FP-P-D D switch to START.
CUE: Switch in Start Engine is not rolling.
- 5. Select Switch to 9.4.2.1 Placed selector switch to MANUAL 1 or Manual 1 MANUAL 2.
CUE: In Manual 1 position.
- 6. Press START button 9.4.2.2 Pressed START button.
CUE: Engine cranking is sluggish and noise in room remains low.
- 7. Select Switch to a. Placed selector switch to MANUAL 2 and Manual 2 and press pressed START button.
START button CUE: Engine cranking is sluggish and noise in room remains low.
- 7. Select Emergency Run 9.5.1 Rotated Governor Manual Lever counter-clockwise to EMERGENCY RUN (located on top of engine).
CUE: Lever in EMERGENCY RUN.
Nebraska Public Power District SKL034-10-94 (7415)
Cooper Nuclear Station Page 4 of 5 Job Performance Measure for Operations Revision 02 Task No.: 286005I0102 Task
Title:
Operate the Diesel Fire Pump Manually (Alternate Path)
- 8. Close CONTACTOR A 9.5.2 Pulled operating lever on either CONTACTOR A or CONTACTOR B (located on north side of engine below block heater) to start engine.
CUE: Sound of engine cranking briskly.
CUE: Sound of engine running.
CUE: Hand wheel is fully counter-clockwise.
CUE: Hand wheel is fully counter-clockwise.
- 11. Check flapper FP-FG-10. 9.5.3.3 Ensured flow flapper in FP-FG-10 (North side above diesel) is in horizontal position.
CUE: Flapper is in horizontal position.
- 12. Check Engine 9.6.1 Check: Circulation water temperature, Parameters. Lube Oil Pressure, Engine RPM.
CUE: Circulation water temperature 180°F Lube Oil Pressure is 45 psig Engine Speed is 1800 RPM
- 13. Contacts the Control The operator calls the Control Room and reports Room Operator. Diesel Fire Pump D: is running normal CUE: Respond as Control Room Operator.
Nebraska Public Power District SKL034-10-94 (7415)
Cooper Nuclear Station Page 5 of 5 Job Performance Measure for Operations Revision 02 Task No.: 286005I0102 ATTACHMENT 1 When I tell you to begin, you are to operate the diesel fire pump manually. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. The plant has experienced a fire.
- 2. The "C" fire pump is out of service.
- 3. The electric fire pump is unable to maintain system pressure.
- 4. The Diesel Fire Pump has failed to auto start.
- 5. The Diesel Fire Pump cannot be started at panel FA.
Initiating Cues:
The Control Room Supervisor directs you to start the diesel fire pump at FP-PNL-F2 in the diesel fire house AND check engine parameters per procedure 2.2.30. Notify the CRS when the task is complete.
Nebraska Public Power District SKL034-40-14 Cooper Nuclear Station Page 1 of 7 Job Performance Measure for Operations Revision: 2 Task No.: 263030P0104 PLACE 24 VDC BATTERIES AND ASSOCIATED CHARGERS IN SERVICE Trainee: Examiner:
Pass: Fail: Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Plant
- 3. Evaluation Method: Perform Simulate
- 4. Performance Time: 15 minutes
- 5. Importance Factor: 2.75
- 6. NRC K/A: 263000 SG9(3.4/3.5)
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to place 24 VDC batteries and associated chargers in service in accordance with Procedure 2.2.26, 24 VDC Electrical System.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-40-14 Cooper Nuclear Station Page 2 of 7 Job Performance Measure for Operations Revision: 2 Task No.: 263030P0104 PLACE 24 VDC BATTERIES AND ASSOCIATED CHARGERS IN SERVICE Directions to Trainee:
When I tell you to begin, you are to place 24 VDC batteries and associated chargers in service in accordance with Procedure 2.2.26, 24 VDC Electrical System. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. A refuel outage is in progress.
- 2. 1A1 and 1A2 24 VDC batteries have been replaced.
General
References:
- 1. Procedure 2.2.26, 24 VDC Electrical System General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by bold steps.
- 2. Simulator cues denoted by "#".
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to place 24 VDC batteries and associated chargers in service per Procedure 2.2.26.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Nebraska Public Power District SKL034-40-14 Cooper Nuclear Station Page 3 of 7 Job Performance Measure for Operations Revision: 2 Task No.: 263030P0104 PLACE 24 VDC BATTERIES AND ASSOCIATED CHARGERS IN SERVICE Initiating Cue(s):
The BOP operator has directed you to return the 1A1 and 1A2 battery chargers and associated 24 VDC batteries to service in accordance with Procedure 2.2.26, 24 VDC Electrical System. .
All prerequisites have been completed or verified.
Notify the Control Room Supervisor when the 1A1 and 1A2 battery chargers and 24 VDC batteries have been returned to service.
NOTE: Tell the trainee to begin.
Nebraska Public Power District SKL034-40-14 Cooper Nuclear Station Page 4 of 7 Job Performance Measure for Operations Revision: 2 Task No.: 263030P0104 PLACE 24 VDC BATTERIES AND ASSOCIATED CHARGERS IN SERVICE Start Time: _________________
Performance Checklist Standards Sat Unsat
- 1. Obtain the procedure The operator obtained 2.2.26 at section 6, Placing 24V Batteries 1A1 and 1A2 in service.
- 2. Verify the 24 VDC 6.1 Verified the batteries 1A1 and 1A2 free Batteries 1A1 and 1A2 of foreign materials.
are free of foreign materials. #CUE: No foreign materials present.
- 3. CLOSE the 24 VDC 6.2 CLOSED the 24 VDC BATTERY A1/A2 BATTERY A1/A2 DISCONNECT switch.
DISCONNECT switch.
- CUE: DISCONNECT switch is DOWN For closed position?
- 4. Verify OPEN the AC 8.2/3 Verified OPEN the AC INPUT INPUT BREAKERS on BREAKERS on 24 VDC CHARGERS 24 VDC CHARGERS 1A1 and 1A2.
1A1 AND 1A2.
- CUE: The breaker handles are down.
- 5. Verify OPEN the DC 8.4/5 Verified OPEN the DC OUTPUT OUTPUT BREAKERS BREAKERS on 24 VDC CHARGER on 24 VDC CHARGERS 1A1 and 1A2.
1A1 and 1A2.
- CUE: The breaker handles are down.
- 6. Verify EQUALIZING 8.6/7 Verified the EQUALIZING timer on 24 timer on 24 VDC VDC CHARGERS 1A1 and 1A2 was CHARGERS 1A1 and set at zero.
1A2 set at zero
- CUE: Using a pen, indicate that the timer is at zero (full CCW).
- 7. CLOSE the DC 8.8/9 CLOSED the DC OUTPUT OUTPUT BREAKERS BREAKERS on 24 VDC CHARGER on 24 VDC CHARGER 1A1 and 1A2.
1A1 and 1A2
- CUE: The breakers are CLOSED.
- 8. Verify CLOSED Bkr 5 8.10 Verified CLOSED Bkr 5 on CDP-1A.
on CDP-1A, Feeder to 24 VDC Battery #CUE: The breaker is in the UP? position Chargers 1A1 and 1A2
Nebraska Public Power District SKL034-40-14 Cooper Nuclear Station Page 5 of 7 Job Performance Measure for Operations Revision: 2 Task No.: 263030P0104 PLACE 24 VDC BATTERIES AND ASSOCIATED CHARGERS IN SERVICE Performance Checklist Standards Sat Unsat
- 9. CLOSE the AC INPUT 8.11 CLOSED the AC INPUT BREAKERS BREAKERS on 24 on 24 VDC CHARGER 1A1 and 1A2.
VDC CHARGER 1A1 and 1A2 #CUE: The breakers are CLOSED.
- 10. Verify the GREEN AC 8.11.1.1 Verified the AC ON INDICATING ON INDICATING LIGHT LIGHTS were illuminated.
on 24 VDC CHARGER 1A1 and 1A2 is #CUE: The GREEN lights are illuminated.
illuminated
- 11. Verify that the 8.11.1.2 Verified the voltmeters to be voltmeters on 24 VDC reading ~26.5 VDC.
CHARGER 1A1 and 1A2 are reading ~26.5 #CUE: With a pen and the respective VDC. Voltmeters, point to ~ 27 VDC.
- 12. Verify annunciators. 8.11.1.4 Verified with the Control Room that Annunciators C-2/A-7 and C-2/B-7 are clear.
- CUE: The annunciators are clear.
- 13. Test GROUND 10.1.1 Placed GND. DETECTION toggle DETECTION indicating switch on 24V Charger 1A1 to LAMP lights TEST and checked that the red GND DET indicating lights turned on.
- CUE: The Red GND DET indicating lights are on.
- 14. Test for grounds on 24 10.1.2 Placed GND. DETECTION toggle VDC CHARGER 1A1 switch on 24V Charger 1A1 to GND.
DET and checked left red GND DET indicating light turned on and right red GND DET indicating light remained off.
- CUE: Left light ON, right light OFF.
- 15. Test GROUND 10.2.1 Placed GND. DETECTION toggle DETECTION indicating switch on 24V Charger 1A2 to LAMP lights TEST and checked red GND DET indicating lights turned on.
- CUE: The Red GND DET indicating lights turn on.
- 16. Test for grounds on 24 10.2.2 Placed GND. DETECTION toggle VDC CHARGER 1A2 switch on 24V Charger 1A2 to GND.
Nebraska Public Power District SKL034-40-14 Cooper Nuclear Station Page 6 of 7 Job Performance Measure for Operations Revision: 2 Task No.: 263030P0104 PLACE 24 VDC BATTERIES AND ASSOCIATED CHARGERS IN SERVICE Performance Checklist Standards Sat Unsat DET and checked right red GND DET indicating light turned on and left red GND DET indicating light remained off.
- CUE: Right light ON, left light OFF.
- 17. Verify voltage 8.15 Verified voltages on Panel DC-A to be ~
indications on 24 VDC 26.5 VDC Power Panel DC-A to be
~26.5 VDC #CUE: With a pen and the respective Voltmeters, indicate ~ 26.7 VDC
- 18. Notify the CRS that task The operator contacted the CRS and is completed. informed him that 1A1 and 1A2 24 VDC Battery Chargers and Batteries have been returned to service.
CUE: The BOP operator acknowledges the report.
Stop Time: _________________ Total Time: _________________
Nebraska Public Power District SKL034-40-14 Cooper Nuclear Station Page 7 of 7 Job Performance Measure for Operations Revision: 2 Task No.: 263030P0104 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to place 24 VDC batteries and associated chargers in service in accordance with Procedure 2.2.26, 24 VDC Electrical System. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
If being simulated in the Control Room:
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 1. A refuel outage is in progress.
- 2. 1A1 and 1A2 24 VDC batteries have been replaced.
Initiating Cue(s):
The BOP operator has directed you to return the 1A1 and 1A2 battery chargers and associated 24 VDC batteries to service in accordance with Procedure 2.2.26, 24 VDC Electrical System. .
All prerequisites have been completed or verified.
Notify the Control Room Supervisor when the 1A1 and 1A2 battery chargers and 24 VDC batteries have been returned to service.
Nebraska Public Power District SKL034-40-102 Cooper Nuclear Station Page 1 of 7 Job Performance Measure for Operations Revision 0 Task No.: 200223A0501
Title:
ALTERNATE BORON INJECTION WITH RCIC Trainee: Examiner:
Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Plant
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 20 minutes
Directions to Examiner:
- 1. This JPM evaluates the trainee's ability to perform Alternate Boron Injection with RCIC in accordance with Procedure 5.8.8, Alternate Boron Injection and Preparation.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Check off either satisfactory or unsatisfactory performance. If Unsat state why in the notes/comments section below.
- 5. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Notes/Comments: ____________________________________________________________
Nebraska Public Power District SKL034-40-102 Cooper Nuclear Station Page 2 of 7 Job Performance Measure for Operations Revision 0 Task No.: 200223A0501
Title:
ALTERNATE BORON INJECTION WITH RCIC Directions to Trainee:
When I tell you to begin, you are to perform Alternate Boron Injection with RCIC in accordance with Procedure 5.8.8, Alternate Boron Injection and Preparation.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
- 3. Boron Injection is required.
General
References:
- 1. Procedure 5.8.8, Alternate Boron Injection and Preparation General Tools and Equipment:
- 1. J423 Key (PTM box padlock)
- 2. Flat Tip Screwdriver
- 3. (2) Spanner Wrenches
- 4. 200' of 1.5" fire hose (R-976-E inside EOP Storage Box) for Alternate Boron Injection with the RCIC System
- 5. Two pipe wrenches (stored on the R-903-NE Quad Alternate Boron Injection hose reel)
Special Conditions, References, Tools, Equipment:
- 1. J423 Key (PTM box padlock), Flat Tip Screwdriver, (2) Spanner Wrenches, 200' of 1.5" fire hose (R-976-E inside EOP Storage Box) for Alternate Boron Injection with the RCIC System, Two pipe wrenches (stored on the R-903-NE Quad Alternate Boron Injection hose reel)
- 2. Critical checks denoted in bold.
- 3. Simulator cues denoted by "#".
Nebraska Public Power District SKL034-40-102 Cooper Nuclear Station Page 3 of 7 Job Performance Measure for Operations Revision 0 Task No.: 200223A0501
Title:
ALTERNATE BORON INJECTION WITH RCIC Task Standards:
- 1. Place Alternate Boron Injection in service using RCIC in accordance with Procedure 5.8.8 Alternate Boron Injection and Preparation.
- 2. 100% of critical elements successfully completed without error.
- 3. 100% of safety and radiological work practices.
Initiating Cue(s):
The Control Room Supervisor directs you perform Alternate Boron Injection with RCIC in accordance with Procedure 5.8.8, Alternate Boron Injection and Preparation.
Notify the CRS when Alternate Boron Injection is in service using RCIC.
Nebraska Public Power District SKL034-40-102 Cooper Nuclear Station Page 4 of 7 Job Performance Measure for Operations Revision 0 Task No.: 200223A0501
Title:
ALTERNATE BORON INJECTION WITH RCIC Start Time: ____________
Performance Checklist Standards Sat Unsat The Operator obtained the current revision of Procedure 5.8.8. Alternate Boron Injection and
- 1. Obtain Procedure Preparation Selects Section 7.
7.3.1 Ensured SLC-17, TANK DRN, is closed (R-976-East).
- 2. Ensure RCIC
- CUE: The valve is fully clockwise and the Lineup hand-wheel has resistance. If there is a valve position indicator, use it and point with a pen to the closed indication 7.3.2 Removed drain cap on outlet of SLC-17 and attached Alternate Boron Injection
- 3. Drain cap removed hose obtained from dedicated hose reel and hose attached.
on R-976-East
- CUE: Drain cap is removed and hose is attached 7.3.3 Connected hose dropped from 976 level of Reactor Building to 903 level of NE
- 4. Thread hose Quad stairwell.
through pipe chase
- CUE: Hoses are connected 7.3.4 Connected hose to Alternate Boron Injection hose obtained from dedicated
- 5. Connect Hose hose reel on 903 level of NE Quad stairwell
- CUE:Hoses are connected.
7.3.5 Threaded second hose through R-903-NE
- 6. Thread hose Quad door and down to elevation 859 through door and between stairs down stairs
- CUE:Hose is installed.
Nebraska Public Power District SKL034-40-102 Cooper Nuclear Station Page 5 of 7 Job Performance Measure for Operations Revision 0 Task No.: 200223A0501
Title:
ALTERNATE BORON INJECTION WITH RCIC Performance Checklist Standards Sat Unsat 7.3.6 Using two pipe wrenches obtained from R-903-NE Quad Alternate Boron Injection hose reel, remove 90° elbow from end of
- 7. Remove Elbow on pipe on outlet of RCIC-179, RCIC PUMP Drain Valve SUCTION STRAINER DRAIN SHUTOFF (R-859-NE QUAD).
- CUE: Elbow is removed.
7.3.7 Attached hose to end of pipe on outlet of RCIC-179, RCIC PUMP SUCT. STRN.
- 8. Attach hose to DRN. SHUTOFF (R-859-NE QUAD)
RCIC Suction
- CUE: Hose is attached.
7.3.8 Informed CRS that Alternate Boron Injection line from SLC tank to RCIC suction is
aligned to RCIC
- CUE:CRS acknowledges alignment.
7.4 Contacted the control room RO to ensure the RCIC Pump was running and system valves were aligned:
- RCIC-MO-20, PUMP DISCH VLV, is OPEN
- RCIC-MO-21, PUMP DISCH TO RX VLV, is
- 10. Verify RCIC OPEN alignment In Control
Room
- RCIC-MO-33, ECST TEST LINE SHUTOFF VLV, is CLOSED
- CUE: Confirm RCIC Pump is running and Repeat Valve positions.
Nebraska Public Power District SKL034-40-102 Cooper Nuclear Station Page 6 of 7 Job Performance Measure for Operations Revision 0 Task No.: 200223A0501
Title:
ALTERNATE BORON INJECTION WITH RCIC Performance Checklist Standards Sat Unsat 7.4.7 Opened breakers for the following valves (R-903-NE, RCIC STARTER RACK):
- 11. Opens breakers for RCIC-MO-33, ECST TEST LINE SHUTOFF.
valves RCIC-MO-27, MIN FLOW BYP VLV.
- CUE: The breakers are in the UP positions?
7.5 Commenced Alternate Boron Injection by opening following valves:
7.5.1 SLC-17, TANK DRN (R-976-E).
7.5.2 RCIC-179, RCIC PUMP SUCT. STRN.
DRN. SHUTOFF (R-859-NE QUAD).
DRN. ROOT (R-859-NE QUAD).
- CUE: As each valves handwheel is turned (CCW), the valves hand-wheel turns until resistance is felt. If there is an indicator for open and closed, point to OPEN. Also, if each valve has a rising stem, then communicate that as well.
7.7 Informed CRS that alternate boron injection via RCIC is in progress.
- 13. Notifies the CRS
- CUE: CRS acknowledges.
Stop Time: __________ Total Time: ___________
Nebraska Public Power District SKL034-21-102 Cooper Nuclear Station Page 7 of 7 Job Performance Measure for Operations Revision 0 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to perform Alternate Boron Injection with RCIC in accordance with Procedure 5.8.8, Alternate Boron Injection and Preparation.
Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.
During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.
General Conditions:
1 The Plant has entered EOP 6A due to a Scram without rods inserting completely.
2 SLC is unavailable for Boron injection to the RPV.
3 Boron Injection is required.
Initiating Cue(s):
The Control Room Supervisor directs you perform Alternate Boron Injection with RCIC in accordance with Procedure 5.8.8, Alternate Boron Injection and Preparation.
Notify the CRS when Alternate Boron Injection is in service using RCIC.
Appendix D Scenario Outline Form ES-D-1 Facility: Cooper Nuclear Station Scenario No.: 1 Op-Test No.: ___1____
Examiners: ____________________________ Operators: _____________________________
Initial Conditions: Plant operating at 85% power (BCL), D CWP out of service.
Turnover: Return D CWP to service, 2.2.3 completed to step 5.5, backwash completed, Continue startup to 100% power. .
Event Malf. Event Event No. No. Type* Description 1 N/A N Place Circulating Water Pump D in service (2.2.3)
(BOP) 2 N/A TS Enters Tech Spec 3.8.1. Condition B Diesel Generator Jacket Water (SRO) Cooling Temperature Low.
3 N/A R Raise Reactor Power using reactor recirculation (2.1.10)
(ATC) 4 RR17a C RR Pump A runs back in speed on the power rise and must be locked out to halt to speed drop. (Abnormal Procedure 2.4RR).
(ATC) 5 N/A TS Enters Tech Spec 3.1.7, Condition A (Based on SLC Tank Suction to (SRO) pump A Closed) 6 EG03 C H2 Gas leak in Generator (Abnormal Procedure 2.4 Gen)
(BOP) 7 N/A N, R Reduce power using Recirculation Pump Flow (2.1.10)
(ATC) 8 N/A M , (©) Unit SCRAM due to Generator hydrogen leak (EOP 1A, 6A,7A)
(Crew) 9 RD15 I , (©) ATWS Manually insert control rods with RMCS (EOP 5.8.3)
(ATC) 10 ED19c C 125V DC power panel AA-3 loses power. (Emergency Procedure 5.3DC125)
(BOP) 11 FW18b C , (©) FW Line B Break inside DW (transition to ECCS for RPV Level (ATC) Control) 2.4MC-RF and 2.4PC.
MS02b 12 RC04 C RCIC controller fails downscale in AUTO, works in Manual (BOP)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specifications, (©) CT Page 1 of 29
Appendix D Scenario Outline Form ES-D-1 Initial Conditions: 85% power (BCL), D CWP out of service, Turnover:
The D CWP will be returned to service, 2.2.3 completed to step 5.5, backwash completed, continue startup to 100% power using reactor recirculation system.
==
Description:==
BOP Operator will place the 4th Circulating Water Pump in service per procedure 2.2.3 Circulating Water System Operation.
The BOP operator will respond to annunciator C-1/E-3, Diesel Gen 1 Trouble and direct a plant operator to investigate. Low jacket cooling water temperature with a jacket heater failure will make DG1 Inoperable. This will require the SRO to enter Tech Spec 3.8.1, Condition B (Based on DG1 being INOP) and determine that SR 3.8.1.1, Verification of Electrical Sources within one hour and it must be restored within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per action B.1.and B.2 The ATC will raise reactor power using Reactor Recirculation flow at least 5% power using procedure 2.1.10, Station Power Changes. During the power rise, RR Pump A will run back in speed requiring the ATC to stop the speed reduction by locking out the pump's scoop tube.
Abnormal Procedure 2.4RR is entered. The CRS will enter TS LCO 3.4.1, Condition B is RR pump speeds differ by more than 5%.
A non-licensed operator will call the control room and report that the SLC - 48, Pump A Tank suction valve is unlocked and closed. This will require the SRO to enter Tech Spec 3.1.7, Condition A.
The BOP operator will respond to a H2 Gas leak on the main generator. Abnormal procedure 2.4GEN-H2 will be entered requiring the operator to remove the generator from service due to excessive leakage.
The ATC will reduce Reactor Recirculation flow to lower power in preparation for removing the reactor from service using procedure 2.1.10, Station Power Changes.
When the reactor is SCRAMMED 15 control rods fail to fully insert (ATWS). The SRO will enter EOPs 6A and 7A. The ATC will insert control rods per EOP 5.8.3 using the reactor manual control system.
After the scram the 125V DC Panel AA-3 will lose power. The crew will enter 5.3DC125 and shift loads that have lost power.
A small Feedwater line break will occur inside the drywell requiring the BOP operator to utilize ECCS systems to maintain reactor water level, and both the ATC and BOP operators will take actions to restore RPV water level and containment parameters. The drywell will require containment sprays to maintain pressure within acceptable limits.
Page 2 of 29
Appendix D Scenario Outline Form ES-D-1 When RCIC is started the BOP Operator will recognize the Controller is not working In AUTO and transfer the controller to MANUAL to control Reactor Water Level per procedure 2.2.67 RCIC System Operation.
The scenario ends when Drywell pressure is being controlled and Reactor Water Level is restored to the normal band and all control rods are inserted.
Page 3 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Place Circulating Water Pump D in service Time Position Applicants Action or Behavior Perform operator action of procedure 2.2.3, Circulating Water System, (Section 5.5) 5.5 Verifies pump has been backwashed per Section 9, (See turnover sheet).
5.6 Place and hold control switch for CIRC WATER PUMP to be started to START until pump starts and check following:
5.6.1 Discharge valve is opening and pump starts after valve has partially opened.
5.6.2 Pump motor current is < 218 amps.
BOP 5.6.3 Pump discharge pressure is within acceptable operating limits per Attachment 1.
5.7 Restore valves operated in Step 5.3.6 to full open.
5.8 Ensure 7 gpm bearing water flow being maintained as indicated on CW-FIS-351.
5.8.1 Annunciator A-4/C-3, CIRC WATER PUMP BRG WTR LOW FLOW, not alarming for pump started.
5.8.2 Verify sufficient gland water leakoff.
Booth ROLE PLAY: If requested as NLO to check CWP D gland water Operator leakoff and bearing water report flow is normal.
BOP Informs CRS that D Circulating Water Pump is in service.
CRS Acknowledges D Circulating Water Pump in service.
END OF EVENT Page 4 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Place Circulating Water Pump D in service Time Position Applicants Action or Behavior Notes Proceed to the next event at direction of the lead examiner.
Page 5 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event
Description:
Diesel Generator Jacket Cooling Water Temperature Low Time Position Applicants Action or Behavior Booth ROLE PLAY: When directed by the Lead Examiner insert Override On for annunciator C-1/E-3, Diesel Gen 1 Trouble.
Operator Respond to annunciator C-1/E-3, Diesel Gen 1 Trouble.
BOP Dispatch NLO to investigate alarm on panel DG-1.
ROLE PLAY: When directed as NLO to investigate, wait 5 minutes and Booth DELETE override on alarm C-1/E-3 then report DG-1/A-1, Jacket Water Operator Low Temperature is alarming and the jacketo water heater will not turn on. Jacket water temperature indicates 99 F and DG-1 is Inop per ARP.
Enter Tech Spec 3.8.1 AC Sources Operating, Condition B, and determine the Diesel Generator is INOP and actions B.1 and B.2 are required.
B1. Perform SR 3.8.1.1 for OPERABLE offsite circuit(s) within one hour and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
CRS AND B.2 Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable within four hours.
Review and perform SR 3.8.1.1, Verify correct breaker alignment and BOP indicated power availability for each offsite circuit.
NOTE : Performance of SR 3.8.1.1 is not required for up to one hour and may not be started immediately END OF EVENT Page 6 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event
Description:
Diesel Generator Jacket Cooling Water Temperature Low Time Position Applicants Action or Behavior Notes Proceed to the next event at direction of the lead examiner.
Page 7 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event
Description:
Raise Reactor Power using Reactor Recirculation Time Position Applicants Action or Behavior Directs the ATC to increase reactor power using procedure 2.1.10, Station Power Changes (Section 6) 6.1 Step is N/A 6.2 Step is N/A 6.3 During initial power ascension following refueling outage and first sequence exchange in a cycle, maintain power ascension ramp rate 2% CTP/hr from 70% power up to rated power.
CRS 6.4 Raise power by raising RR pump flow as follows:
6.4.1 IF thermal power 2413 (or 2375 if power limited to 2381 MWt), THEN raise power by raising RR pump flow.
6.4.1.1 Maintain rate of power change consistent with system capabilities as determined by Load Dispatcher and TG limits.
6.4.2 Step is N/A.
NOTE to Lead Examiner: After the power rise is satisfied, continue with the next event prior to the completion of the power rise (RR pump runs back).
Increase reactor power using procedure 2.1.10, Station Power Changes ATC (Section 6)
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 8 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
RR Pump A controller causes RR Pump A to run down in speed.
Time Position Applicants Action or Behavior When directed by the Lead Examiner Insert Trigger 2 (RR 17a)
Booth Operator RR Pump A run back towards 55% speed.
Recognize RR Pump A lowering in speed.
Respond to alarm 9-4-3/C-2, RRMG A SCOOP TUBE LOVKOUT.
CRS Enter Procedure 2.4RR, and assign actions to ATC.
Enter 2.4RR, Attachment 4 1.1 Operate scoop tube locally per Procedure 2.2.68.1; or 1.2.1 Trip affected RRMG; or ATC 1.2.2 Enter Procedure 2.1.5.
- 2. If RR pump tripped, THEN enter Attachment 1
- 3. Ensure requirements of SR 3.4.1.1 are met as soon as practical.
If greater than 5% speed mismatch, Enter LCO 3.4.1 CRS Condition B-Satisfy requirement of the LCO.
Completion Time 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
NOTE to Examiners: If RR pump speeds vary more than 5%, the CRS may direct RR B speed lowered to match RR Speed A.
If directed to adjust RR A flow locally, use Remote Function Booth Operator RR05.
END OF EVENT Notes Page 9 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
RR Pump A controller causes RR Pump A to run down in speed.
Time Position Applicants Action or Behavior Proceed to the next event at direction of the lead examiner.
Page 10 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event
Description:
SLC Tank outlet valve found closed.
Time Position Applicants Action or Behavior Upon direction from the lead examiner call the BOP Operator and inform him/her that you are the Reactor Building Non Licensed Booth Operator and during your rounds you have found SLC-48, SLC Pump A Operator Tank Outlet valve unlocked and Closed.
Receives a phone call from Reactor Building NLO that during rounds he has BOP discovered SLC-48, SLC Pump A Tank Outlet valve unlocked and Closed.
Informs the CRS of the issue.
Instructs the Non Licensed Operator to Open the valve and perform a valve BOP lineup for the entire SLC System.
Enter Tech Spec 3.1.7 Standby Liquid Control System and determine SLC subsystem A is inoperable.
CRS Action A.1, Restore SLC subsystem to OPERABLE status within 7 days.
Direct system lineup performed per 2.2.74 and SR 3.1.7.6.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 11 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event
Description:
H2 Gas leak in Generator Time Position Applicants Action or Behavior Booth At the direction of the lead examiner once 5% reactor power has Operator been achieved, insert Trigger 1 (EG03) Generator Hydrogen leak.
Respond to annunciators:
Inform the CRS that Hydrogen Pressure in the Main Generator is lowering and entry into 2.4GEN-H2 is required.
Enters ABNORMAL PROCEDURE 2.4GEN-H2 GENERATOR OR HYDROGEN ABNORMAL 4.1 Record current time and date.
4.2 Concurrently refer to Attachment 4, ABNORMAL H2 GAS PRESSURE OR H2 LEAKAGE 4.3 Obtain Control Room Supervisor review/concurrence.
Perform Attachment 4 as follows:
BOP 1. Make announcement for personnel to stay clear of Turbine Building due to potential hydrogen leak.
- 2. IF H2 is leaking into Turbine Building, THEN direct a Non Licensed Operator to perform steps 2.1 through 2.3
3.1 IF Annunciator 9-5-2/C-4 is clear, THEN SCRAM and enter Procedure 2.1.5.
3.2 Trip Main Turbine.
3.3 IF reactor was not scrammed, THEN enter Procedure 2.2.77.
- 4. Maintain Main Generator Capability Curve per Attachment 8 by Page 12 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event
Description:
H2 Gas leak in Generator Time Position Applicants Action or Behavior lowering power per Procedure 2.1.10 to reduce load.
ATC Update crew of ownership of Scram action parameter of 2.4GEN-H2.
Direct the Actions of 2.4 GEN-H2, per attachment 4 as follows:
Direct BOP Operator to
- Update Crew at 5 psig increments as pressure lowers.
- 45 psig - Generator capability limit shifts to 30 psig curve.
Inform the Crew that:
SCRAM is required when Generator H2 pressure reaches < 30 psig.
- Prepare to reduce power per Procedure 2.1.10 - rapid power reduction CRS may be required.
- Brief Procedure 2.1.5.
- Assign Operator to continue Procedure 2.4GEN-H2 action post-Scram.
- Discuss shutdown resources without Fire Brigade.
- Request Operations support from Training or WCC.
- Contact RP for H2 monitoring in Turbine Building.
- Make announcement for personnel to stay clear of Turbine Building.
- Assign Operator to standby for isolating H2.
- Review Flammable and Other Hazard EALs for applicability.
ROLE PLAY-If sent to check H2-PI-13 locally, report pressure is 135 psig.
If sent to check H2-PI-14 (near vacuum priming tank) report hydrogen Booth pressure as 50 psig.
Operator If directed to close H2-106 and H2-108 in the Hydrogen House, wait 3 minutes and report the valves are closed.
END OF EVENT Notes Page 13 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event
Description:
H2 Gas leak in Generator Time Position Applicants Action or Behavior Proceed to the next event at direction of the lead examiner.
Page 14 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
Reduce power using Recirculation Pump Flow in preparation for removing generator from service.
Time Position Applicants Action or Behavior Direct ATC to reduce power in preparation for removing the Main Generator CRS from service.
Refers to procedure 2.1.10, Station Power Changes, Attachment 2 Rapid Power Reduction 1.1 Place OWC INJECTION SYS ENABLE switch to SHUTDOWN (Panel A).
1.2 While monitoring rod line and feedwater flow, reduce core flow to 40x106 lbs/hr using Reactor Recirculation.
1.3 Before rod line exceeds 118.0%, go to Section 9.
1.4 WHEN core flow is ~ 40x106 lbs/hr, THEN go to Section 9, and perform remaining applicable steps of rapid power reduction.
9.5 Reduce rod line to < 70% by performing the following:
9.5.1 Insert Emergency Power Reduction Rods per Procedure 10.13.
ATC 9.5.2 WHEN feedwater flow is 4.5 X 106 to 8.5x106 lbs/hr, THEN secure one RFP by performing following:
9.5.2.1 At any RVLC/RFPT HMI on the RFPT-1A(1B) MAIN CONTROL screen, place RFPT controller to be removed from service in MDEM.
9.5.2.2 Slowly lower speed of RFPT being removed from service using UP/DOWN arrows on RFPT-1A(1B) controller.
9.5.2.3 Check speed of operating RFPT rises to maintain RPV level.
9.5.2.4 Ensure minimum flow valve for RFP being removed from service opens.
9.5.2.4.1 RFP A - RF-FCV-11A, MINIMUM FLOW.
Page 15 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
Reduce power using Recirculation Pump Flow in preparation for removing generator from service.
Time Position Applicants Action or Behavior 9.5.2.4.2 RFP B - RF-FCV-11B, MINIMUM FLOW.
9.5.2.5 WHEN discharge pressure for RFPT being removed from service is less than RPV pressure, THEN press RFPT A(B)
TURBINE TRIP button (Panel A) and check RFPT A(B) speed drops.
9.5.2.6 At Panel A, close RF-MO-29(30), RFP A(B) DISCHARGE VLV.
9.5.2.7 As time permits, secure RFPT being removed from service per Procedure 2.2.28.
9.6 WHEN rod line 70%, THEN reduce core flow to minimum using Reactor Recirculation.
9.7 IF further power reduction is necessary, THEN enter Procedure 2.1.5.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 16 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Event
Description:
Unit SCRAM due to low Generator Hydrogen pressure.
Time Position Applicants Action or Behavior CRS Directs ATC to perform actions 2.1.5 and enters EOP1A Critical SCRAM Reactor prior to Generator Hydrogen pressure lowering to 25 Task psig.
Perform Attachment 1 mitigating task scram actions of 2.1.5 as follows:
1.2 Place REACTOR MODE switch to REFUEL.
ATC 1.3 IF reactor power > 3%, THEN perform following:
1.3.1 Place REACTOR MODE switch to SHUTDOWN.
1.3.2 Initiate ARI.
Perform Attachment 2 Reactor Power Control of 2.1.5 as follows:
1 REACTOR POWER CONTROL 1.1 Ensure REACTOR MODE switch is in SHUTDOWN.
1.2 Verify all SDV vent and drain valves are closed.
NOTE - RR pump(s) will be tripped if on Normal Transformer or if ARI/RPT has automatically initiated.
ATC 1.3 Ensure operating RR pumps have run back to 22% speed.
NOTE - Steps 1.4 and 1.5 may be performed concurrently.
1.4 Verify all control rods are fully inserted.
Page 17 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 8 Event
Description:
Unit SCRAM due to low Generator Hydrogen pressure.
Time Position Applicants Action or Behavior 1.4.1 If necessary, insert control rods as directed by CRS.
1.5 Observe nuclear instrumentation and perform following:
1.5.1 Insert SRM detectors.
1.5.2 Insert IRM detectors.
1.5.3 Change APRM recorders to IRMs.
1.5.4 Range IRMs on scale.
Check reactor power is lowering Reports NOT all rods inserted during performance of 1.4 of 2.1.5.
ATC 15 rods did not fully insert.
Enters EOP1A and exits at step RC3 when all rods are NOT inserted and CRS power is less than 3%.
Enters EOP6A and 7A ATWS CREW Update crew of PCIS Group 2 isolation.
END OF EVENT Notes Proceed to the next event ATWS.
Page 18 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 9 Event
Description:
ATWS Time Position Applicants Action or Behavior Direct ATC to reset the reactor scram and ARI and insert control rods per CRS Procedure 5.8.3, Alternate Rod Insertion.
Insert Control Rods per 5.8.3.
- 4. ALTERNATE ROD INSERTION 4.1 Perform Attachment 1, Alternate Rod Insertion Methods Flowchart, using the 11" x 17" color-enhanced flowcharts provided in the Control Room.
ATC 4.2 Under ATWS conditions, control rod insertions should start in the center of the core, or for partial ATWS conditions, the center of the region with lowest control rod density, and proceed to every other control rod in an outward spiral pattern. All control rods should be fully inserted, starting from their post ATWS notch position, in a continuous fashion to the fully inserted position.
Critical Maintain RPV Steam Dome pressure < 1337 psig.
Task Maintain Reactor Pressure Stabilize RPV pressure below 1050 psig using main turbine BPVs and RPV Pressure Control Systems (TABLE 12) as necessary per step FS/P-5 of EOP 6A.
Table 12 RPV PRESSURE CONTROL SYSTEMS EOP 5.8.12 o HPCI with suction from ECST if available (defeat high area temperature isolation interlocks and high suppression pool water level suction transfer logic if necessary) o RCIC with suction from ECST if available (defeat low RPV BOP pressure, high RPV water level, high exhaust pressure, and high area temperature isolation interlocks if necessary) o RFPT A o RFPT B o Main steam line drains o SRVs only with PC water level above 6 ft (restore IA/N2 supply if necessary) o IF continuous IA/N2 supply to SRV accumulators becomes Page 19 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 9 Event
Description:
ATWS Time Position Applicants Action or Behavior unavailable:
o THEN perform following:
- Pressure stabilization (FS/P-5):
- 1. Place each SRV control switch in AUTO
- 2. Prevent Low-Low Set actuation o Depressurization (FS/P-8 and FS/P-10):
- 1. Depressurize with sustained SRV opening o RWCU in blowdown mode (only if no boron has been injected into RPV) o AOG 3rd stage air ejector and preheater o Gland sealing steam o Steam jet air ejectors o RWCU with filters bypassed (defeat isolation interlocks if necessary)
CRS Direct BOP to inhibit ADS.
Perform actions for RPV Level Control EOP7A
- 1. Inhibit ADS (FS/L-3)
- 2. IF any main steam line is not isolated THEN start defeating low RPV water level interlocks if necessary, EOP 5.8.20 BOP 3. Is reactor power above 3% or cannot be determined (FS/L-4)
- 4. FS/L5, 6, 7, and 8 NA
- 5. FS/L9 Maintain RPV water level between -183 in. and +54 in. using Outside Shroud Injection Systems (TABLE 13)
Upon insertion of all control rods inform the CRS and continue in 2.1.5 post ATC scram activities.
Page 20 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 9 Event
Description:
ATWS Time Position Applicants Action or Behavior CRS Exit EOPs 6A and 7A and re-enter EOP 1A END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 21 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 10 Event
Description:
Loss of 125V DC Panel AA-3 Time Position Applicants Action or Behavior Booth ROLE PLAY: When directed by the Lead Examiner insert Trigger 3 (Loss of 125V DC AA-3).
Operator Respond to alarm 9-5-2/E-3, ARI & ATWS RPT LOGIC POWER FAILURE.
ATC Determine loss of Panel AA-3.
Enter 5.3DC125, LOSS OF 125 VDC CRS Assign actions to BOP.
Per 5.3DC125 1.1 Ensure RR Pump A drive motor breaker has tripped. (Pump tripped on scram).
BOP 1.3 Secure SAC 1A 1.4 If CRD Pump A running direct building operator to trip 480V breaker.
If directed to trip SAC 1A, insert RF IA14 to STOP.
Booth If directed to open breaker for SAC 1A, insert RF IA07 to TRIP.
Operator If directed to start SAC 1B insert RF IA15 to START.
NOTE : Performance of SR 3.8.1.1 is not required for up to one hour and may not be started immediately END OF EVENT Notes Page 22 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 10 Event
Description:
Loss of 125V DC Panel AA-3 Time Position Applicants Action or Behavior Proceed to the next event at direction of the lead examiner.
Page 23 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 11 Event
Description:
FW Line B Break Inside the Drywell Time Position Applicants Action or Behavior When directed by lead examiner, activate trigger 5 (FW leak line Booth break inside primary containment and RCIC flow controller Operator failure).
Direct the actions of 2.4MC-RF, CONDENSATE AND FEEDWATER ABNORMAL Determine that the B Feedwater line has failed and RCIC will need to CRS be used to restore Reactor Water Level.
Enter EOP 3A, Primary Containment Control and direct actions.
Direct Drywell FCUs placed in OVERRIDE.
NOTE to Examiners: RCIC injects into feedwater Line A.
HPCI injects into feedwater Line B. (Failure is in FW line B)
Places Drywell FCUs in OVERRIDE as directed.
Perform the actions of 2.4MC-RF, CONDENSATE AND FEEDWATER ABNORMAL as follows:
4.1 If system piping not intact, perform following:
4.4.1 If break is in Turbine Building, concurrently enter Procedure 5.1BREAK.
4.4.2 If break is endangering personnel or equipment necessary ATC for safe operation:
4.4.2.1 Concurrently enter Procedure 2.1.5.
4.4.2.2 Ensure RFPs tripped.
4.4.2.3 Ensure RFP discharge valves closed.
4.4.2.4 At a RFPT/RVLC HMI, perform following:
4.4.2.4.1 Select RFPT-1A or RFPT-1B Page 24 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 11 Event
Description:
FW Line B Break Inside the Drywell Time Position Applicants Action or Behavior System.
4.4.2.4.2 Select STARTUP VALVE screen.
4.4.2.4.3 Press EMER CLOSE button.
4.4.2.4.4 Confirm pop-up screen.
4.4.2.5 Ensure condensate booster pumps tripped.
4.4.2.6 If necessary, trip condensate pumps.
4.4.3 Notify Plant personnel to stay clear of affected area via gaitronics.
CREW Determine feedwater leak in FW Line B.
BOP Secure HPCI per the Hard Card.
CREW Update Group 6 isolation.
Take drywell pressure as critical parameter and make periodic updates BOP to the crew as it rises.
Critical Initiate Drywell spray before drywell temperature exceeds the PSP Task Limit.
Direct transfer of reactor level control from Condensate/Feedwater to CRS RCIC.
NOTE to Examiners: See Event 12 for operator actions in response to RCIC flow controller failure.
When RFPs/condensate booster pumps are tripped, use RCIC per BOP Procedure 2.2.67.1 to maintain RPV level.
Monitor and control PC pressure below 1.84 psig using containment BOP pressure control systems, EOP 5.8.17 (PC/P-1).
Before torus pressure reaches 10 psig Spray Torus (PC/P-2).
Page 25 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 11 Event
Description:
FW Line B Break Inside the Drywell Time Position Applicants Action or Behavior When torus pressure exceeds 10 psig Spray the Drywell (PC/P-3) maintain drywell pressure between +2 - +10 psig.
Monitor average drywell temperature, EOP 5.8.10, and control below 150°F using available drywell cooling (DW/T-1).
When average drywell temperature cannot be maintained below 150°F, Operate all available drywell cooling (defeat isolation interlocks if necessary (DW/T-2).
Before average drywell temperature reaches 280°F Spray the Drywell (DW/T-4).
Monitor and control torus water level between +2 in. and -2 in. (refer to SOP 2.2.69.3 prior to discharging water) (SP/L-1).
Monitor average torus water temperature, EOP 5.8.9, and control below 95°F using available suppression pool cooling (SP/T-1).
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 26 of 29
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 12 Event
Description:
RCIC Controller Fails Downscale in AUTO Time Position Applicants Action or Behavior BOP Operator recognizes RCIC Flow is less than AUTO setpoint value.
NOTE to Examiners: RCIC manual control requires the potentiometer know to be rotated many times before RCIC speed rises. Note Speed V output on controller reaching approximately 80 before RCIC responds.
Places RCIC Controller in MANUAL and restores system flow to 400 gpm using procedure 2.2.67, REACTOR CORE ISOLATION COOLING BOP SYSTEM, Attachment 1.
Restores reactor water level to normal range.
BOP Informs CRS of failure of the RCIC Controller CRS Acknowledges manual control of RCIC.
END OF EVENT Notes When scram has been inserted and RPV level is within band, stop the scenario as directed by the lead examiner.
END OF SCENARIO Page 27 of 29
Appendix D Required Operator Actions Form ES-D-2 Simulator Setup Initialize the simulator in IC 16 (BOL) (Protected IC 231)
Triggers and Malfunctions E1 - EG03 at 1.5% with 4.5 minute ramp.(Event 4)
E2 - RR17a 55% with 2 minute ramp (Event 3)
E3 - ED19C Loss of 125v DC Panel AA-3 (Event 9)
E4 - None E5 - FW18b, 30% severity on a 3:30 ramp rate, RC04at 0%,
MS02b, 12% on a 3:30 ramp rate and 5:00 time delay.
E6 - None E7 - Ia15 Station Air Compressor local start.
E8 - None E9- None E10- None RD15, Failure of control rods to scram-Active (15 control rods 02-27, 06-15, 14-31, 18-27, 22-07, 22-39, 30-15, 30-23, 30-47, 34-11, 34-43, 38-15, 38-31, and 46-39)
Overrides None Panel Set-up
- Mark Tendamatic plaque on Board B with A-B-C
- Ensure PMIS IDTs are blank.
- Place the Startup BOL Rod Sequence Book on Panel 9-5.
- Remove D Circulating Water Pump from service.
- Ensure Station Air Compressor A running and B secured.
Procedures Needed
- Copy of 2.2.3 Circulating water System marked up to step 5.5, and indicate section 9 Backwash has been completed.
Tags Hung None Parameter Monitoring:
Monitor RPV Pressure, Average Power Range Monitors and Power to Flow Map Page 28 of 29
Appendix D Required Operator Actions Form ES-D-2 Turnover Sheet:
Plant Status: The plant is operating at approximately 85% at the beginning of the current fuel cycle. Plant startup is to continue to 100 %. Surveillance 6.SLC.101, SLC Pump Operability Test was performed last shift.
Risk: Green Activities in Progress:
- Preparation for Startup of D Circulating Water Pump to support startup.
Procedure 2.2.3 is completed through step 5.5, and backwash is complete per section 9.0.
- Power raise in accordance with procedure 2.1.10, Power Changes, using RR Pumps.
LCOs in effect: None Equipment out of service: None.
Activities for the Shift:
- Place D CWP in service to support continued startup.
- Continue raising power using Recirculation flow.
Page 29 of 29
Appendix D Scenario Outline Form ES-D-1 Facility: Cooper Nuclear Station Scenario No.: 2 Op-Test No.: ___1____
Examiners: ____________________________ Operators:_____________________________
Initial Conditions: 100% power, EOL, no equipment out of service, Turnover: Reduce power to 90% for HPCI Test. Following HPCI Test return to 100% power.
6.HPCI.103 completed to Step 4.13.
Event Malf. Event Event No. No. Type* Description 1 N/A N, R Reduce Power with Reactor Recirculation (2.1.10)
(ATC) 2 SW04 C RHRSW Pump trips. (2.2.70)
(BOP)
The SRO addresses Tech Spec 3.7.1 Condition A for one TS pump INOP (SRO) 3 N/A N Place RHR Loop B in Suppression Pool Cooling (2.2.69.3)
(BOP) 4 HP12 N Perform HPCI Full Flow Test (6.HPCI.103)
(BOP)
Enters Tech Spec 3.5.1C and declares HPCI INOP TS (SRO) 5 IA05 C Instrument Air dryer plugs. (Abnormal Procedure 5.2AIR)
(BOP) 6 RR50A C Reactor Recirculation Pump high Vibration (ARP)
(ATC)
RR10A, Recirculation Pump Seal Failure (ARP)
RR11A C (ATC) (Abnormal Procedure 2.4RR and 2.4PC) 7 RR31A M© LOCA - RR Suction Line Break (EOP 1A, 3A)
(All)
C RP12 (ATC) PCIS Group 3 isolation failure (2.1.22) 8 RD01 C © Scram Discharge Volume Drain Vlv. Fails to close.
(ATC) 9 O/R I© RHR Loop A Drywell Spray Valves de-energize.
(BOP)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specifications, (©) CT Page 1 of 23
Appendix D Scenario Outline Form ES-D-1 Initial Conditions: 100% power, EOL, HPCI INOP for testing.
Turnover:
Reduce power to 90% for HPCI Test. Following HPCI Test return to 100% power. 6.HPCI.103 completed to step 4.13
==
Description:==
The ATC reduces reactor power using reactor recirculation flow to 90% reactor power in preparation for the HPCI Full Flow Test per 2.1.10 Station Power Changes.
The B RHRSW Pump trips when B loop of RHRSW is placed in service to support Suppression Pool Cooling, and the other pump in the loop is started per 2.2.70. RHR Service Water Booster Pump System. The CRS addresses Tech Spec LCO 3.7.1 and declares the tripped pump inoperable.
The BOP Operator places B Loop of RHR in Suppression Pool Cooling operation to support the HPCI Full Flow Test per 2.2.69.3, RHR Suppression Pool Cooing and Containment Spray and 2.2.70, RHR Service Water Booster Pump System.
The BOP Operator performs the HPCI Full Flow Test per 6.HPCI.103. At step 4.16 the test fails and the SRO addresses Tech Spec 3.5.1C and declares HPCI INOP.
The instrument air dryer fully plugs requiring the filter/dryer bypassed from the control room until the other filter/dryer can be placed in service.
The ATC responds to high vibration on the A Reactor Recirculation Pump per ARP 9-4-3/C-3 and begins to reduce recirculation pump speed to reduce vibrations. The vibration continues and the Recirculation Pump seals fail resulting in a LOCA inside the Drywell. When the Recirculation Pump Trips the Suction Line breaks. The SRO enters EOP 1A and directs the ATC to SCRAM the reactor then enters EOP 3A to address containment pressure issues.
During the SCRAM recovery one of the SDV drain valves fails to close resulting in a primary system leaking into secondary containment. The ATC recognizes this and closes the valve using the control switch on Panel 9-5 and reports action to SRO.
Post scram, the PCIS Group 3 (RWCU) isolation fails and the ATC closes the valves and reports the failure to the CRS.
The SRO directs the BOP operator to secure Drywell Sprays at approximately 2 psig per EOP 3A, and if the operator fails to control drywell pressure the valves will NOT close resulting in a negative pressure in primary containment.
The scenario ends when the primary containment pressure is being controlled in band (+2 to
+10 psig) as directed by the SRO and Reactor water level is in the normal range.
Page 2 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event
Description:
Reduce Power with Reactor Recirculation (Procedure 2.1.10)
Time Position Applicants Action or Behavior Conducts Reactivity Briefing.
CRS Notifies Shift Manager and Load Dispatcher of power reduction for HPCI testing.
CRS Directs ATC to lower reactor power to 90% per 2.1.10.
NOTE to Examiners: CRS may direct BOP to place RHR in Suppression Pool Cooling at the same time the direction is given to reduce reactor power.
Procedure 2.1.10 Station power changes, Section 7 RR ATC FLOW.
NOTE to Examiners: RR pump flows can be read on recorder RR-FR-163 on VBd 9-4.
7.4 Lower power by lowering RR pump flow. Maintain rate of power change consistent with system capabilities as determined by Load Dispatcher and TG limits.
ATC Monitors reactor power, level, and power-to-flow map.
Reports power lowered to 90% to SRO.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 3 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event
Description:
RHRSWBP trips Time Position Applicants Action or Behavior NOTE to Examiners: SWB Pump B or D will trip shortly after starting.
Allow the RHRSWBP to run for a couple of seconds before tripping the Booth first one started. Insert Trigger 10 for SWBP B or Trigger 11 for SWBP Operator D.
Place RHRSW system B in service per 2.2.70 5.2.1 Place and hold SWBP B or D switch to START until pump starts.
5.2.2 At Panel 9-3, check SWBP B or D AMPS are normal.
5.2.3 At Panel 9-3, check SW-MO-89B, HX-B SW DISCH VLV, opens.
BOP Respond to alarm 9-3-3/C-1 (Pump B) or 9-3-3/D-1 (Pump D).
2.3 Start SWBP B(D), as required, per Procedure 2.2.70.
Respond to alarm 9-3-3/A-1 (Pump B) or 9-3-3/B-1 (Pump D).
2.3 Start SWBP B(D), as required, per Procedure 2.2.70.
CRS Direct BOP to place RHRSW system A in service per 2.2.70.
Refers to Tech Spec 3.7.1 Condition A, One RHRSWB Pump inoperable.
Action A.1 Restore RHR suppression pool cooling subsystem to OPERABLE CRS status.
Time 30 Days to restore 5.2.1 Place and hold SWBP B or D switch to START until pump starts.
5.2.2 At Panel 9-3, check SWBP B or D AMPS are normal.
5.2.3 At Panel 9-3, check SW-MO-89B, HX-B SW DISCH VLV, opens.
BOP 5.1.4.1 Flow on SW-FI-132B, SW FLOW, between 2500 and 4000 gpm.
5.1.4.2 SWBP B or D AMPS 136 amps.
5.1.5 Ensure differential pressure on SW-DPI-359B, RHR HX B SW SIDE DIVIDER PLATE DIFFERENTIAL PRESSURE (R-903-B RHR HX Page 4 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event
Description:
RHRSWBP trips Time Position Applicants Action or Behavior Room), 17.0 psid.
5.1.5.1 Record SW-DPI-359B P (R-903-B RHR HX Room) in Narrative Logs When requested as NLO to report differential pressure at step 5.2.5 of Booth SW 2.2.70, respond it indicates 5 psid. (<17 psid is procedurally Operator acceptable)
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 5 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
Place RHR Loop B in Suppression Pool Cooling (Procedure 2.2.69.3)
Time Position Applicants Action or Behavior Directs BOP to place RHR Loop B in Suppression Pool Cooling per CRS 2.2.69.3.
Booth ROLE PLAY: When contacted, report suction line drain flush for hot Operator spots is not required.
Contact ALARA to determine if suction line drain flush for hot spots is needed.
Ensure RHR Subsystem B in Standby Status per Procedure 2.2.69.
Notify Radiation Protection of RHR startup.
BOP IF RHR Subsystem B is being placed in suppression pool cooling to support non-emergency evolutions, THEN perform Section 3 concurrent with this section.
3.1.2 Initiate 6.LOG.601 Torus Average Temperature and Drywell Bulk Average Temperature Log Attachment for testing which adds heat to the suppression pool.
NOTE to Examiners: Annunciator 9-3-1/G-1, ADS AUX COOLING INTERLOCK, in an expected alarm when starting an RHR pump.
Initiate Suppression Pool Cooling:
8.23 Open RHR-MO-39B, SUPPR POOL COOLING/TORUS SPRAY VLV 8.25 Start RHR Pump B or D.
8.26 Throttle open RHR-MO-34B, SUPPR POOL COOLING INBD THROTTLE VLV, to obtain rated cooling flow or as directed by BOP Control Room Supervisor 8.27 Ensure RHR-MO-16B (min flow valve) closed.
8.28 Perform one of the following:
8.28.1 Close CM-38, LOOP B INJECTION LINE PRESSURE MAINTENANCE SHUTOFF (R-958-SW).
8.28.2 Maintain RHR Subsystem B pressure greater than Page 6 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
Place RHR Loop B in Suppression Pool Cooling (Procedure 2.2.69.3)
Time Position Applicants Action or Behavior Condensate Transfer System pressure to prevent filling Torus.
8.29 Throttle closed RHR-MO66B, HX BYPASS VLV, to obtain desired cooling rate.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 7 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Perform HPCI Full Flow Test (Procedure 6.HPCI.103)
Time Position Applicants Action or Behavior NOTE to Examiners: The HPCI Aux Oil Pump discharge line rupture is passive until the pump is started.
CRS Directs performance of 6.HPCI.103 ROLE PLAY: When requested to establish communications, respond Both that you are setup and ready to begin 6.HPCI.103 at step 4.16.
Operator Wait 2 minutes and report oil pressures were recorded.
Reviews procedure 6.HPCI.103 in preparation for continuing surveillance.
Establish Communications with local Operator in HPCI room.
Begins at step 4.13 4.13 Informs CRS that HPCI System is inoperable for testing.
BOP 4.14 Step already completed 4.15 Step already completed 4.16 (Time) Start AUXILIARY OIL PUMP and time STOP VALVE opening stroke time ROLE PLAY-After HPCI AOP is started and Trigger 13 becomes active, Booth call the control room and report a large lube oil leak on the AOP Operator discharge piping.
CRS Halt the HPCI surveillance.
Refers to Tech Spec 3.5.1 Condition C and declares HPCI INOP.
Action C.1 Verify by administrative means RCIC System is OPERABLE within one CRS hour AND C.2 Restore HPCI System to OPERABLE status within 14 days.
Page 8 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Perform HPCI Full Flow Test (Procedure 6.HPCI.103)
Time Position Applicants Action or Behavior BOP Place HPCI AOP control switch to Pull-To-Lock.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 9 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event
Description:
Instrument Air dryer plugs Time Position Applicants Action or Behavior Booth When directed by the Lead Examiner, Insert Trigger 2 (IA05, Operator Instrument Air dryer plugging)
Respond to alarm A-4/A-5, CONTRL AIR LOW PRESSURE.
1.1 Verify SACs operating properly.
1.2 Check for excessive air leaks or usage.
BOP 1.3 Enter Procedure 5.2AIR Report Instrument air pressure from IA-PI-606 (Panel A)
Report Service air pressure from SA-PI-611.
Report Service air pressure high and instrument air pressure low.
CRS Enter Abnormal Procedure 5.2AIR. Assign actions to BOP.
4.3 If air drying/filtering components at fault then perform following:
4.3.1 Open SA-MO-81, SA TO IA CROSSTIE (Panel A) 4.3.2 Place standby dryer and filters in service per Procedure 2.2.59.
BOP 4.3.3 If necessary, manually bypass any obstructed component(s).
4.3.4 When dryer and filter flow returned to service, close SA-MO-81.
Contact building operator and direct other air dryer/filter placed in service.
If directed to place other air dryer/filter in service, wait 5 Booth Operator minutes delete malfunction IA05, and report the other dryer/filter is in service.
END OF EVENT Page 10 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event
Description:
Instrument Air dryer plugs Time Position Applicants Action or Behavior Notes Proceed to the next event at direction of the lead examiner.
Page 11 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
Reactor Recirculation Pump High Vibration (ARP 9-4-3/C-3)
Recirculation Pump Seal Failure (ARP 9-4-3/A-3)
Time Position Applicants Action or Behavior Booth When directed by lead examiner, insert Trigger 4 (RR10a, RR11a, RR50a RR31a, RR Pump A #1 and #2 seal failure, RR Motor A high vibration, Operator and RR Loop A suction rupture)
Operator responds to annunciator, announces RR Pump A Hi vibration, and ATC refers to ARP.
CRS SRO acknowledges announcement.
ARP 9-4-3/C-3, RECIRC A PUMP MOTOR HI VIBRATION 1.1 Monitor RR A pump/motor vibration using PMIS Points.
ATC 1.2 NA 1.3 Notify System Engineer of valid alarms.
NOTE to Examiners: ATC may trip RR pump A before SRO directs it if a drywell pressure increase is noted with the seal trouble annunciator.
ATC Respond to alarm 9-4-3/A-3, RECIRC PUMP A SEAL TROUBLE Operator responds to annunciator, announces alarm RR Pump A seal ATC failures, and refers to ARP.
CRS Directs ATC to trip RR pump A and entry into 2.4RR.
Trips RR pump A and enters 2.4RR.
4.3 Checks power-to-flow map for operating in the exclusion zone 4.4 Secure OWC Injection System, place OWC INJECTION SYS ENABLE SWITCH to SHUTDOWN (PANEL A).
ATC 4.5 Perform applicable Attachment 2, RECIRCULATION PUMP SEAL FAILURE Attachment 2
- 1. If both seals have failed and affected RR pump requires prompt Page 12 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
Reactor Recirculation Pump High Vibration (ARP 9-4-3/C-3)
Recirculation Pump Seal Failure (ARP 9-4-3/A-3)
Time Position Applicants Action or Behavior isolation, perform following:
1.1 Ensure DRIVE MOTOR BKR 1CN, 1CS (1DN, 1DS) is tripped.
1.2 Close RR-MO-43A(B), PUMP SUCTION VLV.
1.3 Close RR-MO-53A(B), PUMP DISCHARGE VLV.
1.4 Close CRD-50 (CRD-51), REACTOR RECIRCULATION PUMP A (B) SEAL FLOW REGULATOR 46A (B) INLET (R-903-SE).
1.5 Following steps may be performed concurrently:
1.5.1 Enter Single Loop Operation section of Procedure 2.2.68.1.
1.5.2 Ensure RRMG Set A(B) GEN FIELD BKR open.
1.5.3 Ensure operating RRMG is transferred to Startup Transformer per Procedure 2.2.18.
If both seals have degraded and time allows, shut down and isolate affected pump per Procedure 2.2.68.1.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 13 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event
Description:
LOCA - RR Suction Line Break (EOP 1A, 3A)
Time Position Applicants Action or Behavior NOTE to Examiners: malfunction RR31A, 5%, RR Suction line leak is already ramping in (Active).
Crew Respond to drywell pressure rise.
CRS Enter abnormal Procedure 2.4PC BOP Enter 2.4PC and vent containment per the (Hard Card).
ATC Accept scram action of 1.5 psig drywell pressure.
CRS Direct ATC to SCRAM at 1.5 psig drywell pressure.
CRS Enters EOP 1A and 3A on high drywell pressure and directs actions.
SCRAM or verify SCRAM per 2.1.5
1.2 Place REACTOR MODE switch to REFUEL.
ATC 1.3 IF reactor power > 3%, THEN perform following:
1.3.1 Place REACTOR MODE switch to SHUTDOWN.
1.3.2 Initiate ARI.
Perform Attachment 2 Reactor Power Control of 2.1.5 as follows:
ATC 1 REACTOR POWER CONTROL Page 14 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event
Description:
LOCA - RR Suction Line Break (EOP 1A, 3A)
Time Position Applicants Action or Behavior 1.1 Ensure REACTOR MODE switch is in SHUTDOWN.
1.2 Verify all SDV vent and drain valves are closed.
NOTE - RR pump(s) will be tripped if on Normal Transformer or if ARI/RPT has automatically initiated.
1.3 Ensure operating RR pumps have run back to 22% speed.
NOTE - Steps 1.4 and 1.5 may be performed concurrently.
1.4 Verify all control rods are fully inserted.
1.4.1 If necessary, insert control rods as directed by CRS.
1.5 Observe nuclear instrumentation and perform following:
1.5.1 Insert SRM detectors.
1.5.2 Insert IRM detectors.
1.5.3 Change APRM recorders to IRMs.
1.5.4 Range IRMs on scale.
Check reactor power is lowering.
CREW Recognize failure of PCIS Group 3 isolation.
Close RWCU-MO-15 and MO-18.
ATC Throttle open MO-74 EOP 1A RPV Control (RC/P-5)
BOP Stabilize RPV pressure below 1050 psig using main turbine BPVs and RPV Pressure Control Systems (TABLE 1) as necessary (RC/L-5)
Page 15 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event
Description:
LOCA - RR Suction Line Break (EOP 1A, 3A)
Time Position Applicants Action or Behavior If ADS timer has initiated THEN inhibit ADS Note to Examiners: Either Loop of RHR may be used for Torus Spray and Drywell Spray.
Only A Loop of RHR may be used for Torus cooling.
Critical Initiate Drywell Spray prior to Torus Pressure reaching 25 psig.
Task CRS Directs Containment Sprays initiated.
(PC/P-1 )
Monitor and control PC pressure below 1.84 psig using containment pressure control systems, EOP 5.8.17 (PC/P-2)
BEFORE torus pressure reaches 10 psig, Spray Torus (PC/P-3)
When Torus pressure exceeds 10 PSIG Spray the Drywell
- 2. Containment Sprays (RHR Hard Card) 2.1 IF required, with CRS permission, THEN place CONTMT COOLING 2/3 CORE VALVE CONTROL PERMISSIVE switch to MANUAL BOP OVERRD.
2.2 IF required, THEN place CONTMT COOLING VLV CONTROL PERMISSIVE switch to MANUAL.
2.3 Ensure RHR-MO-39A(B) open.
2.4 IF reactor pressure 300 psig and injection not desired, THEN close RHR-MO-27A(B), OUTBD INJECTION VLV.
2.5 Ensure RHR PUMP(s) running.
NOTE - RHR pump operation at minimum flow should be limited to
< 15 minutes or pump damage may result.
2.6 Throttle RHR-MO-38A(B) to maintain desired containment pressure.
2.7 Throttle RHR-MO-66A(B) to obtain desired cooling rate.
Page 16 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event
Description:
LOCA - RR Suction Line Break (EOP 1A, 3A)
Time Position Applicants Action or Behavior 2.8 IF Drywell Spray required, THEN perform following:
2.8.1 Open RHR-MO-31A(B).
2.8.2 Throttle RHR-MO-26A(B) to maintain desired containment pressure.
2.9 IF PCIS Group 6 lights lit on Panel 9-5, THEN ensure one of following open:
2.9.1 REC-MO-711; or 2.9.2 REC-MO-714.
2.10 Place RHR SW System in service:
2.10.1 Start SWBP(s).
2.10.2 Adjust SW-MO-89A(B) to maintain flow between 2500 and 4000 gpm.
2.11 Throttle RHR-MO-66A(B) to maintain desired cooling rate.
Maintain Drywell pressure between +2 & +10 psig.
Ensure each of following initiated:
- ECCS initiations
- DGs (RC/L-3)
ATC Restore and maintain RPV water level between +3 in. and +54 in. with one or more Injection Systems (TABLE 3)
(RC/L-4)
When RPV water level cannot be restored and maintained between +3 in.
and +54 in.
(RC/L-6)
Restore and maintain RPV water level above -150 in. using Injection Systems (TABLE 3) and, if necessary, Alternate Injection Subsystems Page 17 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event
Description:
LOCA - RR Suction Line Break (EOP 1A, 3A)
Time Position Applicants Action or Behavior (TABLE 4)
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 18 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event
Description:
Scram Discharge Volume Drain Valve Fails to close.
Time Position Applicants Action or Behavior NOTE to Examiners: The SDIV drain valve (AO-33) on the south volume fails to isolate when required post scram.
Critical Isolate primary system discharging into secondary containment before Task any Max Safe Operating Limit is reached.
Recognizes that Scram Discharge Volume Drain valve failed to close while performing post scram actions of 2.1.5, Attachment 2, step 1.2 verify all SDV vent and drain valves closed.
s ATC Informs CRS that SDV drain valve failed to close.
Places SDV Isolation switch on Panel 9-5 to ISOL.
Reports SDV drain valve closed.
Recognizes this results in a primary system discharging into Secondary CRS Containment until SCRAM is reset or valve is closed.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 19 of 23
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 9 Event
Description:
RHR Drywell Spray Valve fail to auto close on low DW pressure.
Time Position Applicants Action or Behavior NOTE to Examiners: During performance of Drywell Sprays using procedure 2.2.69.3 during execution of EOP 3A if the operator fails to recognize DW Spray valves have lost power the valves will fail to close resulting in negative DW pressure and challenging PC Integrity.
Critical Secure RHR Loop A drywell sprays or lower Loop B sprays prior to Task Drywell Pressure reaching negative pressure.
Booth As drywell pressure is lowered to ~5 psig, insert Trigger 5 to de-Operator energize MO26A and MO-31A open.
Recognizes that RHR-MO-26A, DRYWELL SPRAY OUTBD THROTTLE VLV and RHR-MO-31A, DRYWELL SPRAY INBD VLV will not close while spraying the Drywell.
If RHR Loop B also being used to spray the drywell, isolate drywell BOP sprays in that loop to maintain drywell pressure above 2 psig.
OR Secure all RHR Loop A pumps.
Report status to the CRS Acknowledges and directs the drywell pressure maintained positive.
CRS When Drywell Pressure is being controlled and RPV level is within band, stop the scenario as directed by the lead examiner.
END OF SCENARIO Page 20 of 23
Appendix D Required Operator Actions Form ES-D-2 Simulator Setup Initialize the simulator in Protected IC 232.
Triggers and Malfunctions E4 - RR10A, RR #1 seal failure, 100% severity with a 5:00 ramp time.
RR11A, RR #2 seal failure, 100% severity with a 15:00 ramp time.
RR31A, RR Suction Line Break, 3.5% severity with a 10:00 ramp time. 6 minute TD.
RR50A RR Pump A High Vibration, 50% severity.
E5 - RH23a and RH19a Loop A DW Spray Valves fail open.
E6 - None E7 - None E9- DMF RD01a (Allows SDIV drain valve to close)
E13- None Trgset 9 "zdirpssws10[1]==1" (SDIV control switch to ISOL)
Trgset 13 "zdihpcisws20[4]==1" (HPCI Aux Oil Pump control switch to START)
RD01a, 100% (Open) South SDV Drain Valve Fails to Close (Active)
RP12 PCIS Group 3 failure (Active)
HP 12, HPCI oil discharge line rupture (15 second time delay) (Active)
IA05 100% with a 2 minute ramp.
Remotes E5- rh19a, RHR-MO-26a control power failure rh23a, RHR-MO-31a control power failure E10- SW04b RHRSW Pump B trip.
E11- SW04d RHRSW Pump D trip.
Overrides None Panel Set-up
- Ensure HPCI Test displayed on SSSP.
- Ensure Tendamatic plaque labeled B-A-C
- Ensure PMIS IDTs are blank.
- Place the Shutdown EOL Rod Sequence Book on Panel 9-5.
- Ensure Recirculation Controllers are selected to P Procedures Needed 6.HPCI.103 - Completed up to step 4.13, then steps 4.14 and 4.15 are complete.
Tags Hung None Page 21 of 23
Appendix D Required Operator Actions Form ES-D-2 Parameter Monitoring:
Monitor RPV Power, Pressure and Level, Drywell Pressure Page 22 of 23
Appendix D Required Operator Actions Form ES-D-2 Turnover Sheet:
Plant Status: 100% power, EOL Risk: Green Activities in Progress:
RHR Heat Exchanger B was vented at the end of the previous shift in preparation for performing HPCI surveillance test.
6.HPCI.103 - procedure completed up to step 4.13, steps 4.14 and 4.15 are complete.
LCOs in effect: None Equipment out of service: None Activities for the Shift:
- Reduce power to 90% for HPCI Test
- Place B Loop of RHR in Suppression Pool Cooling.
- Perform 6.HPCI.103 Test
- Return to 100% power following HPCI test Page 23 of 23
Appendix D SCENARIO OUTLINE Form ES-D-1 Facility: Cooper Nuclear Station Scenario No.: 3 Op-Test No.: ___1____
Examiners: ____________________________ Operators: _____________________________
Initial Conditions: _4%, BCL, power, plant startup in progress.______
Turnover: Procedure 2.1.1, Steps 4.22 and 5.36 are completed, 2.2.77 Attachment 1, Step 1.14 is complete, 2.2.28.1 Step 5.14 is complete. Fuel is being de-channeled on the refueling floor, No Tech Specs Limitations in effect. Reactor Coolant samples (1xE-3 Micro-Curies / CC) indicate higher than normal gross activity level for this point in a startup. Site Management and Reactor Engineering have indicated the startup can continue normally._PRA risk is green. Continue plant startup.
Event Malf. No. Event Event No. Type* Description 1 N/A N, R Continue startup using control rods (ATC) 2 NM05A C IRM power supply failure (ARP 9-5-1/D-7)
(ATC)
TS Tech Specs LCO 3.3.1.1, Reactor Protection System (RPS)
(SRO) Instrumentation 3 SW01d C Service Water Pump D Trip (ARP B-3/B-7)
(BOP)
N/A Tech Spec LCO 3.7.2 Service Water (SW) System and TS Ultimate Heat Sink (UHS) for number of Operable SW (SRO) Pumps.
4 RD03d C Control Rod Drifts IN (2.4 CRD)
(ATC)
N/A Tech Spec LCO 3.1.5 for Inoperable Control Rod.
TS (SRO) 5 HP05,CR I HPCI Inadvertent Initiation / Fuel Failure (2.4CSCS) 01, CR03 (BOP) 6 HP06, M (All) LOCA - Steam line break into Secondary Containment (EOP-HP09, © 5A, 2.4 OG, 5.1RAD)
HP15 R SCRAM (2.1.5)
(ATC) 7 N/A M© Emergency Depressurization (>2 above Max Safe) EOP-2A (BOP) 8 FW28B C Reactor Feedpump fails to trip on high level (ATC) 9 PC18a/b I SGT Fans A & B fail to auto start (BOP)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specifications, (©) CT Page 1 of 24
Appendix D SCENARIO OUTLINE Form ES-D-1 Initial Conditions: 4%, BCL, power, plant startup in progress.
Turnover:
Procedure 2.1.1, Steps 4.22 and 5.36 are completed, 2.2.77 Attachment 1, Step 1.14 is complete, 2.2.28.1 Step 5.14 is complete, LCOs and Logs are complete for change to MODE 1.
Fuel is being de-channeled on the refueling floor, No Tech Specs Limitations in effect. Reactor Coolant samples (1xE-3 Micro-Curies / CC) indicate higher than normal gross activity level for this point in a startup. Site Management and Reactor Engineering have indicated the startup can continue normally. PRA risk is green. Continue plant startup.
==
Description:==
A startup is in progress following a refueling outage. Reactor Power is approximately 4% and the intention is to raise power. Reactor Coolant activity is above normal. The ATC continues the plant startup using control rods using procedure 2.1.1, Startup and procedure 10.13, Control Rod Movement Sequence.
During control rod withdrawal, one IRM power supply fails requiring the ATC to bypass the IRM per ARP 9-5-1/D-7. The SRO addresses Tech Spec 3.3.1.1, Reactor Protection System (RPS)
Instrumentation and declares IRM B inoperable. Potential LCO 3.3.1 is logged. The half reactor scram is reset per Procedure 2.1.5.
The BOP operator responds to a Service Water Pump Trip per ARP B-3/B-7 and responds by starting another pump.
The SRO addresses Tech Spec LCO 3.7.2 Service Water (SW) System and Ultimate Heat Sink (UHS) for number of Operable SW Pumps and determines 30 day LCO entry is required per 3.7.2 and 7 day LCO entry is required per 3.8.1 with DG-1 declared inop.
One Control Rod drifts in due to a leaking outlet scram valve and the ATC responds per 2.4CRD to fully insert the Control Rod using the emergency in switch. The control rod is fully inserted and the SRO enters Tech Spec 3.1.6 because GPWS is not met. The control rod is declared INOP and de-activated. The SRO addresses Tech Spec LCO 3.1.3 for Inoperable Control Rod.
An Inadvertent HPCI Actuation and Injection occurs resulting in a power excursion that results in some Fuel Failure. The BOP Operator responds per 2.4CSCS and secures HPCI. During the process of tripping HPCI the HPCI Steam line breaks in Secondary Containment. The SRO enters EOP 5A due to high Reactor Building temperature and radiation. EOP 5A provides direction to isolate systems discharging into the area As area temperatures and radiation continue to rise the SRO directs the ATC to SCRAM the reactor per 2.1.5, prior to commencing emergency depressurization, due to the inability to isolate the HPCI steam line break and follows up by entering 5.1 RAD and 2.4 OG.
The crew will be able to anticipate emergency depressurization but will have to close the MSIVs due to MSL HI-HI RAD. Once two or more areas are above Max Safe the SRO will direct the BOP operator to Emergency Depressurize the Reactor per EOP 2A prior to exceeding 312oF anywhere in the reactor building.
Page 2 of 24
Appendix D SCENARIO OUTLINE Form ES-D-1 The SGT fans fail to auto start and the BOP operator must manually start them to prevent the secondary containment pressure from becoming positive and a potential radioactivity release.
During recovery of reactor water level using Feedwater the remaining Reactor Feedpump fails to trip on high level requiring the BOP operator to control RPV level using ECCS Systems.
The scenario ends when the RPV level has been restored to the normal range following emergency depressurization and the SGT system has restored negative pressure in the secondary containment.
Page 3 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event
Description:
Continue startup using control rods Time Position Applicants Action or Behavior Performs a Reactivity Briefing CRS Directs the ATC to continue startup.
NOTE to Examiners: Reactivity Briefing is normally conducted in briefing room during turnover prior to entering the simulator.
Continue to withdrawal rods using procedure 10.13 starting at step 4.2.1 - Proceed with consecutive step order on Attachment 5 in the Control Rod Sequence Package.
ATC 4.2.3 The Operator shall initial in the "PERFORMED BY" column on Attachment 5.
4.2.2 The Operator or Concurrent Verifier shall place a check mark in the DESIRED ROD SELECTED block for the selected rod.11 4.2.3 The Operator shall initial in the "PERFORMED BY" column on BOP Attachment 5.
4.2.4 The Concurrent Verifier shall initial in the "CONCURRENT VERIFICATION" column on Attachment 5.11 END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 4 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event
Description:
IRM power supply failure (ARP 9-5-1/D-7)
Time Position Applicants Action or Behavior When directed by the lead examiner insert Trigger 6 (NM05b IRM Booth Operator Power Supply Failure)
Respond to Annunciators 9-5-1/D-7, IRM RPS CH B UPSCALE TRIP OR INOP.
9-5-2/A-3, RX SCRAM CHANNEL B 9-5-2/b-1, NEUTRON MONITORING TRIP Refers to INSTRUMENT OPERATING PROCEDURE 4.1.2,INTERMEDIATE RANGE MONITORING SYSTEM Visually inspects the IRM B cabinet and recognizes the white INOP light is illuminated and the outputs are downscale indicating a power supply failure.
ATC Bypasses IRM B using joystick on panel 9-5 Verifies remaining IRMs indications have normal reading for the reactor power.
Resets RPS B trip per Procedure 2.1.5, Section 4.
- 4. HALF SCRAM RESET 4.1 Place REACTOR SCRAM RESET switch to Group 1 and 4, Group 2 and 3, then back to NORM.
4.2 Ensure eight SCRAM GROUP lights (Panels 9-15 and 9-17) or SCRAM INDICATIONS GROUP A and GROUP B lights are on.
Booth If requested as I&C to investigate the IRM B power supply, respond that you will prepare a troubleshooting request and Operator investigate.
Refers to TECH SPEC LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation.
CRS LCO 3.3.1.1, Table 3.3.1.1-1, Functions 1a and 1b.
Declares IRM B Inop.
Page 5 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event
Description:
IRM power supply failure (ARP 9-5-1/D-7)
Time Position Applicants Action or Behavior END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 6 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
Service Water Pump D Trip (ARP B-3/B-7)
Time Position Applicants Action or Behavior Booth When directed by lead examiner, insert Trigger 4 (Service Water Pump D Trip).
Operator Responds to Annunciator B-3/B-7 Service Water Pump D Trip 1.2 Maintain SW System pressure >38psig 1.2.1 Place available non-running Service Water Pump in MAN.
BOP 1.2.2 Start available Service Water pump(s) as necessary.
1.3 Ensure MODE SELECTOR switches are aligned per procedure 2.2.71.
Dispatch an Operator to investigate the pump trip.
When asked to investigate the Service Water Pump D Trip, report the Booth motor is very hot.
Operator If asked to investigate the local SW Pump 4160 V breaker, report the 51X overload/ground relay has tripped for the pump.
Refer to Tech Spec 3.7.2.A.1 Declare D Service Water Pump Inoperable.
30 Day LCO applies, and CRS Refer to Tech Spec 3.8.1, declare the Diesel Generator 1 inoperable, with a seven day LCO.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 7 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event
Description:
Control Rod Drifts IN (2.4 CRD)
Tech Spec LCO 3.1.5 for Inoperable Control Rod.
Time Position Applicants Action or Behavior Booth When directed by the lead examiner, activate RD03d, Rod 18-39 Drift in (Trigger 1)
Operator Respond to annunciator 9-5-1/C-4, ROD DRIFT.
ATC Determine that rod 18-39 is drifting inward.
Verify no other rod drift indications.
Enter 2.4CRD, Attachment 4, Single Rod Drift IN.
Direct rod driven in with Emergency IN Switch.
CRS Contact the WCC for troubleshooting plan.
Contact Reactor Engineering.
ATC Insert rod 18-39 using Emergency IN switch to full in.
ROLE PLAY: As Reactor Engineer, when contacted by the CRS regarding the control rod drifting in, tell them if they determine the rod is INOP they can continue with the Booth startup.
Operator ROLE PLAY: If contacted as the Work Control Center for the rod drifting in, tell them you will put a team together and develop a troubleshooting plan.
ROLE PLAY: When contacted by the control room as the NLO to isolate Booth HCU 18-39, reply you will isolate the HCU and tag it.
Operator THEN: wait 5 minutes then delete malfunction RD03d.
Refer to Tech Spec 3.1.6 and determine Condition A applies.
CRS Refer to Tech Spec 3.1.3 and determine Condition C applies.
Declare the Control Rod Inoperable and direct it to be deactivated.
Call NLO and direct them to stop by the WCC to get a clearance and to ATC isolate control rod 18-39 and tag it.
Page 8 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event
Description:
Control Rod Drifts IN (2.4 CRD)
Tech Spec LCO 3.1.5 for Inoperable Control Rod.
Time Position Applicants Action or Behavior END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 9 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event
Description:
HPCI Inadvertent Initiation / Fuel Failure (2.4CSCS)
Tech Spec 3.5.1, ECCS Operating Time Position Applicants Action or Behavior Booth When directed by Lead Examiner, Insert Trigger 3 (HP05, HPCI Operator Inadvertent Initiation and HP06 HPCI steam line break)
Check Reactor Level and Drywell pressure.
ATC Verify there are no valid start signals for HPCI.
Respond to inadvertent initiation of HPCI using 2.4CSCS and 3.1 IF HPCI initiated, THEN perform following:
3.1.1 Ensure AUXILIARY OIL PUMP control switch in START.
3.1.2 Press and hold TURBINE TRIP button.
BOP 3.1.3 AFTER turbine stops, THEN place AUXILIARY OIL PUMP in PULL-TO-LOCK.
3.1.4 Release TURBINE TRIP button.
Inform the CRS that HPCI is INOP.
Direct HPCI tripped per 2.4CSCS CRS If HPCI is not shutdown prior to annunciator 9-3-1/A-9 (Reactor Bldg High Rad) alarming then enter EOP5A due to high area radiation.
Refers to Tech Spec 3.5.1, ECCS Operating, Action C requires verification CRS of RCIC operable within one hour and determines Action C.2 applies requiring restoring HPCI to operability within 14 days.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 10 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event
Description:
LOCA - Steam line break into Secondary Containment Time Position Applicants Action or Behavior NOTE to Examiners: Malfunctions HP09, and HP15 (HPCI failure to automatically isolate) and CR01 CR03 (fuel element failure) are ACTIVE.
Crew recognizes rising temperature and radiation levels in the reactor CREW building and diagnose a break in the HPCI Steam Line.
Enters EOP5A, direct actions as follows:
Direct HPCI to be isolated.
Rad Release Isolate all primary systems discharging into areas outside primary and secondary containments except systems required to support EOPs (RR-2)
Before offsite gaseous radioactivity release rate reaches that which requires a General Emergency BUT ONLY IF primary system is discharging into area outside primary and secondary containments Emergency Depressurize the reactor (RR-3)
Secondary Containment Control When Reactor Bldg. exhaust plenum radiation level exceeds 10 mr/hr CRS ensure:
- isolation of Rx Bldg. HVAC
- initiation of SGT When Reactor Building HVAC isolates AND Rx Bldg. exhaust plenum radiation level is below 10 mr/hr, then restart Rx Bldg HVAC (defeat high drywell pressure and low RPV water level isolation interlocks if necessary, EOP 5.8.20) (SC-1)
Monitor and Control TEMPERATURE, RADIATION, & WATER LEVEL BEFORE any secondary containment parameter reaches its maximum normal operating value:
- Temperatures (TABLE 9)
- Radiation (TABLE 10)
- Water levels (TABLE 11)
Isolate all primary systems discharging into areas outside primary and Page 11 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event
Description:
LOCA - Steam line break into Secondary Containment Time Position Applicants Action or Behavior secondary containments except systems required to support EOPs (SC-10)
BEFORE any secondary containment parameter reaches its maximum safe operating value:
- Temperatures (TABLE 9)
- Radiation (TABLE 10)
- Water levels (TABLE 11) with a primary system discharging into secondary containment enter EOP 1A, SCRAM the reactor.
Take action in EOP5A as follows:
BEFORE any secondary containment parameter reaches its maximum safe operating value:
- Temperatures (TABLE 9)
- Radiation (TABLE 10)
- Water levels (TABLE 11)
BOP/ATC 1. Start all reactor building quad room coolers.
- 2. Open REC cooling water supply (MO-711/714) to provide cooling to the quad room coolers.
Respond to Annunciator 9-3-1/A-9 REACTOR BLDG HIGH RAD
- 1. Evacuate plant personnel from the area Attempt to isolate HPCI.
BOP Report to CRS that HPCI will not Isolate.
Send NLO to ASD Room to Isolate HPCI.
If sent to the ASD Room to attempt to isolate HPCI:
Override Alarm 9-3-3/G-5 ASD ROOM DOOR OPEN to ON Booth Then Override Alarm 9-3-3/F-5, ASD SWITCH POSITION Operator ABNORMAL to ON Then report you can NOT get control of the valves from the ASD Room.
DELETE the overrides on the alarms.
Enter 5.1RAD and 2.4OG on notification of High Reactor Bldg. Radiation.
CRS Direct actions.
Enter EOP1A and direct a reactor Scram.
With a primary system discharging into secondary containment Critical through an un-isolable break, SCRAM the reactor per EOP 5A and EOP Task 1A prior to commencing Emergency Depressurization.
Page 12 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event
Description:
LOCA - Steam line break into Secondary Containment Time Position Applicants Action or Behavior Perform Scram actions using procedure 2.1.5 Attachment 1.
Perform Attachment 1 mitigating task scram actions of 2.1.5 as follows:
1.2 Place REACTOR MODE switch to REFUEL.
1.3 IF reactor power > 3%, THEN perform following:
1.3.1 Place REACTOR MODE switch to SHUTDOWN.
1.3.2 Initiate ARI.
Perform Attachment 2 Reactor Power Control of 2.1.5 as follows:
1 REACTOR POWER CONTROL 1.1 Ensure REACTOR MODE switch is in SHUTDOWN.
ATC 1.2 Verify all SDV vent and drain valves are closed.
NOTE - RR pump(s) will be tripped if on Normal Transformer or if ARI/RPT has automatically initiated.
1.3 Ensure operating RR pumps have run back to 22% speed.
NOTE - Steps 1.4 and 1.5 may be performed concurrently.
1.4 Verify all control rods are fully inserted.
1.4.1 If necessary, insert control rods as directed by CRS.
1.5 Observe nuclear instrumentation and perform following:
1.5.1 Insert SRM detectors.
1.5.2 Insert IRM detectors.
1.5.3 Change APRM recorders to IRMs.
Page 13 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event
Description:
LOCA - Steam line break into Secondary Containment Time Position Applicants Action or Behavior 1.5.4 Range IRMs on scale.
Check reactor power is lowering.
Perform action of 5.1RAD, BUILDING RADIATION TROUBLE 4.2 Notify Plant personnel to clear affected area via gaitronics.
Perform actions of 2.4OG, OFF-GAS ABNORMAL Verify automatic actions
- 2. AUTOMATIC ACTIONS 2.1 Standby off-gas dilution fan starts on low dilution flow.
2.2 A 5 minute time delay on low dilution flow or 15 minutes of continuous Alarm 9-4-1/C-4, OFFGAS TIMER INITIATED, causes an off-gas isolation signal.
2.3 An off-gas isolation signal causes following:
2.3.1 OG-AO-254, OG SYSTEM ISOLATION, closes.
2.3.2 AOG-AO-902, AOG RETURN, closes.
NOTE - 50 to 60 psig on AR-12AV and OG-13AV air regulators indicates BOP valves closed.
2.3.3 OG-AO-13, OFF-GAS FILTERS A & B DRAIN, closes.
2.3.4 AR-AO-12, 30 MINUTE HOLDUP PIPE DRAIN, closes.
2.3.5 OWC Injection System trips.
- 3. NA
- 4. Subsequent Actions:
4.1 Record date and time.
4.2 NA 4.3 IF off-gas isolation has occurred, THEN place OWC-SW-ENABLE, OWC INJECTION SYS ENABLE, to SHUTDOWN (PANEL A).
4.3.1 Complete securing OWC Injection System per Procedure 2.2.98 when conditions permit.
4.4 Concurrently perform Attachment 1, Off-Gas System High Radiation Attachment 1
- 1. OFF-GAS SYSTEM HIGH RADIATION:
Page 14 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event
Description:
LOCA - Steam line break into Secondary Containment Time Position Applicants Action or Behavior 1.1 Lower reactor power per Procedure 2.1.10 to prevent off-gas timer from timing out or to clear Annunciator 9-4-1/C-4, OFFGAS TIMER INITIATED.
1.2 IF off-gas isolation is immediately desired, THEN at Panel 9-02, place OFFGAS TIMER switch to CLOSE.
1.3 IF fuel cladding has not been confirmed lost per EPIP 5.7.1, Emergency Classification, THEN request Chemistry obtain isotopic analysis of off-gas stream.
1.4 IF Off-Gas System automatically isolates or is manually isolated due to high-high radiation, THEN:
1.4.1 SCRAM and enter Procedure 2.1.5.
1.4.2 Close MSIVs and MSIV drains.
1.4.3 Ensure OFFGAS TIMER switch on Panel 9-02 is in CLOSE.
1.4.4 Ensure following valves are closed:
1.4.4.1 RHR-920MV, AOG STEAM SUPPLY VALVE (PNL 9-3).
1.4.4.2 RHR-1485MV, AOG STEAM BYP THROTTLE VLV (PNL 9-3).
1.4.4.3 RHR-921MV, AOG STEAM SUPPLY VALVE (PNL 9-3).
1.4.4.4 AOG-AO-902, AOG RETURN (VBD-K).
1.4.4.5 OG-AO-254, OFFGAS SYSTEM ISOLATION (VBD-K).
1.4.5 Remove SJAEs from service per Procedure 2.2.55.
1.4.6 Ensure gland steam exhauster running.
1.4.7 NA 1.4.8 NA 1.4.9 NA 1.4.10 Monitor ERP gas activity levels.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
Page 15 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event
Description:
Emergency Depressurization (>2 above Max Safe) EOP-2A Time Position Applicants Action or Behavior NOTE to Examiners: This event is a continuation of the previous event.
Enter 5.2FUEL and direct actions as follows:
4.6 IF valid MAIN STM LINE HI HI RAD (9-4-1/A-4) alarm is actuated and reactor is shut down, THEN close MSIVs and MSL drain valves.
CRS 4.7 Direct Chemistry to sample reactor coolant activity.
4.8 Notify Reactor Engineering and follow their recommendations per Procedure 10.31.
Close MSIVs and MSL Drains BOP With a primary system discharging into secondary containment through an un-isolable break, execute Emergency Depressurization Critical when Maximum Safe Operating Values are exceeded in two or more Task areas for the same parameter per EOP2A prior to exceeding 3120F anywhere in the reactor building.
EOP1A When CRS determines the second containment area temperature is going to CRS exceed MAX SAFE temperature of 195°F, anticipate Emergency Depressurization and direct BOP to fully open main turbine bypass valves.
When directed fully open main turbine bypass valves per Hard Card. (Panel B DEH HMI)
3.2 Press MANUAL button and check it backlights yellow.
3.3 On BYPASS VALVE POSITION control, use UP/DOWN, JOG UP/JOG DOWN and FAST/SLOW controls to adjust BYPASS Page 16 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event
Description:
Emergency Depressurization (>2 above Max Safe) EOP-2A Time Position Applicants Action or Behavior VALVE POSITION to desired value.
EOP5A (SC-14)
BEFORE any 2 secondary containment parameters reach their maximum safe operating value:
- Temperatures (TABLE 9)
- Radiation (TABLE 10)
- Water levels (TABLE 11) with a primary system discharging into secondary containment Emergency Depressurize the reactor.
EOP2A (RC/P-12)
CRS Rapidly depressurize RPV (disregard cooldown rate)
(RC/P-13) NA (RC/P-14)
WHEN shutdown cooling RPV pressure interlock clears (70 psig) AND further cooldown is required (RC/P-15)
Cool down to cold shutdown conditions with shutdown cooling (use only RHR pumps not required to maintain RPV water level above +3 in.)
CRS Request torus water level before ordering SRVs opened for emergency depressurization.
Report torus water level to CRS.
BOP Open 6SRVs with control switches.
BOP Report RPV pressure as it lowers.
Page 17 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event
Description:
Emergency Depressurization (>2 above Max Safe) EOP-2A Time Position Applicants Action or Behavior Restore RPV Level using Low Pressure ECCS Systems (RHR, Core Spray)
BOP to normal range.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
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Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 8 Event
Description:
Reactor Feedpump fails to trip on high level Time Position Applicants Action or Behavior NOTE to Examiners: Following Emergency Depressurization reactor water level will swell resulting in a Reactor Feed Pump (RFP) Trip setpoint and the RFP will not trip automatically.
Recognizes that reactor water level has exceeded the trip setpoint for the ATC running reactor Feedpump and the reactor Feedpump should have tripped.
Press TURBINE TRIP pushbutton on benchboard A.
When requested to investigate the Reactor Feedpump for reasons it Booth may not have tripped when required, respond that there is nothing Operator abnormal around the Reactor Feedpump.
Acknowledges the Reactor Feedpump did not trip automatically and it has been manually tripped.
CRS Directs the BOP Operator to maintain reactor water level using ECCS Systems.
BOP Maintains Reactor Water Level using Core Spray, and/or RHR.
END OF EVENT Notes Proceed to the next event at direction of the lead examiner.
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Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 9 Event
Description:
SGT Fans A & B fail to auto start Time Position Applicants Action or Behavior NOTE to Examiners: Malfunctions PC18a and PC18b, SGT Fans Fail to Auto Start are ACTIVE.
Recognizes the SGT fan failed to auto start upon a group 6 isolation signal and SGT inlet valves SGT-AO-249 (250) and outlet valves SGT-AO-251 (252) did not auto open.
Informs CRS that SGT fans did not start.
BOP Places the Fan Control Switches to RUN to start both Fans.
Ensures both Inlet and Outlet valves open following start of fans.
Directs BOP to place the SGT Fan switches to RUN and ensure system is CRS maintaining negative pressure in the reactor building.
Booth If requested to investigate the SGT Fans for reasons they may not Operator have started, respond you will notify maintenance to investigate.
END OF EVENT Notes Page 20 of 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 9 Event
Description:
SGT Fans A & B fail to auto start Time Position Applicants Action or Behavior When the RPV has been depressurized and RPV level is has been restored within band, stop the scenario as directed by the lead examiner.
END OF SCENARIO Page 21 of 24
Appendix D Required Operator Actions Form ES-D-2 Simulator Setup Initialize the simulator in IC 10 (BOL) (Protected IC 233)
Triggers and Malfunctions E4 - SW01d, Trip, Service Water Pump D trip E1 - RD03d, Severity 22%, Control rod 18-39 drifts in.
E3 - HP05, Inadvertent initiation CR01, TD 5:00, Severity 1%
CR03, TD 6:00, Severity 100%, Ramp 10:00 minutes HP06, HPCI steam line break, Severity 5%, Ramp 10:00 minutes E6 - NM05b, IRM B power supply failure PC18a (Active) Standby Gas Treatment train A failure to start.
PC18b (Active) Standby Gas Treatment train B failure to start.
FW28a and FW28b (Active), RFP fails to trip on high water level.
HP09 (Active) HPCI fails to automatically isolate.
HP15 (Active) HPCI fails to automatically isolate on low steam supply pressure.
Overrides
- zdihpcisws2[2] Control Switch for HPCI-MO-16, OPEN (Active)
- zdihpcisws1[2] Control Switch for HPCI-MO-15, OPEN (Active)
- zdihpciswmo15[2] Control Switch for HPCI-MO-15 (ASD ROOM), OPEN (Active)
- zdihpciswmo16[2] Control Switch for HPCI-MO-16 (ASD ROOM), OPEN (Active)
- zdihpcisws32[1] HPCI Manual Isolation Switch, OFF (Active)
- an:p1641, HPCI LOGIC INITITATED Alarm, OFF(Active)
Panel Set-up
- Ensure the following breakers are in Normal After Trip position:
- a. 1CN
- b. 1DN
- c. 1AN
- d. 1BN
- Place the Breakers must be cycled tags on the following breakers:
- e. 1CN
- f. 1DN
- g. 1AN
- h. 1BN
- Place PC-PIC-513 in manual and shut and lower Containment Pressure to 0.
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Appendix D Required Operator Actions Form ES-D-2 Procedures Needed
- Procedure 2.1.1 (2 Copies) with steps 4.22 and 5.3.6 completed.
- Procedure 2.2.77, Attachment 1, Step 1.14 complete.
- Procedure 2.2.28.1 Step 5.14 completed.
Tags Hung
- Mark up boards and ensure tag reflects CREF is on Division I.
Parameter Monitoring:
Monitor RPV Pressure, Average Torus Water Temperature and Torus Water Level (HCTL
&BIIT)
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Appendix D Required Operator Actions Form ES-D-2 Turnover Sheet:
Plant Status: The plant is at 4% reactor power during a startup following refueling. Procedure 2.1.1, Steps 4.22 and 5.36 are completed, 2.2.77 Attachment 1, Step 1.14 is complete, 2.2.28.1 Step 5.14 is complete, LCOs and Logs are complete for change to MODE 1.
Fuel is being de-channeled on the refueling floor, Reactor Coolant samples (1xE-3 Micro-Curies / CC) indicate higher than normal gross activity level for this point in a startup. Site Management and Reactor Engineering have indicated the startup can continue normally. Continue plant startup.
Risk: Green Activities in Progress: Fuel is being de-channeled on the refueling floor.
LCOs in effect: No Tech Specs Limitations in effect.
Equipment out of service: None Activities for the Shift: Continue plant startup.
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