ML13160A003
| ML13160A003 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/18/2013 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Ameren Corp, Union Electric Co |
| References | |
| 50-483/13-003, ES-301, ES-301-1 50-483/OL-13 | |
| Download: ML13160A003 (253) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 3/18/2013 Examination Level: RO Operating Test Number: 2013301, Rev 2 Administrative Topic Type Describe activity to be performed (see Note) Code*
Calculate a Shutdown Margin (A1) Conduct of Operations R, N 2.1.37 (4.3) Knowledge of procedures, guidelines, or limitations associated with reactivity management.
Calculate Volume of Water to Transfer Between RWST and Spent Fuel Pool.
(A2) Conduct of Operations R, N 2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves, tables, etc.
Determine Amperage Limits for 480 VAC Safety Related busses.
(A3) Equipment Control R, N 2.2.37 (3.6) Ability to determine operability and/or availability of safety related equipment.
Radiation Control N/A Determine Correct Functional Restoration Guideline (FRG) Procedure Implementation.
(A4) Emergency R, N 2.4.14 (3.8) Knowledge of general guidelines for EOP Procedures/Plan usage.
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)
SUMMARY
A1 This is a new JPM. The applicant will calculate an at power Shutdown Margin.
The plant computer is not available and the calculation must be manually performed.
A2 This is a new JPM. The applicant will calculate the amount of water required to test the Spent Fuel Pool (SFP) high level alarm. The water will come from the RWST and the candidate must determine if there is sufficient volume in the RWST to perform the SFP test without lowering below the Technical Specification low level limit.
A3 This is a new JPM. The applicant will review planned maintenance which requires load centers NG01 and NG03 to be cross-connected. The applicant will be required to determine what equipment can be started on the cross-connected load centers without overloading the buses.
A4 This is a new JPM. The applicant will review the Critical Safety Functions (CSFs) following a plant event. Upon completion of this review, the applicant will report to the CRS that the highest priority CSF that needs to be addressed is Core Cooling and that FR-C.2, Response to Degraded Core Cooling should be implemented.
Rev 2
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 3/18/2013 Examination Level: SRO Operating Test Number: 2013301 Rev. 2 Administrative Topic Type Describe activity to be performed (see Note) Code*
Evaluate Conditions for Restart of Refueling Preshuffle.
(A5) Conduct of Operations R, M 2.1.35 (3.9) Knowledge of the fuel-handling responsibilities of SROs.
Review Shiftly Logs (A6) Conduct of Operations R, N 2.1.18 (3.8) Ability to make accurate, clear, and concise logs, records, status boards, and reports.
Perform a Risk Assessment during Shutdown Conditions.
(A7) Equipment Control R, N 2.2.18 (3.9) Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.
Determine Estimated Dose and Make Shielding Recommendation.
(A8) Radiation Control R, D 2.3.12 (3.7) Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Initiate RERP Implementation to Include Event Classification and Initial Offsite Notification.
(A9) Emergency R, D 2.4.41 (4.6) Knowledge of the emergency action level Procedures/Plan thresholds and classification.
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)
SUMMARY
A5 This is a bank JPM modified from the 2011 Turkey Point Exam. The applicant will be given a set of plant conditions and OOS equipment associated with recommencing shuffling of irradiated fuel assemblies in the Spent Fuel Pool. The applicant will evaluate the given conditions as to whether irradiated fuel can be moved. Of the conditions provided to the applicant, four items would prevent the movement of irradiated fuel assemblies in the Spent Fuel Pool.
A6 This is a new JPM. The applicant will be given 10 pages of a set of manual Control Room logs that have been taken due to the unavailability of Auto Tour.
The applicant will review the logs and inform the RO of any changes or plant issues that need to be addressed based on this review. There are seven issues to be identified on the logs; the applicant must identify at least six of the seven issues to successfully complete this JPM.
A7 This is a new JPM. The applicant will perform a Shutdown Safety Assessment for Power Availability IAW EDP-ZZ-01129 based on a set of given conditions.
After this review, the applicant will have determined that there are 5 credit points available for Power Availability and the Risk Assessment condition color is Green.
A8 This is a bank JPM from the 2012 Ft. Calhoun Exam. The applicant will calculate the total dose for a maintenance job in the Auxiliary Building, with and without temporary shielding installed. The applicant will make a recommendation of whether to request temporary shielding for the job or to perform the job without temporary shielding installed. The addition of shielding reduces the total dose for the job; therefore the applicant should recommend temporary shielding be installed.
A9 This is a Callaway Bank JPM [SRO-RER-02-A119J (TC)]. The applicant will be given a set of plant conditions and will implement the Radiological Emergency Response Plan (RERP) to classify the event within 15 minutes (Time Critical) and then make the initial notifications to offsite agencies within 15 minutes (Time Critical).
Rev 2
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A1, Rev 2 KSA No: GEN 2.1.37 Revision: Feb 2013 KSA Rating: 4.3/4.6 Job
Title:
RO Task
Title:
Knowledge of procedures, guidelines, or limitations associated with reactivity management: Calculate a Shutdown Margin.
Validation Time: 35 minutes Learning Objective: T61.0110, LP SS-08, Obj D, Perform shutdown margin calculation while at power The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts: OSP-SF-00001, Shutdown Margin Calculations, Rev 40 Core Operating Limits Report (COLR), Rev 1, Pages 1-5 Curve Book Table 1-8 WINPCNDR Handouts Calculator
References:
OSP-SF-00001, Shutdown Margin Calculations, Rev 40 Core Operating Limits Report (COLR), Rev 1 Plant Curve Book
JPM NO: A1, Rev 2 Initial Conditions: The plant is at 3565 MWt, as indicated on REU1118, with Control Rods D @ 215 steps and RCS Boron Concentration at 750 ppm.
There are no inoperable rods.
Effective Full Power Days (EFPD) is at 270 (12000 MWD/MTU).
There is a question about whether the Rod Insertion Limit (RIL) monitor is functional.
Initiating Cues: Due to the concerns of the RIL monitor, the Control Room Supervisor directs you to perform a Shutdown Margin Calculation for the current plant conditions IAW OSP-SF-00001, Shutdown Margin Calculations.
He directs you to perform the calculation IAW Step 6.11.
The PC program OSPSF1 is currently being revised by reactor engineering and is not available.
When complete, inform the CRS of what the calculated value is for the Shutdown Margin (SDM) and if the SDM is acceptable.
Task Standard: Upon completion of this JPM, the Applicant will have determined that the Shutdown Margin is acceptable with a value of (-)2348 in accordance with the answer key.
START TIME:
STOP TIME:
PAGE 1 of 7
JPM NO: A1, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Obtain a verified working Applicant obtained working copy of copy of OSP-SF-00001 OSP-SF-00001 Comments:
NOTE: If requested, provide applicant with copies of WinPCNDR handouts.
S U
- 2. At power SDM is normally Applicant read note maintained by ensuring rods Comments:
are above the rod insertion limits. At power SDM calculation is normally performed only when one or more rods are inoperable, misaligned, or not within the insertion, sequence or overlap limits.
Note prior to Step 6.11.1 S U
- 3. If desired, use PC program OSPSF1 is not available - given in OSPSF1 to calculate SDM in initiating cues Comments:
lieu of completing this section Applicant proceeded to Step 6.11.2 Step 6.11.1 S U
- 4. Initiate Attachment 4 and Applicant initiated Attachment 4 record all data for this Comments:
section on Attachment 4 Step 6.11.2
- CRITICAL STEP PAGE 2 of 7
JPM NO: A1, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 5. Record the indicated power Applicant recorded the indicated level as follows: power as 100% on Attachment 4 Comments:
- a. If power is greater than 20%, obtain power level from one of the following:
Computer point REU1118 The highest power range meter
- b. If power is less than or equal to 20% power, obtain power from the highest delta T indication Step 6.11.3 S U
- 6. This calculation assumes Applicant read note that PZR boron Comments:
concentration is equal to or greater than RCS boron concentration.
Note prior to Step 6.11.4 S U
- 7. Record to current critical Applicant recorded current critical boron concentration boron concentration as 750 on Comments:
Attachment 4 Step 6.11.4 S U
- 8. Record the total power Applicant recorded the total power defect for the associated defect for the associated power level Comments:
power level and burnup from and burnup from Curve Book Table Curve Book Table 1-8, 1-8,Section II as 1808 on Section II Attachment 4 Step 6.11.5
- CRITICAL STEP PAGE 3 of 7
JPM NO: A1, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 9. Record the redistribution Applicant recorded the redistribution allowance and voids allowance and voids reactivity from Comments:
reactivity from Curve Book Curve Book Table 1-8,Section II as Table 1-8,Section II 270 on Attachment 4 Step 6.11.6 S U
- 10. Record the corrected power Applicant recorded the corrected defect by summing the power defect as 2078 on Attachment Comments:
redistribution allowance and 4 voids reactivity in Step 6.11.6 and the total power defect in Step 6.11.5 Step 6.11.7 S U
- 11. Record the available rod Applicant recorded the available rod worth from Curve Book Table worth from Curve Book Table 1-8, Comments:
1-8,Section II Section II as 4426 on Attachment 4 Step 6.11.8 S U
- 12. Determine the rods Applicant recorded the most reactive correction for inoperable rods worth from Curve Book Table Comments:
rods: 1-8,Section II as 999 on Attachment 4
- a. Record the most reactive rods worth from Curve Book Table 1-8,Section II Step 6.11.9.a
- CRITICAL STEP PAGE 4 of 7
JPM NO: A1, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 13. Determine the rods Applicant recorded the number of correction for inoperable inoperable rods as 0 on Attachment Comments:
rods: 4
- b. Record the number of inoperable rods Step 6.11.9.b S U
- 14. Determine the rods Applicant recorded the rods correction for inoperable correction for inoperable rods as 0 Comments:
rods: on Attachment 4
- c. Record the total rod worth by multiplying the number of inoperable rods from Step 6.11.9.b by the worth of the most reactive rod from Step 6.11.9.a Step 6.11.9.c S U
- 15. Determine the rods Applicant recorded the RIL for the correction for rod banks power level recorded in Step 6.1.3 Comments:
below the rod insertion limit as Bank D Step 161 on Attachment (RIL) as follows: 4
- a. Record the RIL for the [From Figure 2, Rod Bank Insertion power level recorded in Limits, Core Operating Limits Report Step 6.1.3 (COLR)]
Step 6.11.10.a
- CRITICAL STEP PAGE 5 of 7
JPM NO: A1, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 16. Determine the rods Applicant recorded the current correction for rod banks critical controlling control rod bank Comments:
below the rod insertion limit position as CB D, 215 Steps on (RIL) as follows: Attachment 4
- b. Record the current critical controlling control rod bank and its height from one of the following:
- The step counters
- The plant computer Step 6.11.10.b S U
- 17. Determine the rods Applicant determined controlling correction for rod banks control rod bank position from Step Comments:
below the rod insertion limit 6.11.10.b is above the RIL from Step (RIL) as follows: 6.11.10.a and marked Steps 6.11.10.d through 6.11.10.g NA and went to Step 6.11.10.h
- c. If the current controlling control rod bank position from Step 6.11.10.b is above the RIL from Step 6.11.10.a, perform the following (i.e., no correction is necessary for rod banks above the RIL):
- Mark Steps` 6.11.10.d through 6.11.10.g NA
- Go to Step 6.11.10.h Step 6.11.10.c
- CRITICAL STEP PAGE 6 of 7
JPM NO: A1, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 18. Determine the rods Applicant recorded the rod worth correction for rod banks correction for rod banks as 0 on Comments:
below the rod insertion limit Attachment 4 (RIL) as follows:
- h. Record the rod worth correction for rod banks per one of the following:
- If rod banks are below the RIL, record the rod worth correction from Step 6.11.10.g
- If rod banks are above the RIL, record a rod worth correction of 0 pcm Step 6.11.10.h S U
- 19. Record the total corrected Applicant recorded the total reactivity summing the corrected reactivity as (-)2348 on Comments:
reactivity from Step 6.11.7, Attachment 4 6.11.8, 6.11.9.c and 6.11.10.h Step 6.11.11 S U
S U
- 21. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 7 of 7
Initial Conditions: The plant is at 3565 MWt, as indicated on REU1118, with Control Rods D @ 215 steps and RCS Boron Concentration at 750 ppm.
There are no inoperable rods.
Effective Full Power Days (EFPD) is at 270 (12000 MWD/MTU).
There is a question about whether the Rod Insertion Limit (RIL) monitor is functional.
Initiating Cues: Due to the concerns of the RIL monitor, the Control Room Supervisor directs you to perform a Shutdown Margin Calculation for the current plant conditions IAW OSP-SF-00001, Shutdown Margin Calculations.
He directs you to perform the calculation IAW Step 6.11.
The PC program OSPSF1 is currently being revised by reactor engineering and is not available.
When complete, inform the CRS of what the calculated value is for the Shutdown Margin (SDM) and if the SDM is acceptable.
Provide to Examiner when complete:
Shutdown Margin Acceptable Yes / No (Circle One)
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A2, Rev 2 KSA No: GEN 2.1.25 Revision: Feb 2013 KSA Rating: 3.9/4.2 Job
Title:
RO Task
Title:
Ablity to interpret reference materials, such as graphs, curves, tables, etc:
Calculate volume of water to transfer between RWST and SFP within given limits.
Validation Time: 20 minutes Learning Objective: T61.0110, LP-24, Obj G, List the systems that interface with the FPCCS and Explain how a loss of the interfacing system or a loss of the FPCSS affects the other The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts: OOA-BB-00003, Refuel Level Indications, Rev 11 OTA-RK-00018, Add 47D, Rev 4 OTA-RK-00022, Add 76D, Rev 1 Calculator
References:
OOA-BB-00003, Refuel Level Indications, Rev 11 OTA-RK-00018, Add 47D, Rev 4 OTA-RK-00022, Add 76D, Rev 1 Callaway Plant Tank Data Book
JPM NO: A2, Rev 2 Initial Conditions: The plant is at 80% power.
Maintenance has been performed on the level instrument for the Spent Fuel Pool (SFP), EC LI-39A.
Current level indicates zero (0) on EC LI-39A.
Refueling Water Storage Tank (RWST) level is currently at the Administrative Low Level Limit.
Cask loading pit and transfer canal gates are installed.
Initiating Cues: The Control Room Supervisor (CRS) directs you to transfer water from the RWST to the SFP to verify that the SFP high level alarm will annunciate properly on rising level.
The CRS directs you to calculate the volume of water required to actuate the SFP level high alarm and if this water is available from the RWST without violating the RWST Low Level Technical Specification Limit.
The CRS has authorized you to reduce RWST level below the Administrative Low Level for this evolution.
Complete the following and provide to the Examiner:
RWST Initial Level _________% _________gal RWST Final Level _________% _________gal Is Final RWST Level Above the Tech Spec Limit? Yes / No (Circle One)
Task Standard: Upon completion of this JPM, the Applicant will have determined that 7716 gallons of water is needed to actuate the SFP high level alarm and that the RWST will still be operable if this water is transferred to the SFP from its contents.
START TIME:
STOP TIME:
PAGE 1 of 3
JPM NO: A2, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Determine volume of water Applicant calculated that 7716 gal is required to raise SFP level to needed as follows: Comments:
high alarm setpoint High alarm setpoint for the SFP is
+8.69 as obtained from OTA-RK-00022, Add 76D Applicant determined from OOA-BB-00003 that the SFP contains 888 gal/in 8.69 X 888 gal/ = 7716 gallons S U
- 2. Determine amount that Applicant determined that RWST RWST will lower if water is level will lower by 1.9% as follows: Comments:
transferred to the SFP Current RWST level is 96.3% as obtained from OTA-00018, Add 47D (Admin Limit given in Initiating Cue)
RWST level conversion is 4009 gal/% as obtained from OOA-BB-00003*
7716 gal ÷ 4009 gal/% = 1.9%
96.3 (Initial Level) - 1.9 = 94.4 (Final Level)
- NOTE: If Callaway Plant Tank Data Book is used, conversion is 4007 gal/%
- CRITICAL STEP PAGE 2 of 3
JPM NO: A2, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 3. Determine if RWST contains Applicant determined that RWST sufficient volume to remain does contain sufficient volume to Comments:
above the Technical remain above the Technical Specification Low Level Limit Specification Low Level Limit if it is after water transfer used to transfer water to the SFP Current RWST level is 96.3% as obtained from OTA-00018, Add 47D (Admin Limit given in Initiating Cue) 96.3% - 1.9% = 94.4%
RWST TS low level limit is 93.7%
(From OTA RK-000018, Add 47D)
S U
- 4. Applicant provided following information to examiner as Comments:
requested in Initiating Cue:
Initial RWST Level-96.3% (386,066 gal)
Final RWST Level-94.4 % (378,449 gal)
Is Final RWST Level Above the Tech Spec Limit? YES S U
- 5. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 3 of 3
Initial Conditions: The plant is at 80% power.
Maintenance has been performed on the level instrument for the Spent Fuel Pool (SFP), EC LI-39A.
Current level indicates zero (0) on EC LI-39A.
Refueling Water Storage Tank (RWST) level is currently at the Administrative Low Level Limit.
Cask loading pit and transfer canal gates are installed.
Initiating Cues: The Control Room Supervisor (CRS) directs you to transfer water from the RWST to the SFP to verify that the SFP high level alarm will annunciate properly on rising level.
The CRS directs you to calculate the volume of water required to actuate the SFP level high alarm and if this water is available from the RWST without violating the RWST Low Level Technical Specification Limit.
The CRS has authorized you to reduce RWST level below the Administrative Low Level for this evolution.
Complete the following and provide to the Examiner:
RWST Initial Level _________% _________gal RWST Final Level _________% _________gal Is Final RWST Level Above the Tech Spec Limit? Yes / No (Circle One)
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A3, Rev 2 KSA No: GEN 2.2.37 Revision: Feb 2013 KSA Rating: 3.6/4.6 Job
Title:
RO Task
Title:
Ability to determine operability and/or availability of safety related equipment: Determine amperage limits for 480 VAC safety related busses when cross-connecting for maintenance.
Validation Time: 15 minutes Learning Objective: T61.0110, LP-6, Obj B, Describe the purpose and operation of the following Safeguards Power System components and subsystems: 4. 480 VAC System (NG)
The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts: OTN-NG-00001, Class 1E 480 VAC Electrical System, Rev 14 Calculator
References:
OTN-NG-00001, Class 1E 480 VAC Electrical System, Rev 14
JPM NO: A3, Rev 2 Initial Conditions: The plant is at 100% power.
NG01 local ammeter indicates 712 amps.
NG03 local ammeter indicates 344 amps.
The following Train A equipment is NOT in service:
- DG Vent Supply Fan A, CGM01A
- Air Compressor A, CKA01A
- Fuel Pool Clg Pump A, PEC01A
- CR A/C Unit A, SGK04A Initiating Cues: The Control Room Supervisor (CRS) directs you to cross-connect Load Centers NG01 and NG03 for maintenance to replace Load Center NG01 feeder breaker, NG0101.
Prior to cross-connecting NG01 and NG03, the CRS wants to know which individual equipment not currently in service could be started after the load centers are cross-connected.
Provide your answer on the cue sheet below:
Task Standard: Upon completion of this JPM, the Applicant reported that the following equipment could be started:
CGM01A, DG Vent Sply Fan A SGK04A, Ctrl Rm A/C Unit A PEC01A, Fuel Pool Clg Pmp A START TIME:
STOP TIME:
PAGE 1 of 7
JPM NO: A3, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE EXAMINER NOTE:
JPM refers to OTN-NG-00001, Section 5.10. This section will not be performed by the Applicant but does contain information that the Applicant will need to perform the assigned task. Though not expected to be performed by the Applicant, Section 5.10 steps will be contained in JPM A3.
S U
- 1. Obtain a verified working Applicant obtained working copy of copy of OTN-NG-00001 OTN-NG-00001 Comments:
S U
- 2. Refers to Section 5.10, Applicant referred to Section 5.10, Cross-Connecting Load Cross-Connecting Load Centers Comments:
Centers NG01 And NG03 NG01 And NG03
- CRITICAL STEP PAGE 2 of 7
JPM NO: A3, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 3. The following cautions apply Applicant read caution and when cross-connecting load understood that total amperage Comments:
center NG01 and NG03, due drawn by both load centers shall not to transformer and power exceed 1200 amps on local supplylimitations: ammeters
- Cross Tie Breaker NG0116 is only allowed to Examiner Note:
be closed to repair failed If asked if the impact of starting or degraded equipment current on cycling loads has been
- Closing NG0116 makes all considered, respond that 4 degraded bus voltage engineering has reviewed starting channels for NB01 current for NG01 and NG03 loads inoperable per T/S B and determined that it has no impact 3.8.9, and requires entry on limitations for current loading into T/S ACT 3.3.5.B.1 when cross connecting NG01 and and T/S ACT 3.8.1.F NG03.
- Total amperage drawn by both load centers shall not exceed 1200 amps on local ammeters
- Total allowed load of 1200 amps includes cycling loads
- No major loads should be added without referring to Attachment 1 to account for additional load Caution prior to Step 5.10.1 S U
- 4. Initiate an EOSL item for Step will not be performed inoperability of all 4 channels Comments:
for Bus NB01 degraded voltage with reference to applicable T/S:
Step 5.10.1
- CRITICAL STEP PAGE 3 of 7
JPM NO: A3, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 5. Check load centers NG01 Given in Initiating Cue and NG03 are energized Comments:
Step 5.10.2 S U
- 6. Using local ammeters, Local ammeter values given in ensure combined total load Initiating Cue Comments:
amperage for NG01 and NG03 is less than 1200 amps Step 5.10.3 S U
- 7. The bus transfer is a break- Note not read due to not being before-make operation which applicable to assigned task Comments:
will cause a momentary power loss of approximately 8 to 10 cycles. Alarms may actuate and breakers may trip. Attachment 1 provides load lists to determine effects on plant operation.
Note prior to Step 5.10.4
- CRITICAL STEP PAGE 4 of 7
JPM NO: A3, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 8. If removing the NG01 feeder Step is not applicable from service, perform the Comments:
following:
- a. Using NG HIS-10, hold switch in close position
- b. Using NG HIS-9, open NG0101
- c. Release NG HIS-10 Step 5.10.4 S U
- 9. If removing the NG03 feeder Step is not applicable from service, perform the Comments:
following:
- a. Using NG HIS-10, hold switch in close position
- b. Using NG HIS-11, open NG0301
- c. Release NG HIS-10 Step 5.10.5 S U
- 10. Check loads on NG01 and Step is not applicable NG03 for breaker trips than Comments:
may have occurred during the transfer Step 5.10.6
- CRITICAL STEP PAGE 5 of 7
JPM NO: A3, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 11. Using local ammeters, check Step is not applicable combined total load Comments:
amperage for NG01 and NG03 is less than 1200 amps Step 5.10.7 S U
- 12. If necessary to start loads on Applicant determined loads that NG01 or NG03, ensure toal could be started - see JPM Step 15 Comments:
load will not exceed 1200 amps, by referring to Attachment 1 Step 5.10.8 S U
- 13. If necessary, start loads on Step is not applicable NG01 and NG03 Comments:
Step 5.10.9 S U
- 14. Refers to Attachment 1, Load Applicant referred to Attachment 1, Centers NG01 & NG03 Load Centers NG01 & NG03 Loads Comments:
Loads
- CRITICAL STEP PAGE 6 of 7
JPM NO: A3, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 15. Using Att 1 and provided Applicant determined that CGM01A, cues, determines what SGK04A and PEC01A can be Comments:
equipment can be started on started but that CKA01A could not NG01 and NG03 after they be started, as based on the following are cross-connected calculations:
Current amperage on both busses is 712 + 344 = 1056 (Provided in cue)
Margin for starting additional equipment is 1200 - 1056 = 144 Amperage for equipment not running would be:
CGM01A-130 - Acceptable CKA01A-296 - Not Acceptable PEC01A-132 - Acceptable SGK04A Acceptable Acceptable equipment to start would be CGM01A OR PEC01A OR SGK04A.
Information is provided to the CRS (Examiner)
S U
- 16. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 7 of 7
Initial Conditions: The plant is at 100% power.
NG01 local ammeter indicates 712 amps.
NG03 local ammeter indicates 344 amps.
The following Train A equipment is NOT in service:
- DG Vent Supply Fan A, CGM01A
- Air Compressor A, CKA01A
- Fuel Pool Clg Pump A, PEC01A
- CR A/C Unit A, SGK04A Initiating Cues: The Control Room Supervisor (CRS) directs you to cross-connect Load Centers NG01 and NG03 for maintenance to replace Load Center NG01 feeder breaker, NG0101.
Prior to cross-connecting NG01 and NG03, the CRS wants to know which individual equipment not currently in service could be started after the load centers are cross-connected.
Provide your answer on the cue sheet below:
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A4, Rev 2 KSA No: GEN 2.4.14 Revision: Feb 2013 KSA Rating: 3.8/4.5 Job
Title:
RO Task
Title:
Knowledge of general guidelines for EOP usage: Determine correct Functional Restoration Guideline (FRG) procedure implementation following a plant event.
Validation Time: 14 minutes Learning Objective: T61.003D, LP D-1, Obj L, Explain operator responses during status tree monitoring for each of the following: 1. Extreme challenge is diagnosed; 2. Severe challenge is diagnosed; 3. Not satisfied condition is diagnosed The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts: CSF-1, Critical Safety Function Status Trees (CSFST), Rev 10
References:
CSF-1, Critical Safety Function Status Trees (CSFST), Rev 10
JPM NO: A4, Rev 2 Initial Conditions: A fault/rupture occurred in Steam Generator D 30 minutes ago.
The following plant conditions currently exist:
NIS Source Ranges Energized / 0 SUR Containment Pressure 28 psig RCS Subcooling 10°F Superheat RCS Pressure 1300 psig Auxiliary Feedwater Flow SG A - 100,000 lbm/hr SG B - 100,000 lbm/hr SG C - 100,000 lbm/hr SG D - 0 lbm/hr Steam Generator Levels 0% NR - All Steam Generators Steam Generator Pressures SG A - 825 psig SG B - 815 psig SG C - 815 psig SG D - 0 psig RCS Cold Leg Temperatures 240°F - Loop 4 450°F - Loops 1/2/3 Core Exit Thermocouples 705°F - 750°F RVLIS (Pumps Off) 45%
Pressurizer Level 0%
Containment Spray Pumps Both Off Atmospheric Steam Dumps All Closed Initiating Cues: The Control Room Supervisor (CRS) directs you to perform the Critical Safety Functions in accordance with CSF-1, Critical Safety Function Status Trees (CSFST), and document your results on Attachment A, CSFST Review Summary.
Task Standard: Upon completion of this JPM, the Applicant will report the following CSF status to the CRS:
Subcriticality Green (Sat)
Core Cooling Orange Go to FR-C.2 Heat Sink Yellow Go to FR-H.5 Integrity Orange Go to FR-P.1 Containment Orange Go to FR-Z.1 Inventory Yellow Go to FR-I.2 The Applicant will report that the highest priority CSF is Core Cooling and that FR-C.2, Response to Degraded Core Cooling, should be implemented.
START TIME: STOP TIME:
PAGE 1 of 3
JPM NO: A4, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Obtain a verified working Applicant obtained working copy of copy of CSF-1 CSF-1 Comments:
S U
- 2. Reviews Subcriticality CSF Applicant determined Subcriticality CSF is satisfied - green condition Comments:
S U
- 3. Reviews Core Cooling CSF Applicant determined Core Cooling CSF is orange - go to FR-C.2 Comments:
S U
- CRITICAL STEP PAGE 2 of 3
JPM NO: A4, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
S U
S U
S U
- 8. Informs the CRS that CSF Applicant reported that highest review is complete priority CSF is Core Cooling and that Comments:
FR-C.2, Response to Degraded Core Cooling, should be implemented S U
- 9. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 3 of 3
Initial Conditions: A fault/rupture occurred in Steam Generator D 30 minutes ago.
The following plant conditions currently exist:
NIS Source Ranges Energized / 0 SUR Containment Pressure 28 psig RCS Subcooling 10°F Superheat RCS Pressure 1300 psig Auxiliary Feedwater Flow SG A - 100,000 lbm/hr SG B - 100,000 lbm/hr SG C - 100,000 lbm/hr SG D - 0 lbm/hr Steam Generator Levels 0% NR - All Steam Generators Steam Generator Pressures SG A - 825 psig SG B - 815 psig SG C - 815 psig SG D - 0 psig RCS Cold Leg Temperatures 240°F - Loop 4 450°F - Loops 1/2/3 Core Exit Thermocouples 705°F - 750°F RVLIS (Pumps Off) 45%
Pressurizer Level 0%
Containment Spray Pumps Both Off Atmospheric Steam Dumps All Closed Initiating Cues: The Control Room Supervisor (CRS) directs you to perform the Critical Safety Functions in accordance with CSF-1, Critical Safety Function Status Trees (CSFST), and document your results on Attachment A, CSFST Review Summary.
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A5, Rev 2 KSA No: GEN 2.1.35 Revision: Feb 2013 KSA Rating: 2.2/3.9 Job
Title:
SRO Task
Title:
Knowledge of the fuel handling responsibilities of SROs: Evaluate conditions for restarting of Refueling Preshuffle of Irradiated Fuel Assemblies in the Spent Fuel Pool.
Validation Time: 15 minutes Learning Objective: T61.0110, LP-24, Obj I, Explain the precautions, limitations and bases for the following conditions/processes associated with OTN-EC-00001, Fuel Pool Cooling and Cleanup System: 1. Minimum Spent Fuel Pool (SFP) level; 2. SFP temperature limits; 3. Minimum boron concentration and T61.0110, LP-39, Obj F, State the Tech Spec and FSAR LCOs for the AB/FB HVAC equipment and Area Temperature Monitoring The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts: OSP-SF-00003, Pre-Core Alteration Verifications, Rev 26 OOA-BB-00003, Refuel Level Indications, Rev 11 CDP-ZZ-00200,Chemistry Schedule and Water Specs, APP B, Primary Plant Systems Tables, Rev 27 Technical Specifications Technical Specifications Bases
References:
OSP-SF-00003, Pre-Core Alteration Verifications, Rev 26 OOA-BB-00003, Refuel Level Indications, Rev 11 CDP-ZZ-00200,Chemistry Schedule and Water Specs, APP B, Primary Plant Systems Tables, Rev 27 Technical Specifications Technical Specifications Bases
JPM NO: A5 Rev 2 Initial Conditions: The Plant is in Mode 1.
Preparations are being made for Refuel 19.
Irradiated fuel assembly shuffling activities have been in progress in the Spent Fuel Pool.
Shuffling activities have been suspended for 10 days due to a shortage of manpower.
The Shift Manager (SM) desires to resume shuffling irradiated fuel assemblies in the Spent Fuel Pool.
The following plant conditions exist:
- Spent Fuel Pool level indicates -22 on ECLI39A
- Spent Fuel Pool boron concentration is 2250 ppm
- OSP-KE-00004, Excessive Load Interlock Verification For The Spent Fuel Pool Bridge Crane, was performed 5 days ago
- OSP-KE-00003, Cask Handling Crane Bridge and Trolley Travel Limit Verification, was last performed just before shuffling activities were suspended 10 days ago
- SGK04A, CTRL RM A/C Unit A, failed to start two hours ago, and SGK04B is tagged OOS for breaker maintenance
- TS 3.7.13, Emergency Exhaust System (EES) is satisfied and all Fuel Building doors are closed Initiating Cues: The SM directs you to evaluate conditions for recommencement of shuffling irradiated fuel assemblies in the Spent Fuel Pool IAW OSP-SF-00003, Pre-Core Alterations.
Evaluate conditions per Section 6.8 of OSP-SF-00003 and document your results on Attachment 7, Actions Required Prior To Movement Of Irradiated Fuel Assemblies In The Fuel Building.
PAGE 1 of 6
JPM NO: A5, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE Task Standard: Upon completion of this JPM, the Operator will have identified four (4) items that would prevent the recommencement of shuffling fuel assemblies.
The four items are:
- OSP-KE-00003, Cask Handling Crane Bridge and Trolley Travel Limit Verification, is not current
- Spent Fuel Pool level is below the minimum level of -19.50 (>23 over the top of the storage racks)
- Two inoperable trains of CREVS, TS 3.7.10, due to both SGK04A and SGK04B being OOS, require the suspension of movement of irradiated fuel assemblies
- Two inoperable trains of CRACS, TS 3.7.11, due to both SGK04A and SGK04B being OOS, require the suspension of movement of irradiated fuel assemblies START TIME: STOP TIME:
- CRITICAL STEP PAGE 2 of 6
JPM NO: A5, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Obtains a verified working Applicant obtained working copy of copy of OSP-SF-00003 OSP-SF-00003 Comments:
S U
- 2. Refers to Section 6.8, Prior Applicant referred to Section 6.8 To Movement Of Irradiated Comments:
Fuel Assemblies In The Fuel Building S U
- 3. Steps in Section 6.8 may be Applicant read note performed in any order. Step Comments:
numbers are used for references only.
Documentation for this section is made on Attachment 7.
Note prior to 6.8 S U
- 4. Ensure OSP-KE-00003 has Applicant determined condition NOT been performed within 7 satisfied as OSP was last performed Comments:
days prior to crane use just before shuffling activities were suspended 10 days ago Step 6.8.1
- CRITICAL STEP PAGE 3 of 6
JPM NO: A5, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 5. Ensure OSP-KE-00004 has Applicant determined condition was been performed within 7 satisfied as OSP was performed 5 Comments:
days prior to crane use days ago Step 6.8.2 S U
- 6. Check that the EES is Applicant determined condition was operable satisfied based on information given Comments:
in Initial Conditions (TS 3.7.13, Emergency Exhaust System (EES) is satisfied and all Fuel Building Step 6.8.3 doors are closed)
S U
- 7. Ensure that the Fuel Storage Applicant determined condition was Pool water level is greater NOT satisfied as SFP level of -22 is Comments:
than or equal to 23 feet over below the minimum level of -19.5 for the top of the storage racks moving irradiated FAs Step 6.8.4 (Can be determined from OOA-BB-00003)
S U
- 8. Ensure the Fuel Storage Applicant determined condition was Pool boron concentration is satisfied as the given concentration Comments:
greater than or equal to the is greater than the Operating Limit Operating Limit of CDP-ZZ- from CDP-ZZ-00200, APP B, of 00200 2165 Step 6.8.5
- CRITICAL STEP PAGE 4 of 6
JPM NO: A5, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 9. Ensure the Fuel Storage Applicant determined condition was Pool boron concentration is satisfied as the given concentration Comments:
greater than or equal to 2165 of 2250 is greater than 2165 ppm ppm Step 6.8.6 S U
- 10. Ensure that the Control Applicant determined condition was Room Emergency Ventilation NOT satisfied due to SGK04A and B Comments:
System (CREVS) is operable both being out of service at this time TS 3.7.10 is NOT satisfied Step 6.8.7 S U
- 11. Ensure that the Control Applicant determined condition was Room Air Conditioning NOT satisfied due to SGK04A and B Comments:
System (CRACS) is operable both being out of service at this time TS 3.7.11 is NOT satisfied Step 6.8.8 S U
- 12. Ensure the following Applicant determined condition was electrical power system Tech satisfied Comments:
Specs are met:
- T/S LCO 3.8.5 required)
- T/S LCO 3.8.8
- T/S LCO 3.8.10
- CRITICAL STEP PAGE 5 of 6
JPM NO: A5, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 13. Determines shuffling of FAs Applicant determined shuffling of in the SFP cannot FAs in the SFP cannot recommence Comments:
recommence at this time at this time due to the following 4 items not being satisfied:
- 1) OSP-KE-00003 not current
- 2) SFP level below required minimum
- 3) Two CREVS trains inoperable
- 4) Two CRACS trains inoperable Applicant informed SM of items which prevent recommencing of SFP FA shuffle S U
- 14. The JPM is complete Record stop time on Page 2 Comments:
- CRITICAL STEP PAGE 6 of 6
Initial Conditions: The Plant is in Mode 1.
Preparations are being made for Refuel 19.
Irradiated fuel assembly shuffling activities have been in progress in the Spent Fuel Pool.
Shuffling activities have been suspended for 10 days due to a shortage of manpower.
The Shift Manager (SM) desires to resume shuffling irradiated fuel assemblies in the Spent Fuel Pool.
The following plant conditions exist:
- Spent Fuel Pool level indicates -22 on ECLI39A
- Spent Fuel Pool boron concentration is 2250 ppm
- OSP-KE-00004, Excessive Load Interlock Verification For The Spent Fuel Pool Bridge Crane, was performed 5 days ago
- OSP-KE-00003, Cask Handling Crane Bridge and Trolley Travel Limit Verification, was last performed just before shuffling activities were suspended 10 days ago
- SGK04A, CTRL RM A/C Unit A, failed to start two hours ago, and SGK04B is tagged OOS for breaker maintenance
- TS 3.7.13, Emergency Exhaust System (EES) is satisfied and all Fuel Building doors are closed Initiating Cues: The SM directs you to evaluate conditions for recommencement of shuffling irradiated fuel assemblies in the Spent Fuel Pool IAW OSP-SF-00003, Pre-Core Alterations.
Evaluate conditions per Section 6.8 of OSP-SF-00003 and document your results on Attachment 7, Actions Required Prior To Movement Of Irradiated Fuel Assemblies In The Fuel Building.
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A6, Rev 2 KSA No: GEN 2.1.18 Revision: Feb 2013 KSA Rating: 3.6/3.8 Job
Title:
SRO Task
Title:
Ability to make accurate, clear, and concise logs, records, status boards, and reports: Review shiftly logs for completeness and correctness.
Validation Time: 30 minutes Learning Objective: T61.0110, LP SS-10, Obj C, Review operating logs for trends The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts: OSP-ZZ-00001, Control Room Shift And Daily Log Readings And Channel Checks, Attachment 1, Rev 79
References:
OSP-ZZ-00001, Control Room Shift And Daily Log Readings And Channel Checks, Rev 79 OSP-BB-00009, RCS Inventory Balance, Rev 33
JPM NO: A6, Rev 2 Initial Conditions: The Plant is at 100% power.
Discharge Monitor Tank (DMT) B is currently being discharged.
The program for Auto Tour rounds is not available and manual logs are required.
Initiating Cues: The Reactor Operator (RO) has completed the Control Room Night Shift logs.
You are to review Sheets 1-10 of Attachment 1 for accuracy and list any corrections or plant issues that need to be addressed below.
Another SRO will review Sheets 11-19.
Task Standard: There are 7 mistakes that have been made on the completed logs provided to the Applicant as described below:
- 1) Due date for next completion of OSP-BB-00009 is 5 days rather than the required 3 days on Sheet 1.
- 2) Group counters for control rods Bank D1 and Bank D2 logged at 228 steps rather than 215 steps on Sheet 4 - Controlling rod height is listed as Control Bank D at 215 steps on Sheet 1.
- 3) Condensate Storage Tank Level is below the Acceptance Criteria on Sheet 6.
- 4) Cooling Tower B/D Disch flow on Sheet 6 is above the maximum flow allowed during a plant discharge (DMT B currently being discharged as given in Initial Conditions).
- 5) ACC Tank B Press is below the Acceptance Criteria on Sheet 7.
- 6) Corrective action needed for RWST temperature being above 90°F on Sheet 8.
- 7) Loop 3 flow channel check listed as SAT on Sh 10 - incorrect.
Upon completion of this JPM, the Applicant will have identified at least 6 of the 7 corrections that are needed on the logs to successfully complete this JPM.
START TIME: STOP TIME:
PAGE 1 of 3
JPM NO: A6, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Obtain a verified working Applicant obtained working copy of copy of OSP-ZZ-00001 OSP-ZZ-00001 Comments:
S U
- 2. Review completed copy of Applicant reviewed completed copy Sheets 1-10 of Attachment 1 of Sheets 1-13 of Attachment 1 Comments:
- CRITICAL STEP PAGE 2 of 3
JPM NO: A6, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 3. Identifies at least 6 of the 7 Applicant identified at least six of the items needing to be seven items needing to be Comments:
addressed in completed logs addressed in the completed logs reviewed reviewed - the items needing to be addressed are:
- 1) Due date for OSP-BB-00009 on Sh 1
- 2) Group counters for CB D different on Sh 4 from Sh 1
- 3) Condensate Storage Tank Level below the acceptance criteria on Sh 6
- 4) CT B/D flow incorrect for plant discharge in progress on Sh 6
- 5) ACC Tank B press below acceptance criteria on Sh 7
- 6) RWST temp on Sh 7 needs corrective action identified
- 7) Loop 3 flow channel check listed as SAT on Sh 10 - incorrect S U
- 4. The JPM is complete Record stop time on Page 1 Comments:
Six of seven items need to be identified to successfully complete JPM
- CRITICAL STEP PAGE 3 of 3
Initial Conditions: The Plant is at 100% power.
Discharge Monitor Tank (DMT) B is currently being discharged.
The program for Auto Tour rounds is not available and manual logs are required.
Initiating Cues: The Reactor Operator (RO) has completed the Control Room Night Shift logs.
You are to review Sheets 1-10 of Attachment 1 for accuracy and list any corrections or plant issues that need to be addressed below.
Another SRO will review Sheets 11-19.
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A7, Rev 2 KSA No: GEN 2.2.18 Revision: Feb 2013 KSA Rating: 2.6/3.9 Job
Title:
SRO Task
Title:
Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc:
Perform a risk assessment during shutdown conditions.
Validation Time: 10 minutes Learning Objective: T61.003A, LP A-24, Obj I, Evaluate the effect of removing specific components from service will have upon current Plant Risk The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts: EDP-ZZ-01129, Callaway Energy Center Risk Assessment, Rev 33
References:
EDP-ZZ-01129, Callaway Energy Center Risk Assessment, Rev 33
JPM NO: A7, Rev 2 Initial Conditions:
- The Plant is in Mode 6.
- Core Offload is in progress with Refueling Pool level at 390.
- XNB01 is OPERABLE supplying NB01.
- XNB02 is Out of Service for maintenance.
- NE01 is OPERABLE.
- NE02 is AVAILABLE with LSELS deenergized.
- AEPS Diesel Generators are AVAILABLE.
- There is NO work being performed in the Switchyard or on the Grid.
- A Severe Thunderstorm Warning has been issued for Callaway County.
Initiating Cues: The Shift Manager (SM) directs you to perform a Shutdown Safety Assessment for Power Availabilty IAW EDP-ZZ-01129, Callaway Energy Center Risk Assessment.
Inform the SM of the number of credit points and color condition for Power Availability when you are complete.
Task Standard: Upon completion of this JPM, the Applicant will have completed a Shutdown Safety Assessment for Power Availability, using Attachment 6, and informed the SM that there are five (5) credit points for Power Availability and the condition color is Green.
START TIME:
STOP TIME:
PAGE 1 of 4
JPM NO: A7, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Obtain a verified working Applicant obtained working copy of copy of EDP-ZZ-01129 EDP-ZZ-01129 Comments:
S U
- 2. Determines correct Applicant determined Attachment 6 attachment to use is Att 6, is correct attachment to use for Comments:
Shutdown Safety given plant conditions Assessment - MODE 6 -
Refueling Operations > 23 ft.
Above Vessel Flange (Indicated Level > 376.0)
S U
- 3. Assigns 1 point for operable Applicant assigned 1 point for offsite AC power sources operable offsite AC power sources Comments:
(XNB01) because XNB01 is operable Attachment 6, Power Availability Block, Item #1 S U
- 4. Assigns 0 points for available Applicant assigned 0 points for offsite AC power sources available offsite AC power sources Comments:
because XNB01 is the only operable offsite source (cannot take credit for availability if credit already taken for operablity)
Attachment 6, Power Availability Block, Item #2
- CRITICAL STEP PAGE 2 of 4
JPM NO: A7, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 5. Assigns 1 point for operable Applicant assigned 1 point for onsite AC power sources operable onsite AC power sources Comments:
because NE01 is operable Attachment 6, Power Availability Block, Item #3 S U
- 6. Assigns 1 point for available Applicant assigned 1 point for onsite AC power sources available onsite AC power sources Comments:
because NE02 is available (it is not operable)
Attachment 6, Power Availability Block, Item #4 S U
- 7. Assigns 1 point for AEPS Applicant assigned 1 point for AEPS diesel generators being diesel generators being available Comments:
available (Initial Condition)
Attachment 6, Power Availability Block, Item #5 S U
- 8. Assigns 1 point for no Applicant assigned 1 point for no significant switchyard work in significant switchyard work in Comments:
progress progress (Initial Condition)
Attachment 6, Power Availability Block, Item #6
- CRITICAL STEP PAGE 3 of 4
JPM NO: A7, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 9. Deducts 0 points for no Applicant deducted 0 points for no significant grid work in significant grid work in progress Comments:
progress (Initial Condition)
Attachment 6, Power Availability Block, Item #7 S U
- 10. Applicant informed SM there were five (5) credit points for Power Comments:
Availability S U
- 11. Applicant informed SM the Power Availability condition color is Green Comments:
S U
- 12. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 4 of 4
Initial Conditions:
- The Plant is in Mode 6.
- Core Offload is in progress with Refueling Pool level at 390.
- XNB01 is OPERABLE supplying NB01.
- XNB02 is Out of Service for maintenance.
- NE01 is OPERABLE.
- NE02 is AVAILABLE with LSELS deenergized.
- AEPS Diesel Generators are AVAILABLE.
- There is NO work being performed in the Switchyard or on the Grid.
- A Severe Thunderstorm Warning has been issued for Callaway County.
Initiating Cues: The Shift Manager (SM) directs you to perform a Shutdown Safety Assessment for Power Availabilty IAW EDP-ZZ-01129, Callaway Energy Center Risk Assessment.
Inform the SM of the number of credit points and color condition for Power Availability when you are complete.
Credit Points: __________
Color Condition: __________
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A8, Rev 2 KSA No: GEN 2.3.12 Revision: Feb 2013 KSA Rating: 3.2/3.7 Job
Title:
SRO Task
Title:
Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.:
Determine estimated dose for job and make recommendation on whether to install shielding to reduce total dose.
Validation Time: 6 minutes Learning Objective: T61.0110, LP-75 Obj C, APA-ZZ-01000, Callaway Plant Radiation Protection Program: 1. Describe the purpose and scope; 2. Describe the management policy regarding radiation exposure The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___
Student Handouts:
References:
HTP-ZZ-01101, Administrative Controls For Radiation Shielding, Rev 17
JPM NO: A8, Rev 2 Initial Conditions:
- A work package is being planned for maintenance on EBG05, Letdown Reheat Heat Exchanger, which is located in Room 1104.
- A dose rate reading of 80 mR/hr at 12 inches has been taken by RP at the work location.
- The work for Operations to perform prior to maintenance is expected to take 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.
- It has been determined that if shielding is installed, the dose rate will lower to 45 mR/hr.
- The estimated total time to install and remove the shielding is 30 minutes. The dose to install and remove the shielding is the same.
Initiating Cues: The Shift Manager directs you to review this job and determine the total expected dose for the work if shielding is not installed and total expected dose if shielding is installed.
Recommend whether or not temporary shielding should be requested.
Task Standard: Applicant calculated total estimated dose for the work without installing shielding to be 140 mrem. With shielding installed the total estimated dose, including the time to install and remove the shielding, was calculated to be 118.75 mrem. The applicant recommended requesting the installation of temporary shielding.
START TIME:
STOP TIME:
PAGE 1 of 2
JPM NO: A8, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Determine expected dose Applicant determined expected dose without shielding. without shielding to be 140 mrem Comments:
80 mR/hr X 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> = 140 mrem S U
- 2. Determine expected dose Applicant determined expected dose with shielding installed. with the installation of shielding to be Comments:
118.75 mrem (80 mR/hr X 30 mins) +
(45 mR/hr X 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />) = 118.75 mrem S U
- 3. Determine if shielding should Applicant determined that the be requested. installation of shielding would save a Comments:
total of 21.25 mrem for the job; therefore they recommended that the installation of temporary shielding be requested for this job S U
- 4. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 2 of 2
Initial Conditions:
- A work package is being planned for maintenance on EBG05, Letdown Reheat Heat Exchanger, which is located in Room 1104.
- A dose rate reading of 80 mR/hr at 12 inches has been taken by RP at the work location.
- The work for Operations to perform prior to maintenance is expected to take 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.
- It has been determined that if shielding is installed, the dose rate will lower to 45 mR/hr.
- The estimated total time to install and remove the shielding is 30 minutes. The dose to install and remove the shielding is the same.
Initiating Cues: The Shift Manager directs you to review this job and determine the total expected dose for the work if shielding is not installed and total expected dose if shielding is installed.
Recommend whether or not temporary shielding should be requested.
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: A9, Rev 2 KSA No: GEN 2.4.41 Revision: Feb 2013 KSA Rating: 2.9 / 4.6 Job
Title:
SRO Task
Title:
Knowledge of the emergency action level thresholds and classifications:
Initiate RERP implementation to include event classification and initial offsite notification.
Validation Time: No greater than 30 minutes (Time Critical)
Learning Objective: T61.0110, LP-76, Obj C, Identify initial classifications and potential escalations when plant conditions change and Obj D, For a given Emergency Declaration, demonstrate the use of Sentry computer to make the required notifications The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ X___
Student Handouts: EIP-ZZ-00102, Emergency Implementing Actions, Rev 48
References:
EIP-ZZ-00101, Classification of Emergencies, Rev 47 EIP-ZZ-00101, ADD 1, EAL Classification Matrix, Rev 3 EIP-ZZ-00102, Emergency Implementing Actions, Rev 48
JPM NO: A9, Rev 2 (THIS IS A DRILL)
Initial Conditions: Callaway is in a Refuel with the following conditions:
0100
- Reactor Vessel Head removed for core off-load
- 144 Fuel Assemblies remain in the Reactor Vessel
- The Containment equipment hatch is open to support outage equipment coming into Containment
- RCS Wide Range Temperature (THOT) is 188°F and lowering
- NB02 is deenergized for maintenance
- RHR Pump A trips on overcurrent 0115
- Refueling Pool Level, BB LI-53A 394 inches and STABLE
- RCS Wide Range Temperature (THOT) 204°F and RISING Initiating Cues: Determine the Emergency Event Classification IAW EIP-ZZ-00101, Classification Of Emergencies.
Perform Attachment 5 of EIP-ZZ-00102, Emergency Implementing Actions, up through the notification of Offsite Agencies using Sentry.
This JPM is Time Critical.
(THIS IS A DRILL)
Task Standard: Upon completion of this JPM, the Applicant will have:
- 1) Determined the event to be an Alert IAW EIP-ZZ-00101, Classification Of Emergencies, within 15 minutes.
- 2) Notified all appropriate personnel IAW Attachment 5 of EIP-ZZ-00102, Emergency Implementing Actions, including the notification of Offsite Agencies within 15 minutes of the Event Classification.
START TIME: STOP TIME:
PAGE 1 of 3
JPM NO: A9, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 1. Obtain a verified working Applicant obtained working copies of copy of EIP-ZZ-00101, procedures Comments:
Classification of Emergencies, ADD1 Wall Chart, and combined EAL attachments S U
- 2. Using the given conditions Applicant declared an Alert based on and Addendum 1, determine EAL CA3.1 within 15 minutes Comments:
the appropriate emergency classification: Alert Time of Declaration (Start of new 15 min clock)
S U
- 3. Notify Facility Personnel Applicant notified facility personnel Announce the Emergency Comments:
Classification, the Declaration Time and the Cause EIP-ZZ-00102, ATT 5, EC Flowchart S U
- 4. Notify Onsite Personnel Applicant notified onsite personnel Complete Attachment 1 - Comments:
Sound the Emergency Alarm EIP-ZZ-00102, ATT 5, EC Flowchart
- CRITICAL STEP PAGE 2 of 3
JPM NO: A9, Rev 2 JPM TASK PERFORMANCE STEP ELEMENT STANDARD SCORE S U
- 5. Is Emergency an Alert or Applicant determined emergency Higher? was an Alert Comments:
EIP-ZZ-00102, ATT 5, EC Flowchart S U
- 6. Have SAS activate callout Applicant had SAS activate callout per KOA-ZZ-00200 using the per KOA-ZZ-00200, using Message Comments:
appropriate message, if not #1 - Calls out all ERO members already activated at a lower classification Examiner Cue:
EIP-ZZ-00102, ATT 5, EC SAS has been notified to activate Flowchart callout S U
- 7. Is Emergency a General Applicant determined emergency Emergency was not a General Emergency Comments:
EIP-ZZ-00102, ATT 5, EC Flowchart S U
- 8. Notify offsite agencies by Applicant filled out the Sentry completing and sending the notification form and sent it to the Comments:
Sentry notification form offsite agencies within 15 minutes of completing the EAL classification Time Notification Sent IAW the key (Completion time of 2nd EIP-ZZ-00102, ATT 5, EC Flowchart 15 min clock)
S U
- 9. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 3 of 3
(THIS IS A DRILL)
Initial Conditions: Callaway is in a Refuel with the following conditions:
0100
- Reactor Vessel Head removed for core off-load
- 144 Fuel Assemblies remain in the Reactor Vessel
- The Containment equipment hatch is open to support outage equipment coming into Containment
- RCS Wide Range Temperature (THOT) is 188°F and lowering
- NB02 is deenergized for maintenance
- RHR Pump A trips on overcurrent 0115
- Refueling Pool Level, BB LI-53A 394 inches and STABLE
- RCS Wide Range Temperature (THOT) 204°F and RISING Initiating Cues: Determine the Emergency Event Classification IAW EIP-ZZ-00101, Classification Of Emergencies.
Perform Attachment 5 of EIP-ZZ-00102, Emergency Implementing Actions, up through the notification of Offsite Agencies using Sentry.
This JPM is Time Critical.
(THIS IS A DRILL)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Callaway Date of Examination: 3/18/2013 Exam Level: RO (only) / SRO-I / SRO-U Operating Test No.: 2013301, Rev.3 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 S1 004 Chemical and Volume Control System N, S, A, E 1 Borate Reactor Coolant System for Power Change S2 010 Reactor Coolant System (BB)
D, S 3 Perform System Surveillance - BBHV8000A Stroke Test S3 013 Engineered Safety Features Actuation System (ESFAS) M, S, A, E, 2
EN, L Perform Attachment A of E-0 S4 007 Pressurizer Relief Tank (PRTS)
N, S 5 Drain PRT to Containment Normal Sump (RO ONLY)
S5 059 Main Feedwater System D, S, A 4S Transfer A MFP Speed Control / Pump Trip S6 062 A.C. Electrical Distribution Perform Operational Testing of the Alternate Emergency N, S 6 Power Source S7 005 Residual Heat Removal System N, S, L, 4P Transfer to Cold Leg Recirculation A, E S8 029 Containment Purge System N, S 8 Remove Containment Mini-Purge System From Service In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1 055 Station Blackout D, A 6 Locally Start (NE01) Emergency Diesel P2 059 Main Feedwater (MFW) System D 4S Locally Operate A Main Feedwater Regulating Valve P3 033 Spent Fuel Pool Cooling System M, R 8 Place RWST in Recirculation
@ 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 (5) / 4-6 (5) / 2-3 (3)
(C)ontrol room (0) / (0) / (0)
(D)irect from bank 9 (4) 8 (4) / 4 (2)
(E)mergency or abnormal in-plant 1 (3) / 1 (3) / 1 (2)
(EN)gineered safety feature - (1) / - (1) / 1 (1) (control room system)
(L)ow-Power / Shutdown 1 (2) / 1 (2) / 1 (1)
(N)ew or (M)odified from bank including 1(A) 2 (7) / 2 (6) / 1 (3)
(P)revious 2 exams 3 (0) / 3 (0) / 2 (0) (randomly selected)
(R)CA 1 (1) / 1 (1) / 1 (1)
(S)imulator (8) (7) (2)
Rev 3
JPM Summary S1 This is a NEW JPM. The applicant will be assigned the task of borating the RCS for a plant shutdown due to a S/G tube leak IAW OTO-MA-00008, Rapid Load Reduction. Both normal boration to the VCT and emergency boration from the Boric Acid Storage Tank will not be successful due to equipment malfunctions. The applicant will have to use the RNO option of borating from the RWST, which will be successful (ALTERNATE PATH).
S2 This is a BANK JPM [URO-SBB05C77J (A)]. The applicant will perform the stroke time test for BBHV8000A, Reactor Coolant System Pressurizer PORV Block Valve, per OSP-BB-V00001, RCS Valve Inservice Test. When the valve is stroked, its closing and opening times exceed the allowable times. The acceptance criterion is not met and the valve fails its surveillance with notification provided to the CRS.
S3 This JPM is MODIFIED from BANK JPM URO-AEO01C184J (A). The applicant will be assigned Attachment A of E-0, Reactor Trip or Safety Injection.
When verifying equipment status the applicant will find equipment that failed to properly actuate on the SI signal. This JPM was modified from the bank JPM in that it includes different equipment that must be manually started (ALTERNATE PATH).
S4 This is a NEW JPM. The Pressurizer Relief Tank (PRT) has a high level due to valve testing with its associated high level alarm activated. The applicant will be required to drain the PRT to the containment normal sump sufficiently to clear the tank high level alarm and not actuate the low level alarm.
S5 This is a BANK JPM repeated from the 2007 License Exam. The applicant will be directed to transfer MFP control from Auto to Manual on the GE Controller.
During the process of completing the transfer the pump will develop bearing problems resulting in high thrust bearing oil temperature. ALTERNATE PATH action will be required by the applicant to trip the pump in accordance with OTA-RK-00026 annunciator response.
S6 This is a NEW JPM. The applicant will be assigned the task of performing an online test of Alternate Emergency Power Source Diesel Generator #4 from the Control Room. The diesel will be started, readings taken and then secured from the Control Room.
S7 This is a NEW JPM. The simulator will be set up following a large Loss of Coolant Accident. The applicant will be directed to transfer the Emergency Core Cooling System to the recirculation mode in accordance with ES-1.3, Transfer to Cold Leg Recirculation. During performance, the applicant finds valves out of position and must use the Response Not Obtained column to complete the task (ALTERNATE PATH).
Rev 3
S8 This is a NEW JPM. The containment mini-purge system is in service. The applicant will be directed to remove the containment mini-purge system from service in accordance with OTN-GT-00001, Containment Purge System.
P1 This is a BANK JPM (URO-AEO05059J(A)). In the plant, the applicant will simulate locally starting an emergency diesel generator (EDG) which fails to start following a loss of all AC Power. The applicant will first try to reset the Engine Shutdown Relay to start the EDG. When this fails to start the EDG, the emergency start pop-out button will be actuated, which also fails to start the EDG. The applicant will then take local control of the EDG and will start the EDG with the local start button (ALTERNATE PATH).
P2 This is a BANK JPM (URO-SAE02P055J). In the plant, the applicant will simulate taking local control of A Main Feedwater Regulating Valve.
P3 This JPM is MODIFIED from BANK JPM URO-SEC01053J. In the plant, the applicant will simulate placing the Refueling Water Storage Tank (RWST) in recirculation for Chemistry. This will be an ALTERNATE PATH JPM in that several valves will not be in their required position for recirculation and will have to be repositioned by the applicant. Also flow will have to be adjusted following the lineup. The bank JPM was not alternate path.
Rev 3
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim S1, Rev 2 KSA No: 004A4.07 Revision: Feb 2013 KSA Rating: 3.9 / 3.7 Job
Title:
RO / SROI / SROU Task
Title:
Borate the Reactor Coolant System for a Power Change.
Validation Time: 15 minutes Learning Objective: T61.003B, LP B-39, Obj C, Describe Continuous Action Step(s) including the required Response Not Obtained actions The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluators Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: ___X___ Time Critical: ___ ___
Student Handouts: OTO-MA-00008, Rapid Load Reduction, Pages 1-10 OTN-BG-00002, Reactor Makeup Control and Boron Thermal Regeneration System, Attachment 8, Borate Mode of RMCS Operation
References:
OTO-MA-00008, Rapid Load Reduction, Rev 25 OTN-BG-00002, Reactor Makeup Control and Boron Thermal Regeneration System, Attachment 8, Borate Mode of RMCS Operation, Rev 41
JPM NO: Sim S1, Rev 2 Initial Conditions: Reactor Power is 100%.
A primary to secondary leak has been identified on S/G B.
A plant shutdown has been commenced IAW OTO-MA-00008, Rapid Load Reduction, to be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Initiating Cues: The Control Room Supervisor (CRS) directs you to borate the Reactor Coolant System (RCS) 250 gallons at a rate of 10 gpm to commence the plant shutdown, IAW OTO-MA-00008, Step 4.
Inform the CRS once boration has been commenced.
Notes: Use IC 161.
Fail the RMCS (Switch BG HS-25) to operate by selecting switch X02I16F to OFF Fail BG HIS-8104 to open as follows:
Insert Remote NG04CPF2, Value = Trip, Conditional of HWX01o134R eq 1 (Trips Breaker)
Fail Meter BG FI-183A to 0.0 on glass panel.
ENSURE SWITCH BG HS-25 IS SELECTED TO AUTO AFTER SIMULATOR IS TAKEN TO RUN FOLLOWING SWITCH ALIGNMENT FOR IC SETUP.
Task Standard: Upon completion of this JPM, the Applicant will have commenced a boration of the RCS from the RWST.
START TIME:
STOP TIME:
Page 1 of 8
JPM NO: Sim S1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE EVAULATOR NOTE:
OTO-MA-00008 gives 3 sets of directions to borate the RCS in Step 4. The first refers to of OTN-BG-00002; the second is the same method as the first, just with the steps embedded in Step 4; the third option given is emergency boration, with the required actions given in Step 4. The three options are bulleted, meaning they do not have to be performed in order.
S U
- 1. Obtain a verified Provide applicant with Applicant obtained working copy of procedure copy working copy of OTO- Comments:
OTO-MA-00008 MA-00008 S U
- 2. Borate from the Provide applicant with Applicant obtained BAST by performing procedure copy working copy of OTN- Comments:
any of the following: BG-00002, Att 8 Borate using OTN-BG-00002, Att 8 NOTE:
Applicant may use guidance as Step 4 provided in OTO MA-00008, Step 4, Borate to the VCT, starting at JPM Step 10 OR Step 4, Borate using Emergency Boration, starting at JPM Step 17
- Critical Step Page 2 of 8
JPM NO: Sim S1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 3. NOTE: This Applicant read note attachment provides Comments:
direction for frequently performed, nominal borations.
Prior to Step 1 (Att 8)
S U
Stop in Stop Step 1 (Att 8)
S U
Bor Sel, in Bor Step 2 (Att 8)
S U
- 6. Reset BG FY-110B, Applicant reset BG FY-BA Counter, to 000 110B, BA Counter, to Comments:
000 Step 3 (Att 8)
- Critical Step Page 3 of 8
JPM NO: Sim S1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 7. NOTE: When setting Applicant read note BG FY-110B, Comments:
allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delevered Prior to Step 4 (Att 8)
S U
- 8. Ensure BG FY-110B Applicant ensured BG is set to deliver the FY-110B set to deliver Comments:
desired amount of the desired amount of boron boron Step 4 (Att 8)
- Critical Step Page 4 of 8
JPM NO: Sim S1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 9. Place BG HS-26, Examiner Notes: Applicant placed BG RCS M/U Ctrl, in HS-26, RCS M/U Ctrl, Comments:
RUN 1) Flow Recorder, BG in RUN FR-110, indicates 0 Step 5 (Att 8) flow Applicant recognized that RMCS has
- 2) BG FY-110B is not malfunctioned and is changing (counting) not borating as expected Applicant moved to next option for boration: Either JPM Step 10 or 17 (Applicant will probably go to Step 17 as option starting at Step 10 parallels action taken in Steps 4-9)
S U
- 10. Borate to the VCT: Applicant placed BG HS-26 in STOP Comments:
Place RCS Makeup Control in STOP:
BG HS-26 Step 4.a S U
- 11. Borate to the VCT: Applicant placed BG HS-25 in BORATE Comments:
Place RCS Makeup Control Selector in BORATE:
BG HS-25 Step 4.b
- Critical Step Page 5 of 8
JPM NO: Sim S1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 12. Borate to the VCT: Applicant set BG FK-110 to borate at 10 Comments:
Set Boric Acid Flow gpm (BG FK-110 Controller to the Potentiometer set at desired flow rate 2.5)
BG FK-110 Step 4.c S U
- 13. Borate to the VCT: Applicant placed BG FK-110 in AUTO Comments:
Place BG FK-110 in AUTO Red AUTO light is lit on BG FK-110 Step 4.d S U
- 14. Borate to the VCT: Applicant reset BG FY-110B to 000 Comments:
Reset Boric Acid Counter to 000:
- BG FY-110B Step 4.e S U
- 15. Borate to the VCT: Applicant set BG FY-110B for the desired Comments:
Set BG FY-110B for gallons of boric acid to the desired gallons of be added - 250 gal boric acid to be added Step 4.f
- Critical Step Page 6 of 8
JPM NO: Sim S1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 16. Borate to the VCT: Examiner Notes: Applicant placed BG HS-26 in RUN Comments:
Place BG HS-26 in 1) Flow Recorder, BG RUN FR-110, indicates 0 Applicant recognized flow that RMCS has Step 4.g malfunctioned and is
- 2) BG FY-110B is not not borating as changing (counting) expected Applicant moved to next option for boration: Step 4, Borate using Emergency Boration S U
- 17. Borate using If CRS is asked for Applicant started one Emergency Boration: time to emergency Boric Acid Transfer Comments:
borate, inform Pump Start at least one operator to borate for Boric Acid Transfer 5 minutes - another Red light is lit and Pump: RO will calculate green light is not lit for amount required pump started
- BG HIS-5A
- BG HIS-6A Step 4.a S U
- 18. Borate using Examiner Note: Applicant opened Emergency Boration: Red light is not lit and Emergency Borate To Comments:
green light is not lit on Charging Pump Open Emergency BG HIS-8104 Suction:
Borate To Charging BG HIS-8104 Pump Suction:
Applicant recognized
- BG HIS-8104 If contacted, Primary that power has been OT reports that lost to BG HV-8104 Step 4.b breaker for valve is tripped and will not Applicant moved to reclose RNO for Step 4
- Critical Step Page 7 of 8
JPM NO: Sim S1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 19. Borate from the If CRS is asked for Applicant opened CCP RWST by performing time to emergency Suction From RWST: Comments:
the following: borate, inform BN HIS-112D operator to borate for BN HIS-112E
- a. Open CCP Suction 5 minutes - another From RWST: RO will calculate Red light is lit and amount required green light is not lit on
- BN HIS-112D both:
- BN HIS-112E
- BN HIS-112D
- BN HIS-112E RNO Step 4.a S U
the following: BG HIS-112B BG HIS-112C
- b. Close VCT Outlet Valves: Green light is lit and red light is not lit on
- BG HIS-112B both:
- BG HIS-112C
- BG HIS-112B
- BG HIS-112C RNO Step 4.a S U
- 21. Notifies CRS that CRS acknowledges Applicant informed boration has CRS that boration has Comments:
commenced from the commenced from the RWST RWST S U
- 22. The JPM is complete Record stop time on Page 1 Comments:
- Critical Step Page 8 of 8
Initial Conditions: Reactor Power is 100%.
A primary to secondary leak has been identified on S/G B.
A plant shutdown has been commenced IAW OTO-MA-00008, Rapid Load Reduction, to be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Initiating Cues: The Control Room Supervisor (CRS) directs you to borate the Reactor Coolant System (RCS) 250 gallons at a rate of 10 gpm to commence the plant shutdown, IAW OTO-MA-00008, Step 4.
Inform the CRS once boration has been commenced.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim S2, Rev 2 KSA No: 010A4.03 Revision: Feb 2013 KSA Rating: 4.0 / 3.8 Job
Title:
RO / SROI Task
Title:
Perform System Surveillance - BBHV8000A Stroke Test Validation Time: 10 minutes Learning Objective: T61.0110, LP-9, Obj B, Describe the purpose and operation of the following RCS components to include interlocks, controller operation and power supply: 5. Power Operated Relief Valves (PORVs)
The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: Time Critical:
Student Handouts: OSP-BB-V0001, RCS Valve Inservice Test, Rev 24 Calibrated Stop Watch
References:
OSP-BB-V0001, RCS Valve Inservice Test, Rev 24
JPM NO: Sim S2, Rev 2 Initial Conditions: Callaway Plant is in Mode 3.
Initiating Cues: The Control Room Supervisor (CRS) directs you to perform the Stroke Time Test for BBHV8000A, Reactor Coolant System Pressurizer PORV Block Valve, per OSP-BB-V0001, RCS Valve Inservice Test, Section 6.1.
The local position indication is NOT required for this test.
BBHV8000A, RCS PZR Out Pwr Oper Rlf HV, is NOT on its backseat.
All Prerequisites are satisfied.
Notes: Use IC 168 - Run with Sim JPM S6 Select Engineering Mode ME Schematics/BB/m22bb02_a (Pressurizer)
Right click on motor for bbhv8000a (located on top of Pressurizer)
Select RT04RC_HV8000A_MCTCLOSE - Insert Selected Value to 25 AND Select RT04RC_HV8000A_MCTOPEN - Insert Selected Value to 25 Task Standard: Upon completion of this JPM, the Applicant will have completed the Stroke Time Test for BBHV8000A per OSP-BB-V0001 and reported to the CRS that the Acceptance Criteria was not satisfied.
Start Time:
Stop Time:
PAGE 1 of 7
JPM NO: Sim S2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide Applicant with Applicant obtained working copy of procedure copy working copy of Comments:
- 2. Review Applicant reviewed Acceptance Criteria Acceptance Criteria Comments:
per Attachment 1 Section 3.1 S U
- 3. Review Precautions Applicant reviewed and Limitations Precautions and Comments:
Limitations Section 4.0 S U
- 4. Review Prerequisites Applicant reviewed Prerequisites Comments:
Section 5.0 S U
- 5. NOTE: The local Examiner Note: Applicant read note position indication is Comments:
performed every Given in initial cue that Given in initial cue that refuel prior to Mode 4 local position local position startup. These steps indication is not indication is not may be omitted when required for this test. required for this test.
performing this procedure in Mode 1, 2, or 3 on BBHV8000A.
Prior to 6.1
- CRITICAL STEP PAGE 2 of 7
JPM NO: Sim S2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 6. NOTE: If Applicant read note BBHV8000A, RCS Comments:
PZR Out Pwr Oper Rlf HV, is on its backseat for normal operations, the stroke close time will be from the backseat position and not from the OPEN (limit switch) position.
Prior to 6.1.1 S U
- 7. Using BB HIS-455A, Applicant ensured PZR PORV, ensure BBPCV0455A was Comments:
BBPCV0455A is closed closed BB HIS-455A green light is lit and the red Step 6.1.1 light is not lit S U
- 8. Ensure Applicant ensured BB BB HS-8000A, TRN A HS-8000A BLOCK PB Comments:
Cold O/P Bloc/Arm, is was depressed in the BLOCK position Step 6.1.2
- CRITICAL STEP PAGE 3 of 7
JPM NO: Sim S2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 9. Record Initial Remote Applicant recorded Position of BB HIS- Initial Remote Position Comments:
8000A, PZR PORV of BB HIS-8000A on Block Vlv, on Attachment 1 Attachment 1 Step 6.1.3 S U
- 10. If Position Indication Applicant N/Ad step Testing is scheduled, and proceeded to Step Comments:
perform the following: 6.1.5 Given in Initiating Cue that Position Indication Step 6.1.4 Testing is not scheduled S U
- 11. Using BB HIS-8000A, Applicant closed PZR PORV Block Vlv, BBHV8000A and Comments:
close BBHV8000A measured the elapsed and measure the time between pushing elapsed time the close pushbutton between pushing the and when the open close pushbutton and light went out when the open light goes out Measured stroke time was ~25 seconds Step 6.1.5
- CRITICAL STEP PAGE 4 of 7
JPM NO: Sim S2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 12. Record Observed Applicant recorded Stroke Time Closed Observed Stroke Time Comments:
for BBHV8000A, RCS Closed for PZR Out Pwr Oper Rlf BBHV8000A on HV, on Attachment 1 Attachment 1 (Observed stroke time should be ~25 sec)
Step 6.1.6 S U
- 13. RECORD Full Stroke Applicant recorded Remote Position of Full Stroke Comments:
BB HIS-8000A, PZR Remote Position of PORV Block Vlv, on Closed for Attachment 1 BB HIS-8000A on Attachment 1 Step 6.1.7 S U
- 14. If Position Indication Applicant N/Ad step Testing is scheduled, and proceeded to Step Comments:
record the Full Stroke 6.1.5 Local Position of BBHV8000A, RCS Given in Initiating Cue PZR Out Pwr Oper Rlf that Position Indication HV, on Attachment 1 Testing is not scheduled Step 6.1.8
- CRITICAL STEP PAGE 5 of 7
JPM NO: Sim S2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 15. Using BB HIS-8000A, Applicant opened PZR PORV Block Vlv, BBHV8000A and Comments:
open BBHV8000A measured the elapsed and measure the time between pushing elapsed time the open pushbutton between pushing the and when the closed open pushbutton and light went out when the closed light goes out BB HIS-8000A red light is lit and the Step 6.1.9 green light is not lit Measured stroke time was ~25 seconds S U
- 16. Record Observed Applicant recorded Stroke Time open for Observed Stroke Time Comments:
BBHV8000A, RCS open for BBHV8000A PZR Out Pwr Oper Rlf on Attachment 1 HV, on Attachment 1 (Observed stroke time should be ~25 sec)
Step 6.1.10
- CRITICAL STEP PAGE 6 of 7
JPM NO: Sim S2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 17. Perform the following: Applicant evaluated Retest will NOT be Observed Stroke Time Comments:
- a. Evaluate performed at this for BBHV8000A as Observed Stroke time. exceeding the Time against the maximum allowable Normal Stroke stroke time and NOT Time Range and meeting acceptance the Maximum criteria Allowable Stroke Time and determine if valve retest is required Applicant notified for BBHV8000A SM/CRS that valve stroke time did NOT
- b. If Observed meet acceptance Stroke Time for criteria BBHV8000A does NOT meet acceptance criteria, notify SM/CRS
- c. If retest is required, perform the retest per CA2716, Valve Retest Instructions Step 6.1.11 S U
- 18. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 7 of 7
Initial Conditions: Callaway Plant is in Mode 3.
Initiating Cues: The Control Room Supervisor (CRS) directs you to perform the Stroke Time Test for BBHV8000A, Reactor Coolant System Pressurizer PORV Block Valve, per OSP-BB-V0001, RCS Valve Inservice Test, Section 6.1.
The local position indication is NOT required for this test.
BBHV8000A, RCS PZR Out Pwr Oper Rlf HV, is NOT on its backseat.
All Prerequisites are satisfied.
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: Sim S3, Rev 2 KSA No: 013A4.01 Revision: Feb 2013 KSA Rating: 4.5 / 4.8 Job
Title:
RO / SROI / SROU Duty: Engineered Safety Features Actuation System (ESFAS)
Task
Title:
Perform Attachment A of E-0 Validation Time: 15 minutes Learning Objective: T61.003D, LP D-4, Obj L, Outline procedure flowpath including major system and equipment operation in accomplishing the goal of E-0 The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: X Time Critical:
Student Handouts: E-0, Reactor Trip or Safety Injection, Attachment A, Rev 15
References:
E-0, Reactor Trip or Safety Injection, Attachment A, Rev 15
JPM NO: Sim S3, Rev 2 Initial Conditions: Callaway has experienced a reactor trip from full power due to a Loss of Coolant Accident.
The control room is responding to the trip per E-0, Reactor Trip or Safety Injection.
Currently the crew is at Step 5 of E-0.
Initiating Cues: The CRS directs you to perform Attachment A of E-0 and report to him when complete.
Note: Use IC 163.
Insert the following:
- Malf/SB/CISA_A_Block_Auto/Block/Insert
- Malf/EG/PEG01A_A/Inhibit/Insert
- Malf/EG/PEG01C_A/Inhibit/Insert
- Remote/GN/SGN01A_2/Inhibit/Insert
- Malf/BB/BB002_A/5000/Insert Trip RCPs when RCS pressure lowers to <1425 psig Freeze the simulator until the candidate begins the JPM NOTE: Run following lesson each time IC is restored:
Lesson/All/Generic/1302_Sifts/Sift20120320.lsn Task Standard: Upon completion of this JPM, the Applicant will have performed E-0, Attachment A, with the following actions completed:
- A or C CCW Pump started
- A Containment Cooler started
- CIS A initiated
- CCW Flow isolated from Spent Fuel Pool Heat Exchangers
- B Spent Fuel Pool Cooling Pump secured Start Time:
Stop Time:
Page 1 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide Applicant with Applicant obtained working copy of E-0, procedure copy working copy of E-0, Comments:
Attachment A Attachment A S U
- 2. Check charging Examiner Note: Applicant checked pumps: both CCPs running by Comments:
SI signal will stop NCP verifying both BG HIS-
- a. CCPs - both 1A and 2A have red running light on and green light off
- BG HIS-1A AND
- BG HIS-2A NCP was not running
- b. Stop NCP: by verifying BG HIS-3 green light and yellow
- BG HIS-3 light were lit and the Step A1 red light was off S U
pumps running
- RHR pumps lights off both running EJ HIS-1 and 2 Step A2
- Critical Step Page 2 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- a. CCPs to boron inj a. Boron Inj Hdr Flow and SI pump header flow indicated on discharge flow indicated EM FI-917A and B indicated and RCS pressure
- b. RCS pressure b. RCS WR Press less than 1700 indicated on Applicant determined psig BB PR-403 RCS pressure was not less than 325 psig
- c. SI Pump Disch Flow indicated on
- d. RCS pressure -
less than 325 psig Step A3 S U
- 5. CAUTION: If offsite Applicant read caution power is lost after SI Comments:
reset, manual action may be required to restart safeguards equipment.
Prior to Step A4
- Critical Step Page 3 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- EF HIS-55A and 1) EF HIS-55A has red 56A light on and green light off with ~140 psig Step A4 discharge pressure indicated
- 2) EF HIS-56A has red light on and green light off with ~140 psig discharge pressure indicated S U
CCW Pumps - one in both Red and running in each train Yellow train
- Red train: EG HIS- Manually started either 21 or 23 running A pump (EG HIS-21 or B pump (EG HIS-
- Yellow train: EG 23)
HIS-22 or 24 running EG HIS-21 and 23 have green lights lit and red lights not lit EG HIS-22 has red light lit and green light not lit After starting pump, Step A5.a EG HIS-21 or EG HIS-23 red light is lit and green light is not lit
- Critical Step Page 4 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
valves for one 1) EG ZL-15 and 53 aligned properly operating CCW pump have green lights lit open and red lights off
- EG ZL-15 and 53 2) EG ZL-16 and 54 have red lights lit and
- OR green lights off
- EG ZL-16 and 54 Step A5.b S U
- EG HIS-101 1) Both EG HIS-101 and 102 have both
- EG HIS-102 green and red lights on Step A5.c 2) After operating HISs, both EG HIS-101 and 102 have red lights on green lights off S U
valves
- 1) EC HIS-11 green
- EC HIS-11 light is lit and the red light is not lit
- EC HIS-12
- 2) EC HIS-12 red light Step A 5.d and green light are both lit
- 3) After closing EC HIS-12, the green light is lit and the red light is not lit
- Critical Step Page 5 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 11. Stop spent fuel pool Applicant stopped EC cooling pumps HIS-28 Comments:
- EC HIS 27 1) EC HIS-27 has green light on red light
- EC HIS 28 off Step A5.e 2) EC HIS-28 has red light on green light off
- 3) After operating HIS, EC HIS-28 has green light on and red light off S U
- 12. Record the time Applicant recorded spent fuel pool current time Comments:
cooling pump secured Step A5.f S U
- 13. Monitor time since CRS acknowledges Applicant moved to CCW flow isolated to and assigns this step next step Comments:
SFP HX less than 4 to another RO to hours perform Step A5.g S U
- 14. Check Containment Applicant selected cooler fans running in slow speed on GN HS- Comments:
slow speed 5 and went to run on GN HIS-5
- GN HIS-9
- GN HIS-17 1) Containment cooler
- GN HIS-5 fans B/C/D indicate
- GN HIS-13 red run light for slow speed with all other Step A6 lights out
- 2) After operating HSs, GN HIS-5, red run light for slow is lit with other lights off
- Critical Step Page 6 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 15. Check containment Applicant checked all hydrogen mixing fans four H2 mixing fans Comments:
running in slow speed running in slow speed
- GN HIS-2 GN HIS-2, 4, 1 and 3
- GN HIS-4 have red slow lights lit
- GN HIS-1 and all other lights off
- GN HIS-3 Step A7 S U
- 16. Check if Containment Examiner Note: Applicant checked that Spray should be CS should not be Comments:
actuated Containment pressure actuated due to indicated on Containment pressure GN PR-934 <27 psig and went to Step A9 Step A8
- Critical Step Page 7 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 17. Check if main Examiner Notes: Applicant checked that steamlines should be main steamlines Comments:
isolated 1) Steamline pressure should not be isolated
- a. Check for any of indicated on AB PR- due to containment the following: 514 and AB PR-535 pressure <17 psig and
- Containment main steam pressure pressure-greater 2) Main steamline not <615 psig (MSLIS than 17 psig isolation may have setpoint) and went to OR occurred if SG Step A10
- GN PR-934 pressure is <615 psig indicates or containment OR containment pressure is >17 psig pressure-has been Applicant verified greater than 17 MSIVs and Bypass psig valves were closed if OR main steamline isolation had occurred
- Steamline pressure-less than 615 psig OR
- 18. Check ECCS valves Applicant checked
- proper emergency ECCS valves are in Comments:
alignment for ESFAS proper emergency status panels SIS alignment by verifying sections: SA066X and Y white lights are lit for SIS
- SA066X White sections lights - ALL LIT
- SA066Y White lights - ALL LIT Step A10
- Critical Step Page 8 of 9
JPM NO: Sim S3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 19. Check Containment Applicant checked Isolation Phase A for CISA and manually Comments:
ESFAS status panels actuated Train A using CISA sections: SB HS-47
- SA066X White 1) SA066Y white lights lights - ALL LIT lit for CISA; SA066X red light lit for CISA
- SA066Y White lights - ALL LIT 2) SA066X white lights lit after actuated from SB HS-47 Step A11 S U
status panels SG blowdown isolation SGBSIS sections: by verifying SA066X and Y white lights are
- SA066X White lit for S/G B/D isolation lights - ALL LIT
- SA066Y White lights - ALL LIT Step A12 S U
- 21. The JPM is complete Record stop time on Page 1 Comments:
- Critical Step Page 9 of 9
Initial Conditions: Callaway has experienced a reactor trip from full power due to a Loss of Coolant Accident.
The control room is responding to the trip per E-0, Reactor Trip or Safety Injection.
Currently the crew is at Step 5 of E-0.
Initiating Cues: The CRS directs you to perform Attachment A of E-0 and report to him when complete.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim S4, Rev 2 KSA No: 007A1.01 Revision: Feb 2013 KSA Rating: 2.9 / 3.1 Job
Title:
RO Task
Title:
Drain PRT To The Containment Normal Sump Validation Time: 8 minutes Learning Objectives:T61.0110, LP-9, Obj B, Describe the purpose and operation of the following RCS components to include interlocks, controller operations and power supply: 9. Pressurizer Relief Tank (PRT); and Obj C, Draw, Label and Explain a one line diagram of the RCS to include the components listed in objective B showing system alignment under the following conditions: Normal operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: Time Critical:
Student Handouts: OTN-BB-00004, Pressurizer Relief Tank, Rev 35
References:
OTN-BB-00004, Pressurizer Relief Tank, Rev 35
JPM NO: Sim S4, Rev 2 Initial Conditions:
- The plant is at 50% power.
- Due to valve testing, the Pressurizer Relief Tank (PRT) level is at 81%.
- MCB Annunciator 34F, PRT LEV HILO, is currently in alarm.
Initiating Cues: The Control Room Supervisor (CRS) directs you to lower PRT level to clear Ann 34F, PRT LEV HILO, by draining it to the Containment Normal Sump using OTN-BB-00004, Pressurizer Relief Tank, Section 5.6.
Stop PRT draining and notify the CRS when Ann 34F clears.
Notes: Use IC 162 Insert Browser/Plant Parameters/BB/TAPRTL Input Selected Value to .81 and Insert (This will raise PRT level to 81% and activate Ann 34F, PRT LEV HILO)
Task Standard: Upon completion of this JPM, the Applicant will have drained the PRT to the Containment Normal Sump to clear Ann 34F without reactuating Ann 34F for PRT low level (64%).
Start Time:
Stop Time:
Page 1 of 8
JPM NO: Sim S4, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide Applicant with Applicant obtained working copy of OTN- procedure copy working copy of OTN- Comments:
BB-00004 BB-00004 S U
- 2. Review Precautions Applicant reviewed and Limitations Precautions and Comments:
Limitations S U
concentration is less concentration was less than 4% than 4% (given in Initial Conditions) and Step 5.6.1 proceeds to Step 5.6.2 S U
- 4. Ensure PRT level is Examiner Note: Applicant ensured maintained above PRT level was above Comments:
19% until RCS has BB LI-470 indicates 19%
been degasified 81%
Step 5.6.2
- Critical Step Page 2 of 8
JPM NO: Sim S4, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 5. Ensure RCS is Examiner Note: Applicant ensured depressurized prior to PRT was not lowered Comments:
lowering PRT level Ann 34F,PRT LEV to less than 64% with below 64% HILO, will clear at 80% the RCS pressurized Step 5.6.3 S U
PRT hydrogen <4% before venting concentration is <4%
Step 5.6.4 S U
ensure closed BBHV8031 BB HIS-8031 green light is lit and the red Step 5.6.5 light is not lit
- Critical Step Page 3 of 8
JPM NO: Sim S4, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 8. Ensure BBPCV8034, After contacted, POT Applicant contacted RCS PRT N2/Serv responds that Primary Operations Comments:
Gas Sply PCV, is set BBPCV8034 is set to Technician (POT) to to control between 3 3.5 psig ensure BBPCV8034 and 4 psig (AB 2000 was set to control RM1322) between 3 and 4 psig Step 5.6.6 S U
- 9. Using BB HIS-8026, Examiner Note: Applicant opened PRT N2 Sply Inner Applicant must first BBHV8026 using BB Comments:
Ctmt Iso Vlv, open press Normal to get HIS-8026 BBHV8026 out of Hard Close BB HIS-8026 red light Step 5.6.7 is lit and the green light is not lit S U
- 10. Using BB HIS-8027, Examiner Note: Applicant opened PRT N2 Sply Outer Applicant must first BBHV8027 using BB Comments:
Ctmt Iso Vlv, open press Normal to get HIS-8027 BBHV8027 out of Hard Close BB HIS-8027 red light Step 5.6.8 is lit and the green light is not lit
- Critical Step Page 4 of 8
JPM NO: Sim S4, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 11. CAUTION: If asked, Applicant read caution Containment normal Containment Sump Comments:
sump pumps do not lineup has been have capacity to keep checked up with PRT outlet valves. Containment sump lineup should be checked and level monitored to prevent overflowing sump.
Prior to 5.6.9 S U
- 12. Open one PRT outlet If asked, local Applicant opened valve to containment operation of valve is either BBHV8037A OR Comments:
normal sump: not desired BBHV8037B
- BBHV8037A, by If BBHV8037A operating from opened, BB HIS-RL021 using BB 8037A red light is lit HIS-8037A, PRT and green light is not Drn To Ctmt Norm lit Sump If BBHV8037B OR opened, BB HIS-8037B red light is lit
- BBHV8037B, by and green light is not operating from lit RL021 using BB HIS-8037B, PRT Drn To Ctmt Norm Sump Step 5.6.9
- Critical Step Page 5 of 8
JPM NO: Sim S4, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
instrumentation or computer point:
- BBLI0470, RCS Pressurizer Relief Tank Level Ind (RL021)
- REL0485A, PZR Relief Tank Level (computer point)
Step 5.6.10 S U
- 14. Monitor Containment Applicant monitored Normal Sump level containment normal Comments:
using control room sump level instrumentation or computer points:
- LF LI-9, Ctmt Norm Sump Lev (RL018)
- LF LI-89, Ctmt Norm Sump Lev (RL023)
- LFL0009, Ctmt Normal Sump A/B Lev (computer point)
- LFL0089, Ctmt Normal Sump A/B Lev (computer point)
Step 5.6.11
- Critical Step Page 6 of 8
JPM NO: Sim S4, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 15. When containment Applicant monitored normal sump level containment normal Comments:
reaches 30 inches, or sump level and PRT PRT reaches desired level for indications to level, close: stop PRT draining
- BBHV8037A, by Ann 34F has cleared operating from RL021 using BB Applicant closed PRT HIS-8037A, PRT drain valve opened in Drn To Ctmt Norm JPM Step 12 Sump If BBHV8037A is OR closed, BB HIS-8037A green light is lit and
- BBHV8037B, by the red light is not lit operating from RL021 using BB If BBHV8037B is HIS-8037B, PRT closed, BB HIS-8037B Drn To Ctmt Norm green light is lit and Sump the red light is not lit Step 5.6.12 S U
- 16. If additional PRT Examiner Note: Applicant determined draining is desired, additional draining was Comments:
wait until sump level Step would only be not required reaches a low level, performed if and return to Step containment normal 5.6.9 sump level reached 30 inches - see Step 5.6.12 (JPM Step 15)
Step 5.6.13
- Critical Step Page 7 of 8
JPM NO: Sim S4, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 17. If BBHV8037A or Applicant N/Ad this BBHV8037B were step and proceeded to Comments:
operated manually Step 5.6.15 as valves were not operated Step 5.6.14 manually S U
- 18. Using BB HIS-8026, Applicant closed PRT N2 Sply Inner BBHV8026 using BB Comments:
Ctmt Iso Vlv, close HIS-8026 BBHV8026 BB HIS-8026 green Step 5.6.15 light is lit and the red light is not lit S U
- 19. Using BB HIS-8027, Applicant closed PRT N2 Sply Outer BBHV8027 using BB Comments:
Ctmt Iso Vlv, close HIS-8027 BBHV8027 BB HIS-8027 green Step 5.6.16 light is lit and the red light is not lit S U
- 20. The JPM is complete Record stop time on Page 1 Comments:
- Critical Step Page 8 of 8
Initial Conditions:
- The plant is at 50% power.
- Due to valve testing, the Pressurizer Relief Tank (PRT) level is at 81%.
- MCB Annunciator 34F, PRT LEV HILO, is currently in alarm.
Initiating Cues: The Control Room Supervisor (CRS) directs you to lower PRT level to clear Ann 34F, PRT LEV HILO, by draining it to the Containment Normal Sump using OTN-BB-00004, Pressurizer Relief Tank, Section 5.6.
Stop PRT draining and notify the CRS when Ann 34F clears.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim S5, Rev 2 KSA No: 059A2.07 Revision: Feb 2013 KSA Rating: 3.0 / 3.3 Job
Title:
RO / SROI Task
Title:
Transfer A MFP Speed Control/Pump Trip Validation Time: 11 Minutes Learning Objective: T61.0110, LP-23, Obj H, Identify the MFW MCB controls, indications, and alarms and Describe how each is used to monitor and/or control the MFW System The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: X Time Critical:
Student Handouts: OTN-AE-00001 Addendum 2, MFP (PAE01A/B) Operations, Rev 20 OTA-RK-00026, Addendum 122C, MFT A Thrust Bearing High Oil Temp, Rev 0
References:
OTN-AE-00001 Addendum 2, MFP (PAE01A/B) Operations, Rev 20 OTA-RK-00026, Addendum 122C, MFT A Thrust Bearing High Oil Temp, Rev 0
JPM NO: Sim S5, Rev 2 Initial Conditions: The following plant conditions exist:
- Reactor power is 50%
- A and B Main Feed Pumps are in service
- It has been determined that FC SK-509B requires Corrective Maintenance and needs to be removed from service
- The Plant Computer is NOT available Initiating Cues: The Control Room Supervisor (CRS) directs you to transfer A MFP from AUTO to MANUAL on the GE Controller (FC HK-88) in accordance with Section 5.3 of OTN-AE-00001, Add 2, MFP (PAE01A/B) Operations.
Notes: Use IC 162 (50%).
Insert Cry Wolf Alarms/RK/Annun_C122/ON/Conditional HWX05O124W eq 1/30 sec delay/Insert Task Standard: Upon completion of this JPM, the Applicant will have transferred control of A MFP speed controller from auto to manual and then tripped A MFP due to high thrust bearing oil temperature.
Start Time:
Stop Time:
Page 1 of 7
JPM NO: Sim S5, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtained a verified Provide Applicant with Applicant obtained working copy of OTN- procedure copy working copy of OTN- Comments:
AE-00001, Add 2 AE-00001, Add 2 S U
- 2. Review Precautions Applicant reviewed and Limitations Precautions and Comments:
Limitations Section 3.0 S U
transferred to manual control in either order.
Prior to 5.3 S U
- 4. If desired, place FC It is desired to leave Applicant left FC SK-SK-509A, MFP Turbs FC SK-509A, MFP 509A, MFP Turbs Comments:
Master Speed Ctrl, in Turbs Master Speed Master Speed Ctrl, in MAN Ctrl, in AUTO AUTO Step 5.3.1
- Critical Step Page 2 of 7
JPM NO: Sim S5, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
Ctrl, in MAN Speed Ctrl, in MAN FC SK-509B is in manual with red Step 5.3.2 manual light lit and red auto light off S U
- 6. Using FC HK-88, Applicant nulled FC EI-MFP Turb A Man 88 using FC HK-88 Comments:
Speed Ctrl, Null FC EI-88, MFP A FC EI-88 indicates 0 Man/Auto Sig Match Step 5.3.3 S U
Ctrl Transfer, in MAN Speed Ctrl Transfer, in MAN FC HIS-88 is in Step 5.3.4 manual with white manual light lit and yellow auto light off S U
- 8. Maintain speed using Applicant maintained FC HK-88, MFP Turb speed using FC HK- Comments:
A Man Speed Ctrl 88, MFP Turb A Man Speed Ctrl, at approximately 3840 RPM on FC SI-33 Step 5.3.5
- Critical Step Page 3 of 7
JPM NO: Sim S5, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 9. Annun 122C, MFT A Once Applicant Applicant Thrust Bearing High locates OTA-RK- acknowledged Annun Comments:
Oil Temp, alarms 00026, Add 122C, 122C provide Applicant with copy of Addendum 122C S U
- 10. Monitor thrust bearing SOT reports Applicant dispatched oil temperature using temperature is 182°F Secondary Operations Comments:
either of the following: and rising Technician (SOT) to locally check
- FCTIS0031, Thrust temperature Brg Oil Drn TIS (Local)
- Computer point NOTE: Computer point FCT0031, MFT A not available due to T-Brg Oil Temp unavailability of plant computer (given in Step 3.1 initial conditions)
S U
- 11. Directs SOT to check SOT reports in Applicant directed in service Closed service Closed SOT to check in Comments:
Cooling Water L-O Cooling Water L-O service Closed Cooling Cooler inlet and outlet Cooler inlet and Water L-O Cooler inlet isolation valves open outlet isolation and outlet isolation at MFP A valves open at MFP valves open at MFP A A
Step 3.2.1
- Critical Step Page 4 of 7
JPM NO: Sim S5, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 12. The adjusting knob Applicant read note for FCTIC0055, A Comments:
MFP Lube Oil Clrs CLCW Out Temp Ind Ctrl, is located inside the controller box.
Counter-clockwise rotation results in more cooling water flow. FCTV0055A, A MFP Turb Lube Oil Clr A CLCW Out Temp Vlv, and FCTV0055B, A MFP Turb Lube Oil Clr B CLCW Out Temp Vlv, are fail open valves.
Note prior to Step 3.2.2 S U
- 13. If desired, adjust SOT reports Applicant directed FCTIC0055 to maximum flow is SOT to adjust Comments:
increase cooling through the cooler FCTIC0055 to water flow and temperature on increase cooling water FCTIS0031 is 189°F flow and rising Step 3.2.2
- Critical Step Page 5 of 7
JPM NO: Sim S5, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 14. If desired to control It is not desired to Applicant N/Ad this lube oil temperature manually control step and proceeded to Comments:
manually, perform the lube oil temperature Step 3.3 following:
a) Fail air to FCTV0055A OR FCTV0055B b) Take manual control of FCTV0055A OR FCTV0055B c) Use local temperature indicator, FCTIS0065 for temperature indication Step 3.2.3 S U
- 15. If transfer to the SOT reports that the Applicant directed standby oil cooler is standby oil cooler is SOT to transfer to the Comments:
desired, Refer To tagged out standby oil cooler OTN-AE-00001, Feedwater System NOTE: Operator may determine to trip the feed pump at this time Step 3.3
- Critical Step Page 6 of 7
JPM NO: Sim S5, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 16. If thrust bearing oil Applicant identified temperature is > need to perform Step Comments:
180°F and oil system 3.4 and that turbine flows and load is already < 60%
temperatures are normal, perform the following:
Runback turbine load to < 60%
Step 3.4.1 S U
HIS-18, MFP Turb A Trip, on Panel RL005 Step 3.4.2 Annun 120A, MFP A Trip, is lit S U
- 18. Check that MFP B is S/G levels are stable Applicant stabilized controlling feedwater at 50% S/G levels using MFP Comments:
flow automatically to B maintain steam generator levels at the programmed level Step 3.4.3 S U
- 19. The JPM is complete Record stop time on Page 1 Comments:
- Critical Step Page 7 of 7
Initial Conditions: The following plant conditions exist:
- Reactor power is 50%
- A and B Main Feed Pumps are in service
- It has been determined that FC SK-509B requires Corrective Maintenance and needs to be removed from service
- The Plant Computer is NOT available Initiating Cues: The Control Room Supervisor (CRS) directs you to transfer A MFP from AUTO to MANUAL on the GE Controller (FC HK-88) in accordance with Section 5.3 of OTN-AE-00001, Add 2, MFP (PAE01A/B) Operations.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim S6, Rev 2 KSA No: 062K1.04 Revision: Feb 2013 KSA Rating: 3.7 / 4.2 Job
Title:
RO / SROI Task
Title:
Perform Operational Testing of the Alternate Emergency Power Source Validation Time: 15 minutes Learning Objectives: T61.0110, LP-78, Obj B, Identify the Alternate Emergency Power Supply (AEPS) system Main Control Board (MCB) controls, alarms and indications; and Obj C, Describe the purpose, location and operation of the following Alternate Emergency Power Supply (AEPS) system components and subsystems: 1. AEPS diesel generators The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: Time Critical:
Student Handouts: OTS-PA-00001, Operation And Testing Of The Alternate Emergency Power Source, Rev 10
References:
OTS-PA-00001, Operation And Testing Of The Alternate Emergency Power Source, Rev 10
JPM NO: Sim S6, Rev 2 Initial Conditions: The plant is in Mode 3.
Initiating Cues: The Control Room Supervisor (CRS) directs you to perform an online test of EDGPA5004, AEPS Diesel Generator #4, in accordance with OTS-PA-00001, Operation And Testing Of The Alternate Emergency Power Source, Section 5.10.
The CRS directs you to take one set of readings on Attachment 5 and then secure EDGPA5004.
The Outside OT has been briefed and is at EDGPA5004 to assist in the diesel test.
All Prerequisites are satisfied.
Notes: Perform with Sim S2 (IC-168).
Task Standard: Upon completion of this JPM, the Applicant will have performed an online test of EDGPA5004, AEPS Diesel Generator #4, by starting and stopping the Diesel Generator from PBXY0001, AEPS Computer Interface, in the Control Room.
Start Time:
Stop Time:
Page 1 of 8
JPM NO: Sim S6, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide applicant with Applicant obtained working copy of OTS- procedure copy working copy of OTS- Comments:
PA-00001 PA-00001 S U
- 2. Review Precautions Applicant reviewed and Limitations Precautions and Comments:
Limitations S U
- 3. Review Prerequisites Applicant reviewed Prerequisites Comments:
S U
- 4. NOTE: Diesels are Applicant read note operated from Comments:
PBXY0001, AEPS Computer Interface, in the Control Room.
Similar controls are available on the Master HMI (PA50102 cubicle) in the PA501 building.
The local control panel on the switchgear requires a key to place it in service.
Sections 5.7 through 5.10 may be performed concurrently.
Prior to 5.10.1
- Critical Step Page 2 of 8
JPM NO: Sim S6, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 5. Check Pre-start Pre-start checks are Applicant checked that checks have been complete pre-start checks were Comments:
performed complete Step 5.10.1 S U
- 6. On the Main Screen Applicant pressed icon on PBXY0001, press for PA50107 on Comments:
icon for PA50107 for PBXY0001 AEPS Diesel Generator #4 Generator #4 EDGPA5004 Control Step 5.10.2 Panel is now displayed S U
- 7. Check the diesel Applicant checked status lights are status lights were Comments:
green under the green under the alarm alarm monitoring monitoring section of section of the pop-up the pop-up screen screen. Any status light not green must be evaluated by the CRS prior to continuing.
Step 5.10.3
- Critical Step Page 3 of 8
JPM NO: Sim S6, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 8. In the pop-up Applicant pressed the window, press the button On Line Gen Comments:
button On Line Gen Test Start in the pop-Test Start up window Step 5.10.4 S U
- 9. NOTE: The next step Applicant read note will start the diesel Comments:
generator. The generator will automatically synchronize to the PA501 bus. The output breaker will close automatically when they are synchronized. The diesel will then ramp up to 2000 KW automatically at a pre-set rate and remain at that load.
Prior to 5.10.5 S U
- 10. In the confirmation Applicant pressed the pop-up window, button Yes Start Comments:
press the button Yes Generator in the Start Generator confirmation pop-up window Start 5.10.5
- Critical Step Page 4 of 8
JPM NO: Sim S6, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 11. Check the diesel Applicant checked that started the diesel started Comments:
Step 5.10.6 Engine speed indicates 1800 RPM and MegaWatts indicate 2.00 MW S U
- 12. Locally check the The OOT reports the Applicant contacted ventilation dampers ventilation dampers the Outside Comments:
have opened are open Operations Technician (OOT) to verify the Step 5.10.7 ventilation dampers were open S U
- 13. Check breaker Applicant checked PA50107 closed breaker PA50107 Comments:
closed Step 5.10.8 Breaker indication for PA50107 is lit red
- Critical Step Page 5 of 8
JPM NO: Sim S6, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 14. Check diesel You are directed to Applicant recorded 1 parameters come into take the Attachment set of Attachment 5 Comments:
normal range per 5 readings from readings as directed in Attachment 5 Panel PBXY0001 in Initiating Cues the Control Room Step 5.10.9 Indications are:
Oil Press 57 Water Temp 183 Battery Volt 26 Engine RPM 1800 Volts A 13.8 Volts B 13.8 Volts C 13.8 Hz 60.0 Amps A 86 Amps B 86 Amps C 86 KiloWatts 2000 KiloVars 500 Power Factor -.97 S U
- 15. Record readings on Applicant went to Step Attachment 5 at 1- 5.10.11 to secure from Comments:
hour intervals the online test Step 5.10.10
- Critical Step Page 6 of 8
JPM NO: Sim S6, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 16. NOTE: AEPS diesels Applicant read note go into a 5-minute and caution Comments:
cooldown period after Stop command is given. A Cool Down Time Left timer shows the time remaining in the 5-minute period (in seconds).
CAUTION: The 286 relay must be reset prior to shutting down any of the remaining diesels to ensure a minimum of three diesels remain functional at all times.
Prior to 5.10.11 S U
- 17. To secure from the Examiner Note: Applicant pressed Online test, press Button PA50107 will button PA50107 for Comments:
button PA50107 for not need to be AEPS Diesel AEPS Diesel pressed unless Generator #4 Generator #4 Applicant went back to the AEPS PBXY0001 Step 5.10.11 Main Screen
- Critical Step Page 7 of 8
JPM NO: Sim S6, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 18. Press the button Applicant pressed the Generator Normal button Generator Comments:
Stop Normal Stop Step 5.10.12 S U
- 19. Confirm the Applicant confirmed command by the command by Comments:
pressing the button pressing the button Yes Stop Generator Yes Stop Generator Step 5.10.13 S U
- 20. Check breaker Applicant checked PA50107 opened breaker PA50107 Comments:
opened Step 5.10.14 Breaker indication for PA50107 is lit green S U
- 21. The JPM is complete Record stop time on Page 1 Comments:
- Critical Step Page 8 of 8
Initial Conditions: The plant is in Mode 3.
Initiating Cues: The Control Room Supervisor (CRS) directs you to perform an online test of EDGPA5004, AEPS Diesel Generator #4, in accordance with OTS-PA-00001, Operation And Testing Of The Alternate Emergency Power Source, Section 5.10.
The CRS directs you to take one (1) set of readings on Attachment 5 and then secure EDGPA5004.
The Outside OT has been briefed and is at EDGPA5004 to assist in the diesel test.
All Prerequisites are satisfied.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim S7, Rev 2 KSA No: 005K4.11 Revision: Feb 2013 KSA Rating: 3.5 / 3.9 Job
Title:
RO / SROI Task
Title:
Transfer to Cold Leg Recirculation Validation Time: 15 minutes Learning Objective: T61.003D, LP D-11, Obj G, Outline procedureal flowpath including major system and equipment operation in accomplishing the goal of ES-1.3, Transfer to Cold Leg Recirculation The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: X Time Critical:
Student Handouts: ES-1.3, Transfer To Cold Leg Recirculation, Rev 10
References:
ES-1.3, Transfer To Cold Leg Recirculation, Rev 10 APA-ZZ-00395, Significant Operator Response Timing, Rev 21
JPM NO: Sim S7, Rev 2 Initial Conditions: A large break Loss of Coolant Accident has occurred.
The crew was performing the actions of E-1, Loss of Reactor Or Secondary Coolant, when MCB Annunciator 47C, RWST LOLO 1 AUTO XFR, alarmed.
Initiating Cues: The CRS directs you to place ECCS in cold leg recirculation in accordance with ES-1.3, Transfer To Cold Leg Recirculation.
Notify the Control Room Supervisor when Step 3 is complete.
Note: Use IC 169 (Built from IC-163 used for Sim S3)
After the completion of JPM Sim 3, perform the following:
Insert Malfunction SB/K741TrainA/Fail_As_Is Run/Freeze Insert Plant Parameters BN/TBN01TAZTLIL/Value = 16.5 Verify Annun 47C is in alarm and that ECCS auto swapover is complete Freeze the simulator Task Standard: Upon completion of this JPM, the applicant will have aligned the RHR pumps for cold leg recirculation and aligned the SI pumps and CCPs suction to the RHR pumps IAW ES-1.3.
Start Time:
Stop Time:
PAGE 1 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide applicant with Applicant obtained working copy of procedure copy working copy of Comments:
- 2. Reset SI: Applicant reset SI Comments:
SB HS-42A Auto SI block light is lit SB HS-43A and red SI actuate light is off on Panel SB069 Step 1 S U
exchangers: 102 valves were open
- a. Check CCW to Red lights are lit and RHR HX valves - green lights are not lit open for EG HIS-101 and 102
- EG HIS-101
- EG-HIS-102 Step 2.a S U
exchangers: were closed
- b. Check Spent Fuel Green lights are lit and Pool HX CCW red lights are not lit for outlet valves - EC HIS-11 and 12 closed
- EC HIS-11
- EC-HIS-12 Step 2.b
- CRITICAL STEP PAGE 2 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
exchangers: each train
- c. Check CCW Red light is lit and pumps - one green light is not lit for running in each EG HIS-21 and EG train HIS-22
- Red Train:
EG HIS-21 EG HIS-23
- Yellow Train:
EG HIS-22 EG HIS-24 Step 2.c S U
- 6. CAUTION: Any Applicant read caution pumps taking suction Comments:
from the RWST should be stopped if RWST level lowers to 6%.
Prior to Step 3
- CRITICAL STEP PAGE 3 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
suction switchover -
a.1 Check RHR complete for RHR pump automatic Pump A suction switchover - RHR Pump A - red complete light is not lit and green light is lit for EJ
- RHR Pump A: HIS-8811A; green light Containment is not lit and red light is Recirc Sump To lit for BN HIS-8812A RHR Pump A Suction-Open Applicant went to Step EJ HIS-8811A 3.a.1) RNO to manually align Train A
S U
a) Stop RHR Pump EJ HIS-1 red light is A: not lit and green light is lit
- EJ HIS-1 Step 3.a RNO 1)a
- CRITICAL STEP PAGE 4 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 9. Manually Align RHR Applicant closed BN Pump A suction: HIS-8812A Comments:
b) Close RWST To BN HIS-8812A green RHR Pump A light is lit and red light Suction: is not lit
- BN HIS-8812A Step 3.a RNO 1)b S U
- 10. Manually Align RHR Applicant opened EJ Pump A suction: HIS-8811A Comments:
c) Open Containment EJ HIS-8811A red light Recirc Sump To is lit and green light is RHR Pump A not lit Suction:
- EJ HIS-8811A Step 3.a RNO 1)c
- CRITICAL STEP PAGE 5 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
suction switchover -
a.2 Check RHR complete for RHR pump automatic Pump B suction switchover - RHR Pump B - red complete light is lit and green light is not lit for EJ
- RHR Pump B: HIS-8811B; green light Containment is lit and red light is not Recirc Sump To lit for BN HIS-8812B RHR Pump B Suction-Open EJ HIS-8811B
- CRITICAL STEP PAGE 6 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
running
- EJ HIS-1 Red light is lit and
- EJ HIS-2 green light is no lit for EJ HIS-2 Step 3.b Green light is lit and red light is not lit for EJ HIS-1 Applicant started RHR Pump A using EJ HIS-1 After starting RHR Pump A, EJ HIS-1 red light is lit and green light is not lit S U
satisfied pump discharge flow
- SI pump discharge
- flow indicated Flow is indicated on EM FI-918 EM FI-918 and 922 EM FI-922 Step 3.c
- CRITICAL STEP PAGE 7 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
valves, EM HIS-8814A Close both the AND EM HIS-8814B following:
- 1) Place power lockout for BN HIS- Performed the 8813A in non iso following:
position:
BN HIS-8813A 1) Placed power lockout for BN HIS-
- 2) Close BN HIS- 8813A in non iso 8813 position:
BN HIS-8813A
- 3) Place power lockout for BN HIS- 2) Closed BN HIS-8813A in iso 8813 position:
BN HIS-8813A 3) Placed power lockout for BN HIS-Step 3.d 8813A in iso position:
BN HIS-8813A If BN HIS-8813 was operated, green light is lit and red light is not lit for BN HIS-8813
- CRITICAL STEP PAGE 8 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
valves
- EJ HIS-8716A Green light is lit and
- EJ HIS-8716B red light is not lit for EJ HIS-8716A and 8716B Step 3.e S U
valves: suction valves
- CVCS to SI Pump Red light is lit and A suction valves: green light is not lit for EM HIS-8807A EM HIS-8807A and EM HIS-8807B 8807B Step 3.f S U
- open isolation valve open
- ESFAS status ESFAS status panel panel SIS section SIS section SA066Y, SA066Y location location 2Q, lit white 2Q, CVCS To SI Pmp Iso Vlv EM HV-8924, white light - lit Step 3.g
- CRITICAL STEP PAGE 9 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 18. Open the following Applicant opened RHR suction crosstie to charging pumps and Comments:
valves: RHR to SI pump B suction valves
- RHR to charging pumps:
Red light is lit and
- EJ HIS-8804A green light is not lit for EJ HIS-8804A and
- EJ HIS-8804B Step 3.h S U
- 19. Check if any SI pump Applicant checked if
- running any SI pump was Comments:
running
- EM HIS-4
SI pump suction RWST to SI pump valves: suction valves
- BN HIS-8806A Green light is lit and
- BN HIS-8806B red light is not lit for BN HIS-8806A and Step 3.j 8806B SI pump discharge flow does not change
- CRITICAL STEP PAGE 10 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
close CCP suction CCP discharge flow closed RWST to CCP from RWST valves: should be monitored pump suction valves from CCP A/B To
- BN HIS-112D Boron Inj Flow Green light is lit and
- BN HIS-112E indicators, EM FI-917A red light is not lit for and EM FI-917B BN HIS-112D and Step 3.k 112E CCP pump discharge flow does not change S U
- 22. Check at least one Examiner Note: Applicant checked at flow path from least one flow path Comments:
recirculation sump to RHR pump discharge from recirculation RCS - established flow would indicate sump to RCS was that recirculation flow established had been established EJ FI-618 and EJ FI-Step 3.l 619 both indicate 2100 gpm flow S U
running Coolers were running
SA066Y white light 8B
- SA066X white is lit light 8B (SGL10A) - Lit
- SA066Y white light 8B (SGL10B) - Lit Step 3.m
- CRITICAL STEP PAGE 11 of 12
JPM NO: Sim S7, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
complete through Step 3 S U
- 25. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 12 of 12
Initial Conditions: A large break Loss of Coolant Accident has occurred.
The crew was performing the actions of E-1, Loss of Reactor Or Secondary Coolant, when MCB Annunciator 47C, RWST LOLO 1 AUTO XFR, alarmed.
Initiating Cues: The CRS directs you to place ECCS in cold leg recirculation in accordance with ES-1.3, Transfer To Cold Leg Recirculation.
Notify the Control Room Supervisor when Step 3 is complete.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Sim S8, Rev 2 KSA No: 029G2.1.29 Revision: Feb 2013 KSA Rating: 4.1 / 4.0 JOB TITLE: RO / SROI Task
Title:
Remove the Containment Mini-Purge System From Service Validation Time: 11 minutes Learning Objective: T61.0110, Obj M, Describe function and operation of the following containment purge system components: 1. Mini Purge Supply Air Unit; 4. Mini Purge Exhaust Fan The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: Time Critical:
Student Handouts: OTN-GT-00001, Containment Purge System, Rev 29
References:
OTN-GT-00001, Containment Purge System, Rev 29
JPM NO: Sim S8, Rev 2 Initial Conditions: The plant is in Mode 1.
The containment mini-purge system had been placed in service to support containment maintenance activities.
The Control Room Supervisor (CRS) has the Gaseous Rad Release Permit.
Initiating Cues: The maintenance activities inside containment have been completed.
The CRS directs you to remove containment mini-purge from service in accordance with OTN-GT-00001, Containment Purge System, Section 5.3.
Notes: Use IC 161.
Place containment mini-purge in service IAW OTN-GT-00001, Section 5.2.
Task Standard: Upon completion of this JPM, the Applicant will have removed containment mini-purge from service IAW OTN-GT-00001.
Start Time:
Stop Time:
Page 1 of 6
JPM NO: Sim S8, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide applicant with Applicant obtained working copy of OTN- procedure copy working copy of OTN- Comments:
GT-00001 GT-00001 S U
- 2. Review Precautions Applicant reviewed and Limitations Precautions and Comments:
Limitations Section 3.0 S U
- 3. Review Prerequisites Applicant reviewed Prerequisites Comments:
Section 4.0 S U
- 4. If containment Applicant read step equipment hatch is and determined that it Comments:
open during core was N/A for the given alterations and mini- initial conditions and purge exhaust must went to Step 5.3.2 be secured, perform one of the following:
Step 5.3.1
- Critical Step Page 2 of 6
JPM NO: Sim S8, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 5. Using GT HIS-5, Applicant closed Ctmt Mini Purge Air GTHZ0005 using GT Comments:
Sply CTMT Iso, close HIS-5, Ctmt Mini GTHZ0005 Purge Air Sply CTMT Iso GT HIS-5 green light is Step 5.3.2 lit and the red light is not lit S U
- 6. Using GT HIS-4, Applicant closed Ctmt Mini Purge Air GTHZ0004 using GT Comments:
Sply CTMT Iso, close HIS-4, Ctmt Mini GTHZ0004 Purge Air Sply CTMT Iso GT HIS-4 green light is Step 5.3.3 lit and the red light is not lit S U
- 7. Using GT HIS-23, Applicant stopped CTMT Mini Purge Air SGT02 using GT HIS- Comments:
Sply Unit, stop 23, CTMT Mini Purge SGT02 Air Sply Unit GT HIS-23 green light is lit and the red light is Step 5.3.4 not lit
- Critical Step Page 3 of 6
JPM NO: Sim S8, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 8. Using GT HIS-26, Applicant closed CTMT Purge Sys Air GTHZ0026 using GT Comments:
Sply Damper, close HIS-26, CTMT Purge GTHZ0026 Sys Air Sply Damper GT HIS-26 green light is lit and the red light is Step 5.3.5 not lit S U
- 9. Using GT HIS-27, Applicant closed CTMT Purge Sys Air GTHZ0027 using GT Comments:
Sply Damper, close HIS-27, CTMT Purge GTHZ0027 Sys Air Sply Damper GT HIS-27 green light is lit and the red light is Step 5.3.6 not lit S U
- 10.Using GT HIS-20, Applicant stopped CTMT Mini Purge Exh CGT02 using GT HIS- Comments:
Fan & Damper, stop 20, CTMT Mini Purge CGT02 Exh Fan & Damper GT HIS-20 green lights are lit and the red Step 5.3.7 lights are not lit
- Critical Step Page 4 of 6
JPM NO: Sim S8, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 11. Using GT HIS-11, Applicant closed CTMT Mini Purge GTHZ0011 using GT Comments:
Exh Inner CTMT Iso, HIS-11, CTMT Mini close GTHZ0011 Purge Exh Inner CTMT Iso GT HIS-11 green light Step 5.3.8 is lit and the red light is not lit S U
- 12. Using GT HIS-12, Applicant closed CTMT Mini Purge GTHZ0012 using GT Comments:
Exh Outer CTMT Iso, HIS-12, CTMT Mini close GTHZ0012 Purge Exh Outer CTMT Iso GT HIS-12 green light Step 5.3.9 is lit and the red light is not lit S U
- 13. Using GT HIS-41, Applicant closed CTMT Mini Purge GTHZ0041 and Comments:
Sply/Exh Dampers, GTHZ0042 using GT close the following: HIS-41, CTMT Mini Purge Sply/Exh
- GTHZ0041, CTMT Dampers Mini-Purge Exh Inner CTMT GT HIS-41 green light Upstrm Dmpr Oper is lit and the red light is not lit AND
- Critical Step Page 5 of 6
JPM NO: Sim S8, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 14. Using GT HIS-28, Applicant closed CTMT Purge Exh GTHZ0028 using GT Comments:
Damper, close HIS-28, CTMT Purge GTHZ0028 Exh Damper GT HIS-28 green light is lit and the red light Step 5.3.11 is not lit S U
- 15. Using GT HIS-29, Applicant closed CTMT Purge Exh GTHZ0029 using GT Comments:
Damper, close HIS-29, CTMT Purge GTHZ0029 Exh Damper GT HIS-29 green light is lit and the red light Step 5.3.12 is not lit S U
- 16. Record date and time CRS acknowledges Applicant informed dampers were closed CRS of date and time Comments:
on Gaseous Rad dampers were closed Release Permit Step 5.3.13
- 17. The JPM is complete Record stop time on Page 1
- Critical Step Page 6 of 6
Initial Conditions: The plant is in Mode 1.
The containment mini-purge system had been placed in service to support containment maintenance activities.
The Control Room Supervisor (CRS) has the Gaseous Rad Release Permit.
Initiating Cues: The maintenance activities inside containment have been completed.
The CRS directs you to remove containment mini-purge from service in accordance with OTN-GT-00001, Containment Purge System, Section 5.3.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Plt P1, Rev 2 KSA No: 055EA1.02 Revision: Feb 2013 KSA Rating: 4.3 / 4.4 Job
Title:
RO / SROI / SROU Task
Title:
Locally Start (NE01) Emergency Diesel Validation Time: 15 Minutes Learning Objective: T61.003D, LP D-22, Obj I, Describe in order the methods used to locally start a Diesel Generator per ECA-0.0 (EOP Addendum 21)
The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator/Lab Plant X Classroom Method of Performance: Simulated X Performed Alternate Path: ___X___ Time Critical: ______
Student Handouts: EOP Addendum 21, Local Start Of Emergency DGs, Rev 2
References:
ECA-0.0,Loss Of All AC Power, Rev 16 EOP Addendum 21, Local Start Of Emergency DGs, Rev 2 Tools / Equipment: PPE
JPM NO: Plt P1, Rev 2 Initial Conditions: The Plant has experienced a loss of all AC Power.
Operators are performing ECA-0.0, Loss Of All AC Power, to restore power and stabilize plant conditions.
Initiating Cues: The Control Room Supervisor (CRS) has determined that neither Diesel (NE01/NE02) has started.
The Field Supervisor and an Operations Technician are attempting to start NE02.
The CRS directs you to locally start NE01 per EOP Addendum 21.
Inform the CRS when NE01 is running.
Note: All operator actions are to be simulated.
Task Standard: Upon completion of this JPM, the Applicant will have locally started Diesel Generator NE01 in accordance with EOP Addendum 21, Local Start Of Emergency DGs Start Time:
Stop Time:
PAGE 1 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 1. Obtain a verified Applicant obtained S U working copy of working copy of EOP EOP Addendum Addendum 21 Comments:
21, Local Start Of Emergency DGs
- 2. Determine and Applicant referred to S U correct cause of OTA-KJ-00121, Diesel DG failures(s): Generator NE01 Comments:
Control Panel
- a. Use applicable Annunciator
Response
Procedures(s):
- OTA-KJ-00121, Diesel Generator NE01 Control Panel Step 1.a.
- CRITICAL STEP PAGE 2 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 3. Check all of the Annunciator 6C and Applicant went to Step S U following Engine 6D are in alarm 1.b. RNO due to all Shutdown Relay alarms not being clear Comments:
actuation annunciators for affected DG(s) -
clear
- 2A, Lube Oil Pressure Low
- 4C, Jacket Water Temperature High
- 6C, Engine Overspeed
- 6D, Engine Shutdown Trouble
- 6F Crankcase Pressure High
- 7D, Generator Protection Relay Step 1.b.
- 4. b. Perform the Applicant determined S U following for from OTA-KJ-00121, affected DG(s): Addendum 6D, that the Comments:
engine trouble
- 1. Evaluate annunciator was due to reason for engine overspeed Engine Shutdown Relay actuation Step 1.b.1) RNO
- CRITICAL STEP PAGE 3 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 5. b. Perform the Control Room Applicant notified the following for acknowledges the Control Room that the affected DG(s): engine overspeed Engine Shutdown annunciator and Relay was energized
- 2. Consult with directs you to auto due to engine Control Room start NE01 per Step overspeed prior to 1.b.3) of Addendum resetting any 21 relays to prevent potential damage to DG.
Step 1.b.2) RNO
- 6. b. Perform the Applicant proceeded to following for start NE01 affected DG(s):
- 3. When directed, then Auto Start DG as follows:
Step 1.b.3) RNO
- CRITICAL STEP PAGE 4 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 7. b. Perform the Blue light is lit on Applicant ensured following for NE107 for 186-1 Differenctial OC affected DG(s): Lockout Relay 186-1 was Reset
- 3. When directed, then Auto Start DG as follows:
a) Ensure Differenctial OC Lockout Relay 186-1 is Reset:
Panel NE107 (NE01)
Step 1.b.3)a) RNO
- 8. b. Perform the Knob is in reset Applicant ensured S U following for position mechanical overspeed affected DG(s): (silver knob is pulled device (silver knob) is Comments:
out) Reset (Pulled Out) -
b) Ensure mechanical overspeed device (silver knob) is Reset (Pulled Out) -
Plant South of DG Step 1.b.3)b) RNO
- CRITICAL STEP PAGE 5 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 9. b. Perform the Applicant ensured DG S U following for Master Transfer Switch affected DG(s): is in Auto Comments:
- 3. When directed, then Auto Start DG as follows:
c) Ensure DG Master Transfer Switch is in Auto Step 1.b.3)c) RNO
- 10. b. Perform the No change in noise Applicant Reset Engine S U following for level in room Shutdown Relay by affected DG(s): depressing PB KJ-HS- Comments:
12 on NE107
- 3. When directed, then Auto Start DG as follows:
d) Reset Engine Shutdown Relay:
KJ-HS-12 (NE107)
Step 1.b.3)c) RNO
- 11. b. Perform the Applicant went to S U following for Step 2 affected DG(s): Comments:
- 3. When directed, then Auto Start DG as follows:
e) Go To Step 2 Step 1.b.3)e) RNO
- CRITICAL STEP PAGE 6 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 12. Check affected Applicant determined S U DG(s) - running NE01 did not start Comments:
Step 2 Applicant went to Attachment A, Local Start Of DG NE01, per Step 2 RNO
- 13. Notify Control Control Room Applicant notified CR S U Room of intent to acknowledges energize NB01 by Comments:
locally starting DG NE01 Att A, Step A1
- 14. Perform walkdown Applicant performed S U of DG NE01 to walkdown of DG NE01 ensure no obvious Comments:
adverse conditions exist prior to starting DG Att A, Step A2
- CRITICAL STEP PAGE 7 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 15. Break glass on DG Glass is broken - Applicant broke glass S U NE01 emergency button has popped on DG NE01 start pop-out button out emergency start pop- Comments:
KJ-HS-1D (NE107) out button KJ-HS-1D No change in noise (NE107)
Att A, Step A3 level in room
[May use attached hammer to break glass on KJ-HS-1D (NE107) or the glass cover may be unscrewed]
S U
- 16. Check if DG NE01 Applicant determined
- still stopped. that NE01 did not start Comments:
and went to Step A5 Att A, Step A4
- 17. Place Master Annunciator 5D, Applicant placed S U Transfer Switch KJ- Switch Not In Auto, Master Transfer Switch HS-9 in LOC/MAN on KJ-121, alarms KJ-HS-9 in MANUAL Comments:
Att A, Step A5
- CRITICAL STEP PAGE 8 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 18. Press and hold Noise level rises Applicant depressed S U Local Start significantly in room and held Local Start Pushbutton KJ-HS- Pushbutton KJ-HS-1C Comments:
1C until NE01 started Att A, Step A6
- 19. Check if DG NE01 NE01 indicates 514 Applicant verified that S U
- still stopped RPM on KJ-121 NE01 was running and went to Step A7 RNO Comments:
Att A, Step A7
- 20. If DG NE01 has Annunciator 5D, Applicant placed S U started, then Switch Not In Auto, Master Transfer Switch perform the on KJ-121, clears KJ-HS-9 in AUTO Comments:
following:
- a. Place Master Transfer Switch KJ-HS-9 in AUTO
- b. Go To Step A12 Att A, Step A7 RNO
- CRITICAL STEP PAGE 9 of 10
JPM NO: Plt P1, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE
- 21. Notify Control CRS acknowledges Applicant notified the S U Room of DG NE01 CRS that NE01 was status now running Comments:
Att A, Step A12 S U
- 22. The JPM is complete Record stop time on Page 1 Comments:
- CRITICAL STEP PAGE 10 of 10
Initial Conditions: The Plant has experienced a loss of all AC Power.
Operators are performing ECA-0.0, Loss Of All AC Power, to restore power and stabilize plant conditions.
Initiating Cues: The Control Room Supervisor (CRS) has determined that neither Diesel (NE01/NE02) has started.
The Field Supervisor and an Operations Technician are attempting to start NE02.
The CRS directs you to locally start NE01 per EOP Addendum 21.
Inform the CRS when NE01 is running.
Note: All operator actions are to be simulated.
CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: Plt P2, Rev 2 KSA No: 059A2.12 Revision: Feb 2013 KSA Rating: 3.1 / 3.4 Job
Title:
RO / SROI / SROU Task
Title:
Locally Operate A Main Feedwater Regulating Valve (MFRV)
Validation Time: 15 Minutes Learning Objective: T61.0110.6, LP-23, Obj F, Describe the operation, including signal inputs, of the MFW REG valves and explain the control response to input failures.
The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab Plant X Classroom Method of Performance: Simulated X Performed Alternate Path: _____ Time Critical: _____
References:
OTN-AE-00001 Addendum 8, Local Operation Of Main Feedwater Regulating Valves (MFRV), Rev 4 Handouts: OTN-AE-00001 Addendum 8, Local Operation Of Main Feedwater Regulating Valves (MFRV), Rev 4 Tools / Equipment: PPE
JPM NO: Plt P2, Rev 2 Initial Conditions:
- The plant is in Mode 1.
- A pre job brief has been conducted.
- OTN-AE-00001, Add 8, Local Operation Of Main Feedwater Regulating Valves (MFRV), will be used to control feedwater to 'A' Steam Generator while I&C is working on AE FCV-0510.
- Headset is on and communications have been established with the Balance of Plant (BOP) Operator.
Initiating Cues: The CRS directs you to work with the BOP Operator to take manual control of AE FCV-0510 and control feedwater to 'A' Steam Generator IAW OTN-AE-00001, Add 8, Section 3.1.
All Prerequisites are complete.
Note: All operator actions are to be simulated.
Task Standard: Upon completion of this JPM the applicant will have demonstrated an ability to:
Isolate the Main Feedwater Regulating Valve (MFRV) Bypass Valve to allow stroking from the Control Room Unisolate the MFRV Bypass Valve Align Main Feedwater Regulating Valve, AE FCV-0510, mechanically for Local Manual Operation Vent air from above and below the actuator for Main Feedwater Regulating Valve, AE FCV-0510 Start Time:
Stop Time:
Page 1 of 7
JPM NO: Plt P2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide Applicant with Applicant obtained working copy of OTN- procedure copy working copy of OTN- Comments:
AE-00001, Add 8 AE-00001, Add 8 S U
- 2. Review Precautions Applicant reviewed and Limitations Precautions and Comments:
Limitations S U
- 3. Review Prerequisites Applicant reviewed Prerequisites Comments:
S U Section 3.1, AEFCV0510 BOP informs you AE Applicant contacted
- Local Operation Using LK-550, SG A MN FW BOP and ensured AE Comments:
Handwheel BYP LEV CTRL, is in LK-550, SG A MN FW MAN and Closed BYP LEV CTRL, is in
- 4. Cycle MFRV Bypass MAN and Closed Valve as follows:
Ensure AE LK-550, SG A MN FW BYP LEV CTRL, in MAN and Closed Step 3.1.1.a
- Critical Step Page 2 of 7
JPM NO: Plt P2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 5. Close one of the AEV0260 or AEV0259 Applicant closed following to isolate has threads showing AEV0260 or AEV0259 Comments:
MFRV Bypass: on stem and handwheel can no
- 6. Notify BOP operator BOP acknowledges Applicant informed that isolation valve for MFRV Bypass iso is BOP MFRV Bypass Comments:
MFRV Bypass is closed iso is closed Closed Step 3.1.1.c S U
- 7. Using AE LK-550, SG BOP informs you that Applicant contacted A MN FW BYP LVL AE LK-550, SG MN the BOP to cycle AE Comments:
CTRL, cycle FW BYP LVL CTRL, LK-550, SG A MN FW AEFCV0550. has been cycled BYP LVL CTRL to cycle AEFCV0550 Step 3.1.1.d S U
- 8. Open isolation valve AEV0260 or AEV0259 Applicant opened closed in Step 3.1.1.b has no threads AEV0260 or AEV0259 Comments:
showing and handwheel can no longer be turned in Step 3.1.1.e the counter-clockwise direction
- Critical Step Page 3 of 7
JPM NO: Plt P2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 9. NOTE: Adjusting the Applicant read note MFRV Bypass Valve Comments:
to 60% in the following step allows for some remote adjustment of FW flow once the MFRV is placed in local handwheel operation.
Prior to 3.1.2 S U
- 10. Adjust AE LK-550, BOP informs you AE Applicant contacted SG A MN FW BYP LK-550, SG MN FW BOP to adjust AE LK- Comments:
LVL CTRL, to BYP LVL CTRL, has 550, SG A MN FW approximately 60% been adjusted to BYP LVL CTRL, to approximately 60% approximately 60%
Step 3.1.2 S U
- 11. Using Control Room BOP informs you Applicant contacted computer displays, that 'A' SG BOP to ensure 'A' SG Comments:
ensure affected SG parameters are parameters are stable parameters are stable with level at relatively stable 50%
Step 3.1.3 S U
- 12. Ensure Applicant ensured communications have communications were Comments:
been established established between local operator and BOP (Given in Initial Operator Conditions)
Step 3.1.4
- Critical Step Page 4 of 7
JPM NO: Plt P2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 13. Record the following BOP informs you that Applicant recorded for AEFCV0510, SG AE FK-510 indicates local display at 80% Comments:
A MFW REG VLV: 80% full open Full Open Local (LCD display) Applicant contacted
% Full Open BOP to get AEFCV0510 indication AE FK-510, SG C and recorded in MFW REG VLV procedure CTRL: % Full Open Step 3.1.5 S U
- 14. NOTE: While it might Applicant read note not be possible for all Comments:
repair situations, MFRV position should not be changed using the controller until requested by the local operator. This simplifies restoration to MCB control.
Prior to Step 3.1.6 S U
- 15. Place AE FK-510, SG BOP informs you AE Applicant contacted A MFW REG VLV FK-510, SG A MFW BOP to place AE FK- Comments:
CTRL, in MAN REG VLV CTRL, is in 510, SG A MFW REG MAN VLV CTRL, in MAN Step 3.1.6 S U
- 16. NOTE: The MFRV Applicant read note Bypass Valve is Comments:
operated in MAN due to the lead/lag characteristics of the control circuit.
Prior to Step 3.1.7
- Critical Step Page 5 of 7
JPM NO: Plt P2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 17. Adjust AE LK-550, BOP informs you 'A' Applicant contacted SG A MN FW BYP SG level is stable at BOP to adjust AE LK- Comments:
LEV CTRL, to 50% 550, SG A MN FW maintain stable SG BYP LEV CTRL, to level maintain stable SG level Step 3.1.7 S U
- 18. Rotate AEFCV0510 AEFCV0510 Applicant rotated handwheel to align handwheel has holes AEFCV0510 Comments:
handwheel engaging aligned when looking handwheel to engage mechanism with stem through it with stem engaging mechanism Step 3.1.8 S U
- 19. Place T-handle in T-handle has been Applicant placed alignment holes placed in alignment T-handle in the Comments:
holes alignment holes Step 3.1.9 S U
- 20. Close the following to Examiner Notes: Applicant closed bleed air from the top AEFCV0510V4 Comments:
- 1) This is a 3-way and bottom of valve with a vent actuator: position
- AEFCV0510V4, 2) Steps 20 and 21 AEFCV0510O may be performed in ACT 3-WAY any order ISO/BLEED INST AIR VALVE When it is aligned to Step 3.1.10 vent, inform applicant they hear a small rush of air
- Critical Step Page 6 of 7
JPM NO: Plt P2, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 21. Close the following to Examiner Notes: Applicant closed bleed air from the top AEFCV0510V6 Comments:
- 1) This is a 3-way and bottom of valve with a vent actuator: position
- AEFCV0510V6, 2) Steps 20 and 21 ISOLATION/BLEED may be performed in AIR VALVE TO any order UPPER AND LOWER PISTON When it is aligned to Step 3.1.10 vent, inform applicant they hear a small rush of air S U
- 22. Notify Control Room BOP acknowledges Applicant informed that AEFCV0510, SG AEFCV0510 is BOP AEFCV0510 is in Comments:
A MFW REG VLV, is aligned for local local control mechanically aligned control to handwheel and can only be operated locally Step 3.1.11 S U
- 23. The JPM is complete Record stop time on Page 1 Comments:
- Critical Step Page 7 of 7
Initial Conditions:
- The plant is in Mode 1.
- A pre job brief has been conducted.
- OTN-AE-00001, Add 8, Local Operation Of Main Feedwater Regulating Valves (MFRV), will be used to control feedwater to 'A' Steam Generator while I&C is working on AE FCV-0510.
- Headset is on and communications have been established with the Balance of Plant (BOP) Operator.
Initiating Cues: The CRS directs you to work with the BOP Operator to take manual control of AE FCV-0510 and control feedwater to 'A' Steam Generator IAW OTN-AE-00001, Add 8, Section 3.1.
All Prerequisites are complete.
Note: All operator actions are to be simulated.
CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: Plt P3, Rev 2 KSA No: 033K1.05 Revision: Feb 2013 KSA Rating: 2.7 / 2.8 Job
Title:
RO / SROI / SROU Task
Title:
Place RWST in Recirculation Validation Time: 20 Minutes Learning Objective: T61.0110.6, LP-24, Obj C, Draw, label and explain a one line diagram of the FPCCS to include the components listed in objective B showing the normal alignments and flows through the various subsystems.
The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
Evaluator Signature: Date:
Task Performer:
Location of Performance:
Control Room Simulator / Lab Plant X Classroom Method of Performance: Simulated X Performed Alternate Path: Time Critical: ______
References:
OTN-EC-00001, Addendum 3, RWST Cleanup Operations, Rev 13 Handouts: OTN-EC-00001, Addendum 3, RWST Cleanup Operations, Rev 13 Tools / Equipment: PPE
JPM NO: Plt P3, Rev 2 Initial Conditions: Callaway Plant is in Mode 1.
Chemistry has requested that the RWST be placed in recirculation.
Train A Spent Fuel Pool Cooling is NOT in service.
A pre job brief has been conducted and Steps 5.1.1 through 5.1.7 of OTN-EC-00001, Addendum 3, RWST Cleanup Operations, have been verified complete.
Initiating Cues: The Control Room Supervisor (CRS) directs you to place the RWST in recirculation per OTN-EC-00001, Addendum 3, RWST Cleanup Operations, beginning with Step 5.1.8.
Use Fuel Pool Clean-up Pump B.
A second Operations Technician has been briefed on the assigned job and is standing by in the RWST valve room.
A Reactor Operator has been briefed on the assigned job and is standing by in the Control Room.
All Prerequisites are complete.
Note: All operator actions are to be simulated.
Task Standard: Upon completion of this JPM, the applicant will have:
- 1) Lined up the Spent Fuel Pool Cooling System for RWST recirculation
- 2) Started the B Fuel Pool Clean-up Pump
- 3) Throttled Discharge Flow of the B Fuel Pool Clean-up Pump to the correct band Start Time:
Stop Time:
Page 1 of 8
JPM NO: Plt P3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 1. Obtain a verified Provide Applicant with Applicant obtained working copy of procedure copy working copy of OTN- Comments:
OTN-EC-00001, EC-00001, Add 3 Add 3 S U
- 2. Review Precautions Applicant reviewed and Limitations Precautions and Comments:
Limitations Section 3.0 S U
- 3. Review Prerequisites Applicant reviewed Prerequisites Comments:
Section 4.0
- Critical Step Page 2 of 8
JPM NO: Plt P3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U Section 5.1 RWST Where would you Applicant Recirculation find these Equipment demonstrated the Comments:
Warning signs? ability to find the signs
- 4. To prevent transfer of and each of the water between SFP (Location - following valves and and RWST, hang Ops Storage Area - hang equipment Equipment Warning Room 1405) warning signs on:
signs stating, The RWST is in the cleanup/recirculation
- ECV0099 lineup. Do NOT Examiner Note:
- ECV0100 place the SFP Applicant will need
- ECV0101 skimmers in service. PA301 key on:
Pool Skimmer Pmp Iso
- ECV0100, SFP Skimmer B To Fuel Pool Skimmer Pmp Iso
- ECV0101, SFP Skimmer C To Fuel Pool Skimmer Pmp Iso Step 5.1.8 S U
- 5. CAUTION: Leakage Applicant read caution past ECV0025 and Comments:
ECV0033 will result in water transferring between RWST and SFP.
Prior to 5.1.9
- Critical Step Page 3 of 8
JPM NO: Plt P3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 6. ENSURE CLOSED Stem is out with Applicant the following valves: threads showing on demonstrated the Comments:
ECV0025 (Valve is ability to ensure ECV0025, Fuel Pool OPEN) ECV0025 and Clg HX A To Fuel ECV0033 were closed Pool Clean-Up Pmps Examiner Note:
Iso Applicant recognized Stem is down with no ECV0025 was open ECV0033, Fuel Pool threads showing on and closed valve HX B To Fuel Pool ECV0033 (Valve is Clean-Up Pmps Iso CLOSED)
(FB 2000 - Rms 6104 Step 5.1.9 and 6105)
S U
- 7. Hang Equipment Applicant ensured Warning tags on equipment warning Comments:
following valves tags are hanging on:
stating The RWST is in the
- ECV0025 cleanup/recirculation lineup. Do not place
- ECV0033 SFP Cleanup in service:
(FB 2000 - Rms 6104
- ECV0025, Fuel and 6105)
Pool Clg HX A To Fuel Pool Cln/Upmps Iso
- ECV0033, Fuel Pool HX B To Fuel Pool Clean/Up Pmps Iso Step 5.1.10
- Critical Step Page 4 of 8
JPM NO: Plt P3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 8. CAUTION: If Train A Applicant read caution SFP Cooling is in Comments:
service, water will be transferred to the RWST if BNV0002 and ECV0076 are open at the same time.
Prior to 5.1.11 S U
- 9. Ensure closed Stem is up with Applicant ECV0076, Fuel Pool threads showing on demonstrated the Comments:
Clean-up Demin To ECV0076 ability to close SFP Dnstrm-Iso (Valve is OPEN) ECV0076 Step 5.1.11 (FB 2000 - Rm 6105)
S U
- 10. Hang Equipment Applicant ensured Warning tags on equipment warning tag Comments:
ECV0076 stating was hung on The RWST is in the ECV0076 cleanup/recirculation lineup. Do not place SFP Cleanup in service. (FB 2000 - Rm 6105)
Step 5.1.12
- Critical Step Page 5 of 8
JPM NO: Plt P3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 11. Open BNV0002, Fuel Provide cue after Applicant contacted Pool Clean-up Pmps Operations Tech (OT) OT to open BNV0002 Comments:
To RWST Iso is contacted to open valve (Located in RWST Step 5.1.13 valve room)
BNV0002 is open S U
- 12. Place magnetic Caution signs have Applicant contacted CAUTION signs, been placed on the the Control Room to Comments:
RWST in recirc, on MCB place magnetic Main Control Board CAUTION signs on MCB Step 5.1.14 S U
- 13. PERFORM the Provide cue after RO Applicant contacted following: is contacted to open the control room to Comments:
valve: open BNHCV8800A Using and BNHCV8800B BN HIS-8800A, BNHCV8800A and RWST To Refuel BNHCV8800B are Pool, open open BNHCV8800A Using BN HIS-8800B, RWST To Refuel Pool, open BNHCV8800B Step 5.1.15
- Critical Step Page 6 of 8
JPM NO: Plt P3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 14. NOTE: The Fuel Applicant read note Pool Cleanup Comments:
subsystem may be run regardless of Fuel Pool Cooling subsystem status as long as the system is properly aligned (suction and discharge).
Prior to 5.1.16 S U
- 15. Start one Fuel Pool Once B pump HS Applicant started B Cleanup Pump: is taken to RUN: Fuel Pool Cleanup Comments:
Pump using
- ECHS0023, ECPI0022, Fuel Pool ECHS0024, Fuel Pool Clean-up Clean-up B Disch Fuel Pool Clean-up Pump A Hand Pressure Indicator Pump B Hand Switch Switch indicates 100 psig
- ECHS0024, ECFI0044, Fuel Pool (FB 2000 - Rm 6104)
Fuel Pool Clean-up Clean-up Pumps Pump B Hand Disch Hdr Flow Switch indicates 90,000 lbm/hr Step 5.1.16
- Critical Step Page 7 of 8
JPM NO: Plt P3, Rev 2 JPM TASK EXAMINER PERFORMANCE STEP ELEMENT CUE STANDARD SCORE S U
- 16. Throttle pump Provide cue after Applicant throttled discharge valve to ECV0043 is throttled: valve ECV0043 to Comments:
obtain flow between maintain 70,000 lbm/hr 70,000 lbm/hr and After valve is to 75,000 lbm/hr 75,000 lbm/hr as throttled, ECFI0044 indicated by indicates 72,000 Applicant recognized ECFI0044, Fuel Pool lbm/hr flow was excessive Clean-up Pumps and throttled closed on Disch Hdr Flow Ind: ECV0043
- ECV0038, Fuel Pool Clean-up Pmp A Disch Iso
- ECV0043, Fuel (FB 2000 - Rm 6104)
Pool Clean-up Pmp B Disch Iso Step 5.1.17 S U
- 17. The JPM is Record stop time on complete Page 1 Comments:
- Critical Step Page 8 of 8
Initial Conditions: Callaway Plant is in Mode 1.
Chemistry has requested that the RWST be placed in recirculation.
Train A Spent Fuel Pool Cooling is NOT in service.
A pre job brief has been conducted and Steps 5.1.1 through 5.1.7 of OTN-EC-00001, Addendum 3, RWST Cleanup Operations, have been verified complete.
Initiating Cues: The Control Room Supervisor (CRS) directs you to place the RWST in recirculation per OTN-EC-00001, Addendum 3, RWST Cleanup Operations, beginning with Step 5.1.8.
Use Fuel Pool Clean-up Pump B.
A second Operations Technician has been briefed on the assigned job and is standing by in the RWST valve room.
A Reactor Operator has been briefed on the assigned job and is standing by in the Control Room.
All Prerequisites are complete.
Note: All operator actions are to be simulated.
Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 1, Rev 2 Op-Test No.: 2013301 Examiners: ____________________________ Operators: _____________________________
Initial Conditions: 100% Power, Steady State Conditions Turnover: B SI Pump is tagged out of service for a breaker inspection. The B Emergency Diesel Generator is running fully loaded. After the completion of Shift Turnover, Unload and Shutdown the B Emergency Diesel Generator.
Eve Malf. No. Event Event nt Type* Description No.
BOP (N) 1 N/A Unload and shutdown the B Diesel Generator SRO (I) Pressurizer Level Transmitter BB LT-459 Fails Low / Restore 2 BBLT459 RO (I) Letdown (Tech Spec)
SRO (C) Main Seal Oil Pump Trips / Emergency Seal Oil Pump fails to start 3 PCD01_Trip BOP (C) in Automatic PBG04 SRO (C) Normal Charging Pump Trips, must start a Centrifugal Charging 4
RO (C) Pump EBB01B SRO (C) Steam Generator B Tube Leak (25 gpm) Requiring Rapid Load 5
RO (R) Reduction (Tech Spec)
BOP (C)
EBB01B SRO (M) Steam Generator B Tube Rupture (400 gpm) after downpower 6
RO (M) started which results in a Reactor Trip / Safety Injection (PRA)
BOP (M)
SAS10XX_2 BOP (C) Feedwater Isolation Valve Fails to close on Ruptured SG 7
SRO (C)
CPIS BLOCK RO (C) Containment Purge Isolation Signal fails to Actuate (Both Trains) 8
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 4
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 0
- 7. Critical tasks (2-3) 2
Scenario Event Description Callaway 2013 NRC Scenario #1, rev. 2 The plant is operating at 100%, steady state power. Diesel Generator NE02 has been running fully loaded for one hour. During turnover, the crew is directed to unload and secure NE02 IAW OSP-NE-0001B, Standby Diesel Generator B Periodic Tests. B Safety Injection Pump is tagged out of service for a breaker inspection.
After NE02 has been unloaded, Pressurizer Level Channel BB LT-459 fails low, resulting in a loss of letdown. The crew will respond IAW OTO-BG-00001, Pressurizer Level Control Malfunction, select an operable pressurizer level channel and restore letdown to service. Tech Spec 3.3.1 for Reactor Trip System Instrumentation applies.
After Tech Specs have been addressed for BB LT-459, the Main Seal Oil Pump for the Main Generator trips and the Emergency Seal Oil Pump fails to start. The crew will enter OTO-MA-00002, Generator Seal Oil System Malfunction and restore generator seal oil by manually starting the Emergency Seal Oil Pump.
Once seal oil has been restored, the Normal Charging Pump will trip. The crew will re-enter OTO-BG-00001, Pressurizer Level Control Malfunction, and start a Centrifugal Charging Pump (CCP) to restore RCS charging flow.
Once the CCP has been started and pressurizer level is stable a 25 gpm tube leak develops on B Steam Generator. The crew should enter OTO-BB-00001, Steam Generator Tube Leak. OTO-BB-00001 will direct the crew to commence a rapid load decrease IAW OTO-MA-00008, Rapid Load Reduction, to have the unit off-line within the next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Tech spec 3.4.13 for RCS Operational Leakage applies.
Once the rapid load reduction has been commenced and a CUE has been received from the Lead Examiner, Steam Generator B tube ruptures and results in a 400 gpm primary to secondary leak. The crew should initiate a manual reactor trip and safety injection due to the loss of primary inventory.
The Main Feedwater Isolation Valve to Steam Generator B fails to close on the Feedwater Isolation Signal following the reactor trip and SI and must be manually closed by the crew.
Also post trip, the Containment Purge Isolation Signal fails to actuate. The crew will actuate a Containment Purge Isolation Signal when completing Attachment A in E-0, Reactor Trip or Safety Injection.
The scenario can be terminated after the crew completes the initial RCS cooldown IAW E-3, Steam Generator Tube Rupture, or at the discretion of the lead evaluator.
Callaway 2013 NRC Scenario #1, rev. 2 Critical Tasks:
Event #7 CT - Isolate "B" Steam Generator by closing FWIV B prior to transitioning from E-0, Reactor Trip or Safety Injection Event #8 CT - Manually initiate a Containment Purge Isolation Signal (CPIS) prior to completing Attachment A, Automatic Action Verification, in E-0, Reactor Trip or Safety Injection References OSP-NE-0001B, Standby Diesel Generator B Periodic Tests OTO-BG-00001, Pressurizer Level Control Malfunction OTO-MA-00002, Generator Seal Oil System Malfunction OTO-BB-00001, Steam Generator Tube Leak OTO-MA-00008, Rapid Load Reduction E-0, Reactor Trip or Safety Injection E-3, Steam Generator Tube Rupture Tech Spec 3.3.1 for Reactor Trip System Instrumentation Tech spec 3.4.13 for RCS Operational Leakage ODP-ZZ-00025, EOP/OTO User's Guide
Callaway 2013 NRC Scenario #1, rev. 2 Scenario Setup Guide:
Establish the initial conditions of IC-164, MOL 100% power:
- CCP A 765 ppm minus 5 days
- CCP B 775 ppm minus 15 days
- Rod Control Bank D 215 steps, Other banks 228 steps
- Diesel Generator NE02 is running fully loaded
- ENSURE BB-LT-459 is selected on BB-LS459E
- B SI Pump is tagged out with breaker in P-T-L and tag on handswitch
- Place Show 4 NE02 on large CRT
=======SCENARIO PRELOADS / SETUP ITEMS==========
B SI Pump Tagged out for maintenance
- ME Schematics (EM) e23em01b, Breaker position = 3 Emergency Seal Oil Pump Fails to start in Automatic
- Insert Malfunction (CD) DPCD03_AUTO, Value = Block B Feed Line Isolation Valve Fail to close in AUTO
- Insert Malfunction (SA) SAS10XX_2, Value = Enable Containment Purge Isolation fails to actuate
- Insert Malfunction (SB) CPIS_A_Block_Auto, Value = Block
- Insert Malfunction (SB) CPIS_B_Block_Auto, Value = Block
======= EVENT 2 ============================
Pressurizer Level Channel BB LT-459 fails Low
- Insert Malfunction (BB) BBLT0459, Value= 466.1
======= EVENT 3 ============================
Main Seal Oil Pump trips and the Emergency Seal Oil Pump fails to start Automatically
- Insert Malfunction (CD) PCD01_Trip, Value = Trip
=======EVENT 4 =============================
Normal Charging Pump Trips
- Insert Malfunction (BG) PBG04, Value = Trip
=======EVENT 5 ==============================
Steam Generator B Tube Leak of 25 gpm
- Insert Malfunction (BB) EBB01B, Value = 25
=======EVENT 6 ============================
Steam Generator B Tube Rupture of 400 gpm
- Insert Malfunction (BB) EBB01B, Value = 400
=======EVENT 7 PRELOADED===============
Feedwater Isolation on B Steam Generator Fails to close in Auto SEE PRELOADS ABOVE
=======EVENT 8 PRELOADED===============
Containment Purge Isolation Signal Fails to actuate SEE PRELOADS ABOVE
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 1 Page 5 of 24 Event
Description:
Unload and secure NE02 IAW OSP-NE-0001B Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- When contacted, respond as Secondary Operator that you are standing by and waiting for the Control Room Staff to Shut down the B Emergency Diesel Generator NE02.
- Contact the Secondary Operator using the Gaitronics for all communications OSP-NE-0001B Section 6.5, Unloading Diesel Generator B Two handed operation is allowed in accordance with ODP-ZZ-NOTE 00001, step 3.8.17 while adjusting Diesel load and MVARs T=0 (Step 6.5.1) Using KJ HS-107A, LOWER load in increments CRS and WAIT for load to stabilize between adjustments OSP-NE-0001B, (Step 6.5.2) As NE02 load is lowered, CHECK for associated BOP Section change in transformer amps.
6.5 (Step 6.5.3) Record time load reduction begins on Attachment BOP 6 and Control Room Log.
(Step 6.5.4) Periodically Ensure Power Factor of approximately BOP 0.9 LAG (Step 6.5.5) When NE02 load is lowered to approximately 0.2 BOP MW, Record time on Attachment 6 and Control Room Log.
(Step 6.5.6) Wait 3 to 5 minutes with load stable at BOP approximately 0.2 MW load on Diesel Generator B (Step 6.5.7) Wait 3 to 5 minutes with load stable at BOP approximately 0.2 MW load on Diesel Generator B (Step 6.5.8) Record time diesel output breaker NB0211 was BOP opened NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 2 Page 6 of 24 Event
Description:
Pressurizer Level Transmitter Fails Low, Restore Letdown Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- T = 15 minutes or at the discretion of the Lead Examiner
- Pressurizer Level Channel BB LT-459 fails Low
- Insert Malfunction (BB) BBLT0459, Value= 466.1
- When contacted, respond as I&C. Acknowledge the request to investigate the instrument/channel failure.
- When contacted, respond as EDO. Acknowledge entry into the OTO Indications Available:
T= 15 ANN 32B, PZR 17% HTRS OFF LTDN ISO ANN 32C, PZR LO LEV DEV OTO-BG-00001, Pressurizer Level Control Malfunction CRS Implement OTO-BG-00001, Pressurizer Level Control Malfunction OTO-BG- (Step 1) CHECK Charging Pumps - At Least One Running 00001 RO
- NCP is running Step 1 is an immediate action step (Step 2) CHECK for Failed Pressurizer Level Indicator RO
- BB-LI-459A is failed LOW (Step 3) Transfer Pressurizer Level Control Selector to Remove RO Failed Channel from Control
- BB LS-459D to L461/L469 position (Step 4) CHECK Letdown - In Service - NO RO
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 2 Page 7 of 24 Event
Description:
Pressurizer Level Transmitter Fails Low, Restore Letdown Proc /Time Position Applicants Actions or Behavior OTO-BG- (Step 4 RNO) Perform the following:
00001 a. Slowly Close Charging Header Back Pressure Control Valve while THROTTLING appropriate charging Discharge Valve to maintain 8-13 gpm to RCP seals
- BG HC-182
- b. Ensure BG HC-182 is CLOSED
- c. Restore Letdown as follows:
- 1) Ensure Letdown Containment Isolation Valves are OPEN
- BG HIS-8152
- BG HIS-8160
- 2) OPEN RCS Letdown to Regen Heat Exchanger Valves
- BG HIS-459
- BG HIS-460
- 3) Establish 85 gpm to 90 gpm Charging Header Flow while maintaining seal injection flow
- BG HC-182
- 4) PLACE Letdown Hx Outlet Pressure Controller in Manual and RAISE setpoint to greater than 75% open:
- BG PK-131
- 5) OPEN Orifice Isolation Valve(s) to establish desired letdown flow:
- BG HIS-8149AA
- BG HIS 8149BA
- BG HIS 8149CA
- 6) ADJUST Letdown Hx Outlet Press Controller to maintain between 300 psig and 350 psig and PLACE in Automatic:
- BG PK-131
- 7) ADJUST Charging flow to maintain Pressurizer Level.
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 2 Page 8 of 24 Event
Description:
Pressurizer Level Transmitter Fails Low, Restore Letdown Proc /Time Position Applicants Actions or Behavior OTO-BG- (Step 5) CHECK Pressurizer Heater Control Group C - ON 00001 RO
- BB HIS-50
- (Step 6) CHECK Pressurizer Level Trending to or at Program RO Level (Step 7) CHECK Operable Pressurizer Level Channel - USED RO FOR RECORDER
- BB LS-459E (Step 8) Review Applicable Technical Specifications 3.3.1, Table 3.3.1-1 Item 9 Cond M CRS Place channel in trip within 72 hrs OR Reduce Thermal power to less than P-7 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> (Step 9) Review Attachment A, Effects of Pressurizer Level CRS Instrument Failure NOTE At this time the crew should have an UPDATE Brief (Step 10) Perform Notifications Per ODP-ZZ-00001 Addendum 13, CRS Shift Manager Communications NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 3 Page 9 of 24 Event
Description:
Main Seal Oil Pump Trips / Emergency Seal Oil Pump fails to start in Automatic Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- T = 25 minutes or at the discretion of the Lead Examiner
- Main Seal Oil Pump trips and the Emergency Seal Oil Pump fails to start Automatically
- Insert Malfunction (CD) PCD01_Trip, Value = Trip
- When contacted, respond as Secondary or Polisher Operator and inform the Control Room WITHIN 30 secs, the Main Seal Oil pump is not operating and the pump motor feels hot to the touch.
o If asked about the breaker, it is tripped.
o The Local Generator Hydrogen Panel CC-128A has the following alarms 1C, Differential Seal Oil Pressure Low (Alarm would only be on if crew has NOT started ESOP - alarm setpoint is < 5 psid)
OTA directs entry into OTO-MA-00002, Generator Seal Oil Malfunction 4B, Emerg Seal Oil Pump Running (Alarm would only be on if CR has started ESOP)
OTA directs entry into OTO-MA-00002, Generator Seal Oil Malfunction o If asked to reset the Local Alarm Panel - Insert Remote Function (CC) CCQA0001, Value = Reset
- When contacted, respond as EDO. Acknowledge entry into the OTO Indications Available:
T= 15 ANN 130E, GEN AUX TROUBLE OTO-MA-00002, Generator Seal Oil System Malfunction Implement OTO-MA-00002, Generator Seal Oil System CRS Malfunction OTO-MA- (Step 1) Dispatch Operations Technician to perform Actions of 00002 BOP OTA-CC-0128A, Generator Hydrogen Panel (Step 2) CHECK Main Generator Gas pressure - LOWERING -
NO BOP
- CC PI-6 GO To Step 5
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 3 Page 10 of 24 Event
Description:
Main Seal Oil Pump Trips / Emergency Seal Oil Pump fails to start in Automatic Proc /Time Position Applicants Actions or Behavior OTO-MA- (Step 5) CHECK Main Seal Oil Pump - Tripped - YES 00002 BOP
- CD HIS-10 (Step 6) CHECK Emergency Seal Oil Pump Running - NO RNO Perform the following:
- a. Start the Emergency Seal Oil Pump
- b. If the Emergency Seal Oil Pump is running - go to Step 7
- (Step 7) CHECK Generator Gas Purity > 90% - YES BOP
- CC AI-17 CRS (Step 8) Go To Step 10 (Step 10) Perform Notifications Per ODP-ZZ-00001, Addendum 13, CRS Shift Manager Communications (Step 11) Go To Appropriate Plant Procedure as Directed by the CRS Control Room Supervisor At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 4 Page 11 of 24 Event
Description:
Normal Charging Pump Trips, must start a Centrifugal Charging Pump Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- T = 35 minutes or at the discretion of the Lead Examiner
- Normal Charging Pump Trips
- Insert Malfunction (BG) PBG04, Value = Trip
- When contacted, respond as Primary Operator and inform the Control Room the NCP is not running and there is a smell of burnt insulation in the room, but no fire.
o If asked about the breaker on PB03, it is tripped.
- When contacted, respond as EDO. Acknowledge entry into the OTO Indications Available:
T= 35 ANN 42A, CHG LINE FLOW HILO OTO-BG-00001, Pressurizer Level Control Malfunction CRS Implement OTO-BG-00001, Pressurizer Level Control Malfunction Tech Spec 3.4.1, DNB Limits, may be entered on Low RCS NOTE CREW Pressure (2223 psig) due to loss of NCP - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore if entered OTO-BG- (Step 1) CHECK Charging Pumps - At Least One Running - NO 00001
- NCP is tripped RNO - Perform the following:
- e. Ensure CCW is running in the same train as the CCP that was started Step 1 is an immediate action step (Step 2) CHECK for Failed Pressurizer Level Indicator - NO RO RNO - Perform the following:
- b. Go To Step 20
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 4 Page 12 of 24 Event
Description:
Normal Charging Pump Trips, must start a Centrifugal Charging Pump Proc /Time Position Applicants Actions or Behavior OTO-BG- (Step 20) CHECK Charging Header Flow - Indicates Proper 00001 RO Charging Alignment
- BG-FI-121A (Step 21) Maintain RCP Seal Injection Flow between 8 gpm and 13 RO gpm per RCP using Charging Header Back Pressure Control Valve
- BG HC-182 BOP (Step 22) CHECK Instrument Air - In Service - Yes RO (Step 23) CHECK Letdown - In Service - Yes (Step 24) Check Letdown Relief Valve (BG8117) - Normal - Yes RO
- Letdown Relief to PRT Outlet Temp BG TI-125
- Annunciator 39C, LTDN TEMP HI - CLEAR
- Containment Conditions - Normal RO
- Aux Building Conditions - Normal
- PRT Conditions - Normal
- Recycle Holdup Tank Levels - Normal CRS (Step 27) Review applicable Tech Specs - NONE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 5 Page 13 of 24 Event
Description:
Steam Generator "B" Tube Leak (25 gpm) Requiring Rapid Load Reduction Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- T = 45 minutes or at the discretion of the Lead Examiner
- Steam Generator B Tube Leak of 25 gpm
- Insert Malfunction (BB) EBB01B, Value = 25
- When contacted, respond as Chemistry that you will perform CTP-ZZ-02590, Primary To Secondary Leakrate Determination
- When contacted, respond as Count Room Tech and inform the Control Room the higher than Normal Radiation readings from Steam Generator B are valid
- When contacted, respond as EDO. Acknowledge entry into the OTO Indications Available:
T= 45 ANN 61A, PROCESS RAD HIHI ANN 61B, PROCESS RAD HI OTO-BB-00001, Steam Generator Tube Leak CRS Implement OTO-BB-00001, Steam Generator Tube Leak OTO-BB- #(Step 1) CHECK if PZR Level can be maintained - YES 00001 RO a. Control charging flow as necessary to maintain PZR level
- b. Check Pressurizer Level - Stable or Rising
- (Step 2) CHECK if VCT Level Can be Maintained - YES RO a. VCT Level - Maintained Greater Than 5% by Normal Makeup (Step 3) Notify Chemistry to Perform CTP-ZZ-02590, Primary to CRS Secondary Leakrate Determination
- (Step 4) Try to identify Affected SG - "B" Steam Generator RO/BOP
- High radiation on N16 monitors at the RM-11 station
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 5 Page 14 of 24 Event
Description:
Steam Generator "B" Tube Leak (25 gpm) Requiring Rapid Load Reduction Proc /Time Position Applicants Actions or Behavior OTO-BB- #(Step 5) Determine SG Tube Leak Rate 00001 RO/BOP a. Should calculate leak rate of 20 - 40 gpm
- b. Leak rate - LESS THAN 50 GPM
- The upper leak rate limit of 75 gpd requires plant shutdown independent of whether this limit is exceeded by a qualitatively confirmed leakage spike or progressively rising leakage.
NOTES
- To avoid unnecessary shutdown, leakage should be qualitatively confirmed prior to declaration Action level 2 or 3. If a second radiation monitor is not available, actions should be based on the indications of the available monitor.
- (Step 6) CHECK if Plant should be Shutdown
- a. Using the table in this step determine appropriate actions CRS
- EPRI Action Level 3, > 75 gpd including confirmed spikes
- Perform Actions in Attachment D OTO-BB- (Step D1.a) Initiate Step 7 and commence a controlled shutdown 00001, CRS to Mode 3. Reduce power to < 50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and be in Mode Att D 3 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (Step D1.a.1) Perform Applicable procedures as necessary CRS
- a. OTO-MA-00008, Rapid Load Reduction OTO-MA-00008, Rapid Load Reduction OTO-MA- (Step 1) Place Rod Control In AUTO 00008 b. SE HS-9 While reviewing reactivity plans consider repositioning Control NOTE Rods per OTS-SF-00001, Control Rod Repositioning (Plant Conditions allow).
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 5 Page 15 of 24 Event
Description:
Steam Generator "B" Tube Leak (25 gpm) Requiring Rapid Load Reduction Proc /Time Position Applicants Actions or Behavior OTO-MA- (Step 2) Manage Reactivity 00008 a. Perform Reactivity Management Brief:
- Discuss Amount and Rate of Turbine Load Reduction
- Determine amount of boric acid needed If using the Load Limit Potentiometer, unloading at greater than 50 CAUTION MWe per minute may arm the Main Condenser Steam Dumps Steps 3 and 4 may be performed concurrently while continuing in NOTE this procedure
- (Step 3) REDUCE Turbine Load at Less than or Equal to 5% per Minute using any of the following:
CRS/BOP
- Reduce Turbine load using the %/Min Loading Rate:
- Reduce Turbine load using the Load Limit Potentiometer If changing load reduction methods to the Load Limiter ENSURE CAUTION Load Set is restored to AT SET LOAD prior to using the Load Limiter.
- (Step 4) Borate From the BAST by performing any of the CRS/RO following:
- BORATE using OTN-BG-00002, Attachment 8 OTN-BG-00002, Attachment 8, Borate Mode of RMCS Operation OTN-BG-00002, RO (Step 1) Place BG HS-26, RCS M/U CTRL, in STOP.
Att 8 RO (Step 2) Place BG HS-25, RCS M/U CTRL SEL, in BOR.
RO (Step 3) RESET BG FY110B, BA COUNTER, to 000.
When setting BG FY-110B, allowance should be made in the NOTE setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered.
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 5 Page 16 of 24 Event
Description:
Steam Generator "B" Tube Leak (25 gpm) Requiring Rapid Load Reduction Proc /Time Position Applicants Actions or Behavior OTN-BG-(Step 4) ENSURE BG FY-110B is set to deliver the desired 00002, RO amount of boron.
Att 8 RO (Step 5) Place BG HS-26, RCS M/U CTRL, in RUN.
(Step 6) WHEN the desired amount of borated water has been RO added, PLACE BG HS-26, RCS M/U CTRL, in STOP (Step 7) If required, PERFORM the following:
RO a. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO.
- b. PLACE BG HS-26, RCS M/U CTRL, in RUN.
OTO-MA- (Step 5) Initiate Boron Equalization by performing the following:
00008 a. ENERGIZE at least one group of Pressurizer Backup (cont'd) Heaters:
- B/U Group A BB HIS-51A
- B/U Group B BB HIS 52A RO
- b. Place Pressurizer Pressure Master Controller in MAN:
- BB PK-455A
- c. Lower Pressurizer Pressure Master controller output to 38% to 42%
- d. Place Pressurizer Master Controller in AUTO (Step 6) Check MFP Turbine Speed Control - IN AUTO BOP
- FC SK-509B
- FC SK-509C Once the crew starts the shutdown using steps 1-6 of OTO-MA-00008, as proven by observation lowering load 5-10 MWe:
CUE GO TO THE NEXT EVENT AS CUED BY LEAD EXAMINER
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 17 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- T = 60 minutes or at the discretion of the Lead Examiner
- Steam Generator B Tube Rupture of 400 gpm
- Insert Malfunction (BB) EBB01B, Value = 400
- If contacted, respond as Count Room Tech and inform the Control Room the higher than Normal Radiation readings from Steam Generator B are valid
- When contacted, respond as EDO. Acknowledge entry into the OTO Indications Available:
T= 60 ANN 109C, SG B LEV DEV OTO-BB-00001, Steam Generator Tube Leak (Continuous Action Step 1)
OTO-BB- #(Step 1) CHECK if PZR Level can be maintained 00001 a. Control charging flow as necessary to maintain PZR level
- b. Check Pressurizer Level - Stable or Rising - NO RNO b. PERFORM the following:
- 1) Isolate letdown as necessary
- 2) RAISE charging flow as necessary
- 3) If PZR level can NOT be maintained greater than 6%,
THEN PERFORM the following:
a) Manually TRIP the reactor.
b) When reactor trip is verified, THEN ACTUATE SI.
c) Go To E-0, Reactor Trip Or Safety Injection, Step 1 E-0, Reactor Trip or Safety Injection E-0 CRS Implement E-0, Reactor Trip or Safety Injection NOTE Steps 1 through 4 are immediate actions
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 18 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior E-0 (Step 1) CHECK Reactor Trip
- Rod Bottom Lights - All Lit RO
- Reactor Trip and Bypass Breakers - Open
- Neutron Flux - Lowering (Step 2) CHECK Turbine Trip BOP
- a. Turbine Stop Valves - Closed (Step 3) CHECK Power to AC Emergency Buses BOP a. At Least One Emergency Bus - Energized
- b. Both Emergency Buses - Energized (Step 4) CHECK SI Status
- a. Check if SI is Actuated
- LOCA Sequencer ANN 30A - Lit
- LOCA Sequencer ANN 31A - Lit
- SB069 SI Actuate Red Light - Lit Solid (Step 5) Perform Attachment A, Automatic Action Verification, RO/BOP while continuing with this procedure Call STA to Initiate CSF Status Tree Monitoring in accordance with CRS ODP-ZZ-00025, EOP/OTO User's Guide, step 4.24.8 E-0 Att A RO/BOP (Step A1) CHECK Charging Pumps - Both CCPs running (Step A2) CHECK SI and RHR Pumps - All running - NO RO/BOP SI Pump B Out of Service RO/BOP (Step A3) CHECK ECCS Flow - BIH flow indicated
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 19 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior E-0 Att A (Step A4) CHECK ESW Pumps - BOTH RUNNING RO/BOP
- EF HIS-55A
- EF HIS-56A (Step A5) CHECK CCW Alignment:
- CCW Pumps - ONE RUNNING IN EACH TRAIN
- STOP Spent Fuel Pool Cooling Pump(s)
- RECORD The Time Spent Fuel Pool Cooling Pump Secured (Step A6) CHECK Containment Cooler Fans - RUNNING IN RO/BOP SLOW SPEED (Step A7) CHECK Containment Hydrogen Mixing Fans -
RO/BOP RUNNING IN SLOW SPEED RO/BOP (Step A8) CHECK If Containment Spray should Be Actuated - NO (Step A9) CHECK If Main Steamlines Should Be Isolated:
RO/BOP
- Containment pressure > 17 psig
- Steamline pressure - LESS THAN 615 PSIG (Step A10) CHECK ECCS Valves - PROPER EMERGENCY RO/BOP ALIGNMENT RO/BOP (Step A11) CHECK Containment Isolation Phase A RO/BOP (Step A12) CHECK SG Blowdown Isolation
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 20 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior E-0 Att A (Step A13) CHECK Both Trains of Control Room Ventilation RO/BOP Isolation RO/BOP (Step A14) CHECK Containment Purge Isolation Critical Manually initiate a Containment Purge Isolation Signal (CPIS)
Task CREW prior to completing Attachment A, Automatic Action Verification, in E-0, Reactor Trip or Safety Injection (Step A15) NOTIFY CRS of the following:
- Unanticipated Manual actions taken.
RO/BOP
- Failed Equipment status
- Attachment A, Automatic Action Verification, completed.
E-0 (Step 6) CHECK Generator Output Breakers - Open BOP (cont'd)
(Step 7) CHECK Feedwater Isolation Main Feedwater Pumps - Tripped BOP Main Feedwater Reg Valves - Closed Main Feedwater Reg Bypass Valves - Closed Feedwater Isolation Valves - Closed - NO The following Critical Task could have been addressed by the crew using the Ruptured SG Isolation Foldout Page Criteria which states:
If BOTH conditions listed below occur, THEN isolate feed flow to Note to affected SG(s) as desired:
Evaluator
- Narrow range level in affected SG(s) - GREATER THAN 7% [25%]
Critical Isolate Steam Generator "B" by closing FWIV B prior to CREW Task transitioning from E-0, Reactor Trip or Safety Injection
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 21 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior E-0 (Step 8) CHECK AFW Pumps BOP a. MD AFW Pumps - Both Running
- TD AFP Flow Control Valves - FULL OPEN
- TD AFP Loop Steam Supply Valves - Both OPEN IF NECESSARY BOP (Step 10) CHECK Total AFW Flow > 285,000 lbm/hr (Step 11) CHECK PZR PORVs and Spray Valves
- c. PORV Block Valves - Both Open
- d. Normal PZR Spray Valves - Closed (Step 12) CHECK if RCPs should be Stopped
- c. RCS Pressure - Less than 1425 psig -NO RNO - Go To Step 13
- RCPs Running - Tavg 557 Deg F
- a. CHECK pressures in all SGs:
RO/BOP
- Any SG pressure lowering in an uncontrolled manner -
- Any SG completely depressurized RNO - Go to Step 15
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 22 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior E-0 (Step 15) CHECK if SG Tubes are Intact
- Levels in all SGs - "B" NR Level is rising uncontrollably
- SG Steamline N16 radiation - Normal - NO
- Condenser Air Removal radiation - Normal before Isolation - NO RO/BOP
- SG Blowdown and Sample radiation - Normal before Isolation - NO
- Turbine Driven Aux Feedwater Pump Exhaust radiation -
normal GO TO E-3, Steam Generator Tube Rupture E-3, STEAM GENERATOR TUBE RUPTURE NOTE Personnel should be available for sampling during this procedure NOTE Seal Injection flow should be maintained to all RCPs NOTE Step 1 criteria applies until an operator controlled cooldown is initiated E-3 (Step 1) CHECK if RCPs should be stopped
- High radiation from any SG sample
- High radiation from any SG steamline
- High radiation from any SG blowdown line sample
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 23 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior E-3 (Step 3) Isolate Flow From Ruptured SG
- c. Locally close TDAFP Steam Supply from Main Steam Loop Manual Isolation valve from ruptured SG o ABV0085 (SG B)
SIM V0085 Insert Remote Function (AB) ABV0085, Value = 0 Operator SIM (Step 3 contd)
- f. Check if C-9 interlock is lit
- a. Narrow range level > 7% [25%]
- b. Stop feed flow to ruptured SG CLOSE AL HK-9A and AL HK-10A RO/BOP (Step 5) CHECK Ruptured SG Pressure - > 340 psig If RCPs are NOT running, the following steps may cause a false CSF-1, Figure 4, Integrity Status Tree indication for the ruptured CAUTION loop. Disregard the ruptured loop T-cold indication until after performing Step 29
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 1 rev.2 Event # 6, 7, 8, 9 Page 24 of 24 Event
Description:
Steam Generator B Tube Rupture / Reactor Trip / FWIV Fails to close/ SI Pump fails to Auto Start / CPIS fails to Auto Actuate Proc /Time Position Applicants Actions or Behavior E-3 After the low steamline pressure SI signal is blocked, main NOTE steamline isolation will occur if the high steam pressure rate setpoint is exceeded.
(Step 6) Initiate RCS Cooldown
- b. Block Steamline Pressure SI
- c. Determine required core exit temperature (based on table in E-3 and Lowest Ruptured SG Pressure BOP d. Dump steam to condenser from the intact SGs at maximum rate using steam dumps or ASDs
- e. Core exit TCs - less than required temperature
- f. Stop the RCS cooldown
- g. Maintain core exit TCs - Less than required Temperature NOTE Once the RCS cooldown has begun as described in STEP 6 EVAL OR at the discretion of the Lead evaluator - The Scenario can be STOPPED
Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 3, Rev 5 Op-Test No.: 2013301 Examiners: ____________________________ Operators: _____________________________
Initial Conditions: 80% Power, Steady State Conditions Turnover: The B Motor Driven Auxiliary Feedwater Pump is out of service for breaker maintenance and will not be returned to service until next shift. The NCP is vibrating excessively, so after the completion of Shift Turnover, shift to the "A" CCP.
Event Malf. No. Event Event No. Type* Description 1 N/A RO (N) Swap Charging Pumps (High Vibration on NCP)
SRO (I) 2 BBTE0411A1 RTD Fails High (Tech Spec)
RO (I)
SRO (C) MFW Reg Valve (FRV) C Controller Fails Closed - Manual 3 AEFC0530_1 BOP (C) Control Available SRO Refueling Water Storage Tank (RWST) Level Channel Fails 4 BNLT0932 Low (Tech Spec)
SRO (M) 5 PB03 RO (M) Loss of Power Supply PB03 / Reactor Trip BOP (M)
SRO (C) Running CCP Trips (A) / Non Running CCP (B) must be 6 PBG05A RO (C) manually started SA036D_MD AFAS SRO (I) Auxiliary Feedwater Actuation Signal (MD AFAS) fails to actuate 7 SA036E_MD BOP (I) on both trains AFAS SRO (C) Turbine Driven Auxiliary Feedwater Pump trips 60 seconds 8
PAL02_1 BOP (C) following the Reactor Trip (contributes to Loss of Secondary Heat Sink)
SRO (C) "A" Motor Driven Auxiliary Feedwater Pump Discharge Flow 9
BOP (C) Degraded. Discharge Valve cannot be opened (which ALV0043 contributes to Loss of Secondary Heat Sink)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 3
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 3
Scenario Event Description Callaway 2013 NRC Scenario #3, rev. 5 The plant is operating at 80%, steady state power. Motor Driven Auxiliary Feedwater (MDAFW) Pump B is out of service for breaker maintenance and will not be returned to service until next shift. The crew is directed to shift charging to Centrifugal Charging Pump (CCP) A after shift turnover due to excessive vibration reported on the Normal Charging Pump (NCP).
After the NCP is secured and pressurizer level has been stabilized, the Loop 1 Hot Leg RTD will fail high causing the control rods to drive in. The Reactor Operator will take manual control of the control rods and respond in accordance with OTO-BB-00004, RCS RTD Channel Failures. Tech Spec 3.3.1 applies.
After Tech Specs have been addressed for the RTD, MFW Reg Valve (FRV) C fails closed. This causes a feedwater flow reduction and a lowering SG level. The crew should respond per OTO-AE-00001, Feedwater System Malfunction, and take manual control of the failed valve to prevent a reactor trip.
After Steam Generator C level has been stabilized, a Refueling Water Storage Tank (RWST) level channel fails low. The crew will respond IAW OTO-BN-00001, RWST Level Channel Malfunction, Tech Spec 3.3.2 applies.
After Tech Specs have been reviewed for the RWST level channel a loss of Bus PB03 occurs. This results in a loss Heater Drain Pump A and Condensate Pumps A and C. The crew should respond by manually tripping the reactor and entering E-0, Reactor Trip or Safety Injection. If the reactor is not tripped manually, it will trip automatically on SG low level.
When the reactor trips, CCP A will trip. CCP B will have to be manually started to provide RCS charging and seal injection to the Reactor Coolant Pumps. This could be on prudent operation action in accordance with ODP-ZZ-00025, EOP/OTO User's Guide, or from direction in ES-0.1, Reactor Trip Response, or from FR-H.1, Response to Loss of Secondary Heat Sink.
The Auxiliary Feedwater Actuation Signal-Motor Driven (AFAS-MD) fails to actuate on both trains from the SG low level. The crew should respond to the failed AFAS-MD signal by starting MDAFW Pump A (B pump is OOS for maintenance). The manual discharge valve for MDAFW Pump A is failed at 10% open and cannot be opened locally.
Once the crew has entered ES-0.1, Reactor Trip Response, and completed the first 4 steps, the Turbine Driven Aux Feedwater Pump will be tripped.
Due to the status of the AFW system, the crew should transition to FR-H.1. The crew should use EOP Addendum 38, Non Safety Auxiliary Feedwater Pump, as directed in FR-H.1, to restore Aux Feedwater flow.
The scenario can be terminated once the crew restores Aux Feedwater flow IAW EOP Addendum 38 or at the discretion of the lead evaluator.
Callaway 2013 NRC Scenario #3, rev. 5 Critical Tasks:
Event #3 CT - Take manual control of FRV C prior to a reactor trip occurring on low steam generator water level Event #5 CT - Manually start CCP B prior to initiating a RCS bleed and feed due to having no CCPs in service Event #8 CT - Manually start the Non Safety Auxiliary Feedwater Pump IAW FR-H.1, Response to Loss of Secondary Heat Sink, prior to initiating a RCS bleed and feed due to Steam Generator low level NOTE:
RCS bleed and feed criteria:
WR level in any 3 S/Gs < 27% [42%]
OR PZR Pressure > 2335 psig OR NO CCPs available References OTN-BG-00001, Addendum 1, Shifting From The NCP to One Of The CCPs OTO-BB-00004, RCS RTD Channel Failures OTO-AE-00001, Feedwater System Malfunction OTO-BN-00001, RWST Level Channel Malfunction E-0, Reactor Trip or Safety Injection ES-0.1, Reactor Trip Response FR-H.1, Response To Loss Of Secondary Heat Sink EOP Addendum 38, Non Safety Auxiliary Feedwater Pump Tech Spec 3.3.1 for Reactor Trip System Instrumentation Tech Spec 3.3.2 for ESFAS Instrumentation ODP-ZZ-00025, EOP/OTO User's Guide
Callaway 2013 NRC Scenario #3, rev. 5 Scenario Setup Guide:
Establish the initial conditions of IC-166, MOL 80% power:
- CCP A 799 ppm minus 5 days
- CCP B 809 ppm minus 15 days
- Rod Control Bank D 186 steps, Other banks 228 steps
- B AFW Pump is tagged out with breaker in P-T-L and tag on handswitch
=======SCENARIO PRELOADS / SETUP ITEMS==========
B AFW Pump is tagged out for maintenance
- ME Schematics (AL) e23al01b, NB0205 Breaker position = 3 A CCP trips when reactor trips
- Insert Malfunction (BG) PBG05A, Value = Trip, Conditional = rec009 le 1.0, Delay = 5 sec Motor Driven AFAS fails to actuate - both trains
- Insert Malfunction (SA) SA036D_MDAFAS, Value = Block
- Insert Malfunction (SA) SA036E_MDAFAS, Value = Block TD AFW Pump trips 3 minutes after reactor trip
- Insert Malfunction (AL) PAL02_1, Value = True, Conditional = rec009 le 1.0, Delay = 3 min Motor Driven AFW Pump A discharge flow is degraded
- Insert Remote (AL) ALV0043, Value = 10.0
======= EVENT 2 ============================
RCS Loop 1 Hot Leg RTD fails high
- Insert Malfunction (BB) BBTE0411A1, Value= 650, Ramp = 10 sec
======= EVENT 3 ============================
MFW Reg Valve (FRV) C Fails Closed - Manual Control Available
- Insert Malfunction (AE) AEFC0530_1, Value = 0, Ramp = 90 sec
=======EVENT 4 =============================
RWST Level Channel fails low
- Insert Malfunction (BN) BNLT0932, Value = 0
=======EVENT 5 ==============================
Loss of Bus PB03 - Reactor Trip
- Insert Malfunction (PB) PB03, Value = Trip
=======EVENT 6 PRELOADED===================
A CCP trips when reactor trips SEE PRELOADS ABOVE
=======EVENT 7 PRELOADED===============
Motor Driven AFAS fails to actuate - both trains SEE PRELOADS ABOVE
=======EVENT 8 PRELOADED===============
TD AFW Pump trips 60 sec after reactor trip SEE PRELOADS ABOVE
=======EVENT 9 PRELOADED===============
Motor Driven AFW Pump A discharge valve is shut SEE PRELOADS ABOVE
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 1 Page 5 of 23 Event
Description:
Shift Charging Flow from the NCP to A CCP Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- When contacted, acknowledge as RP that charging pumps are being swapped OTN-BG-00001, Add 1, Shifting From The NCP To One Of The CCPs T=0 CRS Start the A CCP and secure the NCP OTN-BG-(Step 5.1.1) Initiate a FPIP for A CCP and commence hourly 00001, RO Fire Watch Add 1 Per Turnover Sheet FPIP has been initiated and hourly Fire (NOTE)
Watch has commenced.
(Step 5.1.2) Notify RP that A CCP will be started and the NCP RO secured RO (Step 5.1.3) Ensure CCP being started is supplied by CCW (NOTE) CCW A Train is in service (Step 5.1.4) Place BG FK-121, CCP Disch Flow Ctrl, in manual RO and set at minimum flow RO (Step 5.1.5) CHECK BG HIS-8110, CCP A Recirc Vlv, is open (Step 5.1.6) Place BG HIS-1AX, CCP A Aux L-O Pump, in auto RO and ensure the run light is on RO (Step 5.1.7) Start CCP A using BG HIS-1A
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 1 Page 6 of 23 Event
Description:
Shift Charging Flow from the NCP to A CCP Proc /Time Position Applicants Actions or Behavior OTN-BG-(Step 5.1.8) If this Add was entered from section for CCP Bkr 00001, RO Operability Check, check Bkr closed properly Add 1 (NOTE) Step 5.1.8 is N/A (Step 5.1.9) CHECK BG HIS-1AX, CCP A Aux L-O Pump, run RO light has gone out and the stop light is lit after a reasonalble time following start of the CCP (Step 5.1.10) Place BG FK-124, NCP Disch Flow Ctrl, in RO manual (MAN)
(Step 5.1.11) When flow through the NCP is less than 65 gpm, RO ensure BGHV8109 is open using BG HIS-8109, NCP Recirc Vlv (Step 5.1.12) Raise CCP flow using BG FK-121 while lowering RO NCP flow using BG FK-124 to maintain a constant charging flow as indicated on BG FI-121A, Chg Hdr Flow Two handed operation is allowed for Step 5.1.12 to maintain a (NOTE) constant charging flow in accordance with ODP-ZZ-00001, Section 3.8.17 (Step 5.1.13) If desired, when BG FK-124 indicates 0%, stop RO the NCP using BG HIS-3 (Step 5.1.14) Using BG HC-182, Chg Hdr Back Press Ctrl, RO ensure that the RCP seal water injection flow is 8 to 13 gpm per pump (Step 5.1.15) CHECK PZR level stable, and then place BG FK-RO 121 in auto NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 2 Page 7 of 23 Event
Description:
RCS Loop 1 Hot Leg RTD Fails High Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- T = 15 minutes or at the discretion of the Lead Examiner
- RCS Loop 1 Hot Leg Fails High
- Insert Malfunction (BB) BBTE0411A1, Value = 650, Ramp = 10 sec
- When contacted, respond as I&C. Acknowledge the request to trip bistables and to investigate the instrument/channel failure.
- When contacted, respond as EDO. Acknowledge entry into the OTO.
Indications Available:
T = 15 ANN 65C, AUCT T AVG HI ANN 65E, T REF / T AUCT LO ANN 82B, OTT ROD STOP ANN 82C, OPT ROD STOP ANN 83C, RX PARTIAL TRIP OTO-BB-00004, RCS RTD Channel Failures CRS Implement OTO-BB-00004, RCS RTD Channel Failures (Step 1) Place rod control in manual RO
- Loop 1: BB TI-412 (Tavg) - failed high
- Loop 1 BB TI-411A (T) - failed high (Step 3) Select T and Tavg channel defeat switches to failed channel:
- BB TS-411F, T Defeat Switch - Select to T411
- BB TS-412T, Rod Control Tave Input Channel Defeat Switch - Select to T412
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 2 Page 8 of 23 Event
Description:
RCS Loop 1 Hot Leg RTD Fails High Proc /Time Position Applicants Actions or Behavior OTO-BB- #(Step 4 and Step 4 RNO) Check RCS Tavg within 1.5°F of Tref 00004 RNO Restore RCS Tavg to within 1.5°F of Tref using any of the following:
- Adjust control rods
- Adjust turbine load
- Adjust RCS boron concentration NOTE RNO may or may not have to be performed dependent on how quickly rods are placed in manual IAW Step 1 (Step 5) CHECK rod control - IN AUTO RO
- SE HS-9 (Step 6) CHECK pressurizer level within one of the following:
- Trending to program level OR
- SC TS-411E (Step 8) Review Attachment A, Effects Of RCS RTD Instrument CRS Failure (Step 9) Review Applicable Technical Specifications:
- Refer to Att J, Technical Specifications 3.3.1, Table 3.3.1-1, Item 6, Cond E CRS 3.3.1, Table 3.3.1-1, Item 7, Cond E
- Place channel in trip in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR Be in Mode 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> CRS (Step 10) Direct I&C to trip bistables NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 3 Page 9 of 23 Event
Description:
MFW Reg Valve C Controller Fails Closed - Manual Control Available Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- T = 25 minutes or at the discretion of the Lead Examiner
- MFW Reg Valve (FRV) C Fails Closed - Manual Control Available o Insert Malfunction (AE) AEFC0530_1, Value = 0, Ramp = 90 sec
- If contacted as SOT to check for problems locally at FRV C, report no abnormal conditions can be seen at the valve.
- When contacted, respond as EDO. Acknowledge entry into the OTO.
Indications Available:
T = 25 ANN 110D, SG C FLOW MISMATCH OTO-AE-00001, Feedwater System Malfunction OTO-AE-CRS Implement OTO-AE-00001, Feedwater System Malfunction 00001 NOTE Steps 1 through 3 are immediate action steps (NOTE) Crew goes to step 9 after completion of step 2 (Step 1) Place rod control in auto:
- RNO - End of immediate actions - Go to Step 9 (Step 9) CHECK running main feed pump(s) speed - meets both of the following BOP
- Controlling in auto
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 3 Page 10 of 23 Event
Description:
MFW Reg Valve C Controller Fails Closed - Manual Control Available Proc /Time Position Applicants Actions or Behavior OTO-AE- (Step 11) CHECK MFW reg valves - Controlling in AUTO 00001 BOP
- AE FK-530 (SG C) - NO Go to RNO Manual Operation of AE FK-530 may have already been taken (NOTE) using Prudent Operator Action in accordance with ODP-ZZ-00001, Section 4.7 (Step 11 RNO) Perform the following:
(Level can be restored using MFW reg valve in manual)
Critical Take manual control of FRV C prior to a reactor trip CREW Task occurring on low steam generator water level (Step 12) CHECK if MFW reg valve bypass - in service BOP
- NO Go to Step 14 (Step 14) CHECK condensate pump - tripped BOP
- NO Go to Step 18 (Step 18) CHECK heater drain pump - tripped BOP
- NO Go to Step 21
- (Step 21) CHECK steam generator NR level within one of the following:
- Trending to between 45% and 55%
BOP or
- Between 45% and 55%
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 3 Page 11 of 23 Event
Description:
MFW Reg Valve C Controller Fails Closed - Manual Control Available Proc /Time Position Applicants Actions or Behavior OTO-AE- #(Step 22) Monitor rod control system responding to RCS 00001 Tavg/Tref deviation by ensuring one of the following:
- Control rods are inserting and RCS Tavg trending to within RO 3°F of Tref or
- RCS Tavg within 3°F of Tref BOP (Step 23) CHECK MFP oil pressure - NORMAL (Step 24) Review applicable Technical Specifications CRS
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 3 rev.5 Event # 4 Page 12 of 23 Event
Description:
Refueling Water Storage Tank (RWST) Level Channel Fails Low Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- T = 35 minutes or at the discretion of the Lead Examiner
- RWST Level Channel fails low o Insert Malfunction (BN) BNLT0932, Value = 0
- When contacted, respond as Operations Technician (OT) and inform the Control Room that no abnormalities are found in the RWST valve house associated with RWST level instruments.
- When contacted, respond as EDO. Acknowledge entry into the OTO.
Indications Available:
T = 35 ANN 47A, RWST EMPTY ANN 47B, RWST LEV LOLO 2 ANN 47D, RWST LEV HILO OTO-BN-00001, RWST Level Channel Malfunction CRS Implement OTO-BN-00001, RWST Level Channel Malfunction (Step 1) CHECK RWST level instruments indications - reading BOP abnormal
- BN LI-932 - failed low (Step 2) Dispatch Equipment Operator to the RWST valve house CRS to inspect RWST level instruments (Step 3) Review applicable Technical Specifications:
- 3.3.2, Table 3.3.2-1, Item 7.b, Cond K Restore channel to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR Be in Mode 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND Be in Mode 5 in 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> CRS (Step 21) Perform notifications per ODP-ZZ-00001 NOTE At Lead Examiners discretion move to the next Event
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 5 Page 13 of 23 Event
Description:
Loss of PB03 - results in Reactor Trip Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- T = 40 minutes or at the discretion of the Lead Examiner
- Loss of Bus PB03 - Reactor Trip
- Insert Malfunction (PB) PB03, Value = Trip
- If contacted as SOT to check Bus PB03, report that there is a 186 lockout on PB03 feeder breaker PB0306.
- If contacted as EDO, acknowledge entry into the OTO.
Indications Available:
T = 40 ANN 16A, XPB03/04 XFMR LOCKOUT ANN 16B, PB03/04 BUS UV OTO-AE-00001, Feedwater System Malfunction CRS Implement OTO-AE-00001, Feedwater System Malfunction NOTE Crew may initially go to OTAs for loss of PB03 which will direct them to OTO-AE-00001 NOTE Steps 1 through 3 are immediate action steps NOTE Crew goes to step 9 after completion of step 2 (Step 1) Place rod control in AUTO:
- RNO - End of immediate actions - Go to Step 9 (Step 9) CHECK running main feed pump(s) speed - meets both of the following BOP
- Controlling in auto
- Stable
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 5 Page 14 of 23 Event
Description:
Loss of PB03 - results in Reactor Trip Proc /Time Position Applicants Actions or Behavior OTO-AE-BOP (Step 10) CHECK if MFW reg valves - in service 00001 BOP (Step 11) CHECK MFW reg valves - controlling in auto - YES (Step 12) CHECK if MFW reg valve bypass - in service BOP
- NO Go to Step 14 BOP (Step 14) CHECK condensate pump - tripped - YES (Step 15) CHECK reactor power - greater than 45% - YES
- If less than two condensate pumps are running, then CREW perform the following:
- 1) Manually trip the reactor
- 2) Go to E-0, Reactor Trip or Safety Injection NOTE Crew may trip the reactor prior to Step 14 based on prudent operator action in accordance ODP-ZZ-00025, EOP/OTO User's Guide, if SG levels are approaching the trip setpoint Once the reactor has been tripped GO TO THE NEXT EVENT
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 15 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- If contacted as the Secondary Operator to investigate the TDAFP trip, inform the CR that the pump appears to have oversped and cannot be reset due to the linkage being bent.
- If contacted as the Secondary Operator to investigate the A MDAFP, inform the CR that the discharge valve is bound up at about 10% open and cannot be opened further.
- When contacted as the Secondary OT to line up the Non Safety Aux Feed Pump IAW Add 38, perform the following:
Insert Remote (AL) ALV0200, Value = 100, Ramp = 10 sec Insert Remote (AP) APV0022, Value = 100 Insert Remote (AP) APV0012, Value = 0.0 Indications Available:
ANN 87F, MANUAL RX TRIP E-0, Reactor Trip or Safety Injection CRS Implement E-0, Reactor Trip or Safety Injection (NOTE) Steps 1 through 4 are immediate action steps (Step 1) CHECK reactor trip:
- Rod bottom lights - all lit RO
- Reactor trip and bypass breakers - open
- Neutron flux - lowering (Step 2) CHECK turbine trip:
- a. All turbine stop valves - CLOSED (Step 3) CHECK power to AC emergency buses:
- b. AC emergency buses - both energized
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 16 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior E-0 (Step 4) CHECK SI status:
CREW
- PZR pressure less than or equal to 1849 psig BOP
- Any SG pressure less than or equal to 615 psig
- Containment pressure greater than or equal to 3.5 psig If SI is not required, then go to ES-0.1, Reactor Trip Response ES-0.1 CRS Implement ES-0.1, Reactor Trip Response Call STA to initiate CSF Status Tree Monitoring in accordance with CRS ODP-ZZ-00025, EOP/OTO User's Guide step 4.24.8
- (Step 1) CHECK RCS temperature control:
BOP a. Check RCPs - any running
- b. Check RCS temperature response - normal
- (Step 2) CHECK status of AC buses:
BOP a. Check generator output breakers - open
- b. Check all AC buses - energized by offsite power (Step 3) CHECK PZR pressure control:
RO a. Pressure - greater than 1849 psig
- b. Pressure - stable at or trending to 2235 psig (Step 4) CHECK PZR level control:
- a. PZR level - greater than 17%
- b. Check instrument air supply containment isolation valve -
open (KA HIS-29)
- c. Check charging - in service NO Go to RNO - See Below
- d. Check letdown - in service
- e. PZR level - trending to 25%
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 17 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior SIM After completion of Step 4 of ES-0.1 or at the discretion of the Operator TDAFW Lead Examiner, Trip the TDAFW Pump by inserting the following:
Pump Insert Malfunction (AL) PAL02_1, Value = True ES-0.1 (Step 4 RNO for no charging in service)
RNO 4.c. Establish charging:
RO a. Ensure CCP recirc valves are open:
- BG HIS-8110
- BG HIS-8111
- b. Start one CCP:
- BG HIS-2A (B CCP)
Critical Manually start CCP B prior to initiating a RCS bleed and CREW Task feed due to having no CCPs in service NOTE Crew may notice no charging flow prior to Step 4 and start CCP B at that time (Step 5) CHECK shutdown reactivity status:
- a. Check all control rods - fully inserted RO
- b. Check if uncontrolled RCS dilution - in progress NO Go to RNO Go to Step 6 (Step 6) CHECK Feedwater status:
- a. Check RCS Tavg - less than 564°F
- d. Check main feedwater reg bypass valves - closed
- e. Check total feed flow to SGs - greater than 285,000 lbm/hr NO Go to RNO
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 18 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior ES-0.1 (Step 6.e RNO for total AFW flow less than 285,000 lbm/hr)
Establish feed flow to SG(s) as necessary using AFW.
BOP If feed flow cannot be established, then monitor conditions for transition to FR-H.1 Transition to FR-H.1 may occur prior to Step 6 if STA (NOTE) completes CSF review and reports heat sink red path to CRS prior to completion of ES-0.1, Step 6 FR-H.1 CRS Implement FR-H.1, Response To Loss Of Secondary Heat Sink (Step 1) CHECK if secondary heat sink is required:
- RCS temperature - greater than 350°F
- RCS pressure - greater than 360 psig
- (Step 2) CHECK if RCS bleed and feed - required:
- a. Any RCS bleed and feed condition - satisfied
- PZR pressure - greater than 2335 psig due to loss of secondary heat sink
Bleed and feed not required - Go to RNO RNO 2.a Perform the following:
- 1) Monitor RCS bleed and feed conditions
- 2) If any condition occurs, then perform Step 2.b and 2.c
- 3) Continue with Step 3
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 19 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior FR-H.1 (Step 3) Try to establish AFW flow to at least one SG:
- a. Check SG blowdown isolation
- SG blowdown containment isolation valves -
Closed
- SG sample outer containment isolation valves -
Closed
- c. Try to restore AFW flow
- d. Check total flow to SGs - greater than 285,000 lbm/hr NO Go to RNO RNO 3.d. If any feed flow to at least one SG is NOT verified, then perform the following:
- 1) Perform EOP Addendum 38, Non Safety Auxiliary Feedwater Pump
- 2) Dispatch Operator to locally restore AFW flow.
- 3) Go to Step 4 NOTE Crew may take MAN control of Pressurizer Pressure Controller to lower RCS pressure when > 2250 psig EOP ADD Implement EOP Addendum 38, Non Safety Auxiliary CRS 38 Feedwater Pump (Addendum Assigned to BOP)
(Step 1) CHECK AEPS 4.16 KV PB05 Bus energized by one of the following:
- At least one alternate emergency power supply (AEPS)
- Central electric power reform substation
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 20 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior EOP Add (Step 2) Locally align the non safety aux feedwater pump:
38 a. Open ALV0200, NS AFP TO TDAFP Disch Upstrm ISO BOP b. Open APV0022, CST Drain
- c. Close APV0012, CST Makeup To Hotwell Iso Vlv
- d. Notify control room NS AFP status (Step 3) Throttle the following TD AFP AFW Reg Valves - 25%
open:
- AL HK-10A
- AL HK-12A
- AL HK-6A NOTE on A dry SG is any SG WIDE RANGE level less than 10% [25%] AND FOP NO feed flow established.
(Step 4) Close CST makeup to hotwell level control valve:
- a. Close condenser hotwell makeup level controller by BOP placing controller in manual and zero output:
- At least one alternate emergency power supply (AEPS)
- Central Electric Power Reform Substation (Step 6) Start the Non Safety Aux Feedwater pump:
- a. Check Step 2 alignment - complete BOP b. Using PBXY0001 CLOSE NS AFP FDR BKR PB0504:
PB0504
- c. Monitor running NS AFW pump operation
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 21 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior Critical Manually start the Non Safety Auxiliary Feedwater Pump IAW Task CREW FR-H.1 prior to initiating a RCS bleed and feed due to Steam Generator low level EOP (Step 7) Establish and maintain NS AFW flow - less than BOP Add 38 280,000 lbm/hr
- (Step 8) CHECK CST to AFP suction header pressure - greater BOP than 2.75 psig (Step 9) Monitor AEPS system using PBXY0001:
- Watts BOP
- Amps
- Volts
- Fuel (DG only)
(Step 10) Notify Jefferson City Oil to refuel AEPS DGs as BOP necessary:
(Step 11) CHECK addendum entry status:
- a. Entry - from FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK - YES
- b. Determine if Safety Injection has been actuated due to BOP RCS Bleed and Feed required - NO RNO 11.b. Return to FR-H.1, Response To Loss of Secondary Heat Sink, 3.d.
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 22 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior FR-H.1 (Step 3.d) Check total flow to SGs - greater than 285,000 lbm/hr NO Go to RNO RNO 3.d. If any feed flow to at least one SG is verified, then perform the following:
- 1) Maintain flow to restore narrow range level to greater than 7% [25%].
- 2) WHEN narrow range level is greater than 7%
[25%], THEN Return to procedure and step in effect.
- 3) Go To Step 4 (Step 4) Transfer Condenser Steam Dump to Steam Pressure Mode:
- a. CHECK Condenser - AVAILABLE
- C-9 interlock - LIT
- MSIVs - ANY OPEN
- AB PK-507
- c. PLACE Steam Dump Select switch in STM PRESS position:
- AB US-500Z
- d. PLACE Steam Header Pressure Controller in AUTO:
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 3 rev.5 Event # 6,7,8,9 Page 23 of 23 Event
Description:
Reactor Trip/A CCP Trips/MDAFAS Fails to Actuate (Both Trains)/TDAFW Pump Trips/MDAFW Pump A Discharge Flow Degraded Proc /Time Position Applicants Actions or Behavior (Step 6) Try to Establish Main Feedwater To At Least ONE SG:
- a. Check Condensate System - IN SERVICE
- b. RESET SI if necessary:
- SB HS-42A
- c. RESET FWIS:
- SB HS-17
- SB HS-18
- d. Bypass the FWIS using EOP Addendum 29, FWIS Bypass Operation Examiner FW ISO If Crew attempts to use EOP Addendum 29, inform them that CUE Valves the FW Isolation Valves will not open (Step 6 cont'd)
- e. Open at least one Feedwater Isolation Valve:
RNO 6.e. If NO Feedwater Isolation Valve can be opened, THEN Go To Step 10.
FR-H.1 (Step 10) Check For Loss of Secondary Heat Sink:
- WIDE RANGE level in any three SGs - LESS THAN 27%
[42%] - NO OR
- PZR pressure - GREATER THAN 2335 PSIG DUE TO LOSS OF SECONDARY HEAT SINK - NO RNO Step 10 - Return to Step 1. Observe CAUTIONS prior to Step 1.
NOTE Once flow has been established to the SGs through the Non Safety Aux Feedwater Pump IAW Addendum 38, or at the EVAL discretion of the Lead Evaluator - the scenario can be STOPPED NOTE Follow up Question to CRS:
With the existing Steam Generator Feed Flow Rate, what is the procedural guidance?
Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 4, Rev. 6 Op-Test No.: 2013301 Examiners: ____________________________ Operators: _____________________________
Initial Conditions: A Reactor Startup has just been completed with Reactor power just above the Point of Adding Heat (POAH). A Train CCW in Service.
Turnover: The plant is in Mode 2. Reactor Startup has just been completed on the previous shift.
Conditions are being held steady while the on-coming crew is performing Just In Time Training for the
-6 -6 power increase and directed to maintain power between 1.0 X 10 to 2.0 X 10 amps. Callaway County is under a severe thunderstorm watch. The crew is directed to shift CCW train Service Loops from the "A" to the "B" Train for normal equipment rotation.
Event Malf. No. Event Event No. Type* Description RO (N) 1 N/A Swap CCW Train Service Loops from A to B Train SRO (N)
SRO (I) 2 BBPT0455 Pressurizer pressure channel 455 fails high (Tech Spec)
RO (I)
BOP (C) 3 ABPV0002A Atmospheric Steam Dump Failure on B SG (Tech Spec)
SRO (C)
SRO (C) 4 XMR01_1 Loss of ESF transformer XNB02 causing a Loss of NB02/
BOP (C)
PEF01B_1 EDG B starts, ESW Pump B trips (Tech Spec)
RO (C)
SRO (M) 5 Loss of Offsite Power, A EDG fails to start Automatically, Loss MD RO (M) of All AC Power, Manual Reactor Trip BOP (M)
BBPCV RO (C) 6 Pressurizer PORV Fails Partially Open 0455A SRO (C)
PEF01A_2 SRO (C) 7 ESW Pump A Auto Start Failure BOP (C)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 2
- 6. EOP contingencies requiring substantive actions (0-2) 0
- 7. Critical tasks (2-3) 3
Scenario Event Description Callaway 2013 NRC Scenario #4, rev. 6 The plant is in Mode 2. Reactor Startup has just been completed on the previous shift. Conditions are being held steady while the on-coming crew is performing Just In Time Training prior to the startup.
Callaway County is under a severe thunderstorm watch.
The crew starts the scenario by having the ATC Applicant shift CCW Service Loops from the A to the B Train for normal equipment rotation.
Once the Pumps have been shifted, Pressurizer Pressure Channel, PT-455 fails high. The crew should respond IAW OTO-BB-00006, Pressurizer Pressure Control Malfunction, and selects away from the failed channel prior to the reactor tripping on low pressurizer pressure. T.S. 3.3.1, 3.3.2, and 3.3.4 apply.
Once Tech Specs are addressed, SG B Atmospheric Steam Dump fails Open. The crew should respond per OTO-AB-00001, Steam Dump Malfunction, close the failed valve and initiate action to make repairs. T.S. 3.7.4 applies.
A fault on ESF Transformer XNB02 occurs, resulting in a loss of power to Bus NB02. B EDG starts, but Essential Service Water Pump B trips 3 minutes following pump start, forcing the crew to trip the affected Diesel and enter OTO-NB-00002, Loss of Power to NB02. Technical Specifications 3.8.1, 3.8.4, 3.8.7, and 3.8.9 apply. The crew will also have to shift back to A Train CCW service loop and stop Aux Feed Flow to the Steam Generators from the Turbine Driven Aux Feed Pump.
Due to the severe weather, a fault at the Montgomery substation results in a Loss of Offsite power. Upon the loss of offsite power, the crew sees that the A EDG has not started causing a loss of power to NB01.
Since there is no power to NB01 or NB02, the crew will transition to ECA-0.0, Loss of All AC Power and perform the Immediate Actions. The reactor should be tripped when performing Immediate Actions.
When the crew gets to Step 5 of ECA-0.0, they will attempt to start the A Emergency Diesel Generator and it will start, however the A ESW pump fails to start automatically, but should be started manually.
Once power is restored to NB01, the crew will transition to E-0, Reactor Trip or Safety Injection and perform appropriate actions. Once the crew has completed applicable portions of E-0 and transitioned to ES-0.1, Reactor Trip Response, PZR PORV, BB PCV-455A, fails partially open. BB PCV-455A should be isolated prior to RCS pressure lowering to the Safety Injection setpoint.
The scenario will be stopped when the crew is required to Transfer Steam Dumps to the Steam Pressure Mode at Step 8 of ES-0.1 or at the discretion of the Lead Examiner.
Callaway 2013 NRC Scenario #4, rev. 6 Critical Tasks:
Event #2 CT - Select away from the failed Pressurizer Pressure Channel prior to Reactor tripping on low pressurizer pressure.
Event #6 CT - Manually close the PORV before receiving a Safety Injection.
Event #7 CT - Manually start ESW Pump A before Emergency Diesel Generator NE01 trips on high temperature.
References OTG-ZZ-00002, Reactor Startup OTN-EG-00001, Component Cooling Water System OTO-BB-00006, Pressurizer Pressure Control Malfunction OTO-AB-00001, Steam Dump Malfunction OTO-NB-00002, Loss of Power to NB02 E-0, Reactor Trip or Safety Injection ECA-0.0, Loss of All AC Power ES-0.1, Reactor Trip Response Tech Spec 3.3.1, Reactor Trip System Instrumentation Tech Spec 3.3.2, ESFAS Instrumentation Tech Spec 3.3.4, Remote Shutdown System Tech Spec 3.7.4, Atmospheric Steam Dump Valves (ASDs)
Tech Spec 3.8.1, AC Sources - Operating ODP-ZZ-00025, EOP/OTO User's Guide
Callaway 2013 NRC Scenario #4, rev. 6 Scenario Setup Guide:
Establish the initial conditions of IC-167, BOL 10-6% power:
- CCP A and B 1222 minus 5 days
- Rod Control Bank C is 216 steps and Control Bank D is 100 steps, Other banks 228 steps
- ENSURE BB PT-455 is selected on BB PS-455F
- ENSURE A Train CCW is in service
- RCS Press / Temp - 2236 / 559.5
- PZR Master Controller pot set at 6.61 turns
- Screen set up for "OTGZZ3"
=======SCENARIO PRELOADS / SETUP ITEMS==========
NE01 fails to start automatically following Loss of Offsite Power
- Insert Remote (KJ) DGBLOCK_1, Value = Block_Auto
======= EVENT 2 ============================
Pressurizer Pressure Channel BB PT-455 fails high
- Insert Malfunction (BB) BBPT0455, Value = 2500, Ramp = 15 secs
======= EVENT 3 ============================
Atmospheric Steam Dump Failure on "B" SG
- Insert Malfunction (AB) ABPV0002A_1, Value = 1.0, Ramp = 30 secs
======= EVENT 4 ============================
Loss of Startup Transformer (SUT) - NE02 starts, but ESW Pump "B" Trips
- Insert Malfunction (EF) PEF01B, Value = Trip, delay = 3 min, conditional = hwx19o241r eq 1
=======EVENT 5 ===================
Loss of Offsite Power / DG"A" to Auto Start / ESW Pump "A" Fails to Auto Start "A" ESW Fails to start Automatically
- Insert Malfunction (EF) PEF01A_1, Value = Block Loss of Offsite Power
- Run Lesson "ALL/GENERIC/lossofswitchyard" NE01 Fails to start on Loss of Offsite Power
- SEE PRELOADS ABOVE
=======EVENT 6 ============================
Pressurizer PORV Fails Partially Open after Entry into procedure ES-0.1
- Insert Malfunction (BB) BBPCV0455A_1, Value = 0.1, Ramp = 5 sec
=======EVENT 7 ===============
ESW Pump "A" Fails to Auto Start
- SEE EVENT 5 ABOVE
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 1 Page 5 of 23 Event
Description:
Swap CCW Train Service Loops from A to B Train Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions
- If asked which pump has the least amount of run time, inform the crew "B" Pump will be started. (Step 5.6.2) This will be addressed during shift turnover.
OTN-EG-00001, Component Cooling Water System Section 5.6, Running Both Trains, Shifting Trains Or Service Loop From Train A to Train B T=0 Shift from the "A" CCW Train to the "B" CCW Train by starting CRS the "B" CCW Pump and shifting to the "B" Service Loop, but leave "A" CCW Pump running OTN-EG- (Step 5.6.1) Ensure that SW/ESW cooling water is in service to 00001, RO the B CCW Heat Exchanger with EF HIS-52, ESW TRN B TO Sect 5.6 CCW HX B , open (Step 5.6.2) If neither CCW pump B or D is running, Perform the following:
- a. Ensure the B CCW Surge Tank level is greater than 50%
- b. Determine the pump with the least run time on the equipment log (cued during the turnover)
- c. Using the applicable switch, START the "B" CCW pump
- EG HIS-22, CCW PUMP B (Step 5.6.3) If shifting service loop from A to train B, Perform the following:
- a. Using EG HIS-9, CLOSE EGRV00009
- b. Using EG HIS-10, CLOSE EGRV0010 RO
- c. Using EG HS-16, OPEN EGHV0016 and EGHV0054
- d. Using EG HS-15 CLOSE EGHV0015 and EGHV0053
- e. Using EG HIS-9, OPEN EGRV00009
- f. Using EG HIS-10, OPEN EGRV0010
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 1 Page 6 of 23 Event
Description:
Swap CCW Train Service Loops from A to B Train Proc /Time Position Applicants Actions or Behavior OTN-EG-(Step 5.6.4) Using EC HIS-12, THROTTLE ECHV0012 as 00001, RO needed to clear flow alarms Sect 5.6 (Step 5.6.5) If NOT Required for the safety loop loads (CCP, SFP, SI, RHR), STOP the running train A CCW pump and RO ENSURE the handswitches are in AUTO NOTE The turnover has the crew keep the "A" CCW Pump running (Step 5.6.6) Inform the shift Chemistry technician that CCW RO Train B is in service.
(Step 5.6.7) As necessary for coarse adjustment, using EG RO HIS-102, CCW TO RHR HX B, THROTTLE EGHV0102 to maintain annunciator 75 D, SFP TEMP HI, clear.
(Step 5.6.8) Ensure the CCW Heat Exchanger being removed from service is either in the winter or summer alignment as RO appropriate per Step 3.2.10.
NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 2 Page 7 of 23 Event
Description:
Pressurizer Pressure Channel 455 Fails High (Tech Spec)
Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- T = 15 minutes or at the discretion of the Lead Examiner
- Pressurizer Pressure Channel BB PT-455 fails high
- Insert Malfunction (BB) BBPT0455, Value = 2500, Ramp = 15 secs
- If contacted as I&C, acknowledge request to trip bistables and troubleshoot failed channel.
- If contacted, respond as EDO. Acknowledge entry into the OTO.
Indications Available:
T= 15 ANN 33B, PZR HI PRESS DEV ANN 33C, PZR PRESS LO HTRS ON OTO-BB-00006, Pressurizer Pressure Control Malfunction OTO-BB- Implement OTO-BB-00006, Pressurizer Pressure Control CRS 00006 Malfunction (Step 1) CHECK pressurizer pressure indicator - failed
- BB PI-455A YES RO
- BB PI-456
- BB PI-457
- BB PI-458 (Step 2) CHECK pressurizer pressure
- a. Between 2225 psig and 2250 psig RNO a. - Stabilize Pressurizer Pressure RO
- 1) PLACE PZR Press Master CTRL in MANUAL
- 2) RESTORE Pressurizer pressure between 2225 psig and 2250 Examiner The Crew may enter DNB Tech Spec 3.4.1 due to Pressurizer NOTE Pressure lowering to less than 2223 psia
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 2 Page 8 of 23 Event
Description:
Pressurizer Pressure Channel 455 Fails High (Tech Spec)
Proc /Time Position Applicants Actions or Behavior OTO-BB- (Step 3) If Required TRANSFER Pressurizer Pressure Control 00006 RO Selector to Remove Failed Channel From Control
- BB PS-455F (Selects P457/P456)
Critical Select away from the failed Pressurizer Pressure Channel CREW Task prior to Reactor tripping on low pressurizer pressure.
(Step 4) CHECK Pressurizer Pressure Within one of the Following:
- Trending to between 2225 psig and 2250 psig OR
- Between 2225 and 2250 psig (Step 5) RESTORE Pressurizer Pressure to AUTO CONTROL
- a. Verify PZR Spray Valves are in AUTO:
- BB PK-455B, PZR Spray Loop 1 Ctrl RO
- BB PK-455C, PZR Spray Loop 2 Ctrl
- b. PLACE PZR Press Master CTRL in AUTO
- BB PK-455A (Step 6) CHECK permissive P-11 is in the correct state within one RO hour of the pressurizer pressure channel failure
- Current time ________________
(Step 7) Select an operable channel for the following:
- RCS pressurizer pressure recorder:
BB PS-455G
- OPDT/OTDT temperature recorder:
BOP SC TS-411E
- Computer digital readout display:
REP0480A REP0481A REP0482A REP0483A
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 2 Page 9 of 23 Event
Description:
Pressurizer Pressure Channel 455 Fails High (Tech Spec)
Proc /Time Position Applicants Actions or Behavior OTO-BB- (Step 8) Review Applicable Technical Specifications:
00006
- Refer to Att J, Technical Specifications 3.3.1, Table 3.3.1-1, Item 6, 8b Cond E o Place channel in trip within in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR be in Mode 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> 3.3.1, Table 3.3.1-1, Item 8a, Cond M o Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR reduce thermal power to < P-7 3.3.2, Table 3.3.2-1, Item 1d, 9b Cond D CRS o Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR be in Mode 3 within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND be in Mode 4 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> 3.3.2, Table 3.3.2-1, Item 8b, Cond L o Verify interlock is in required state for existing unit condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND be in Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 3.3.4, Table 3.3.4-1, Item 3 o Restore required Function and required ASP Controls to Operable status within 30 days (Step 9) Record Permissive P-11 is in the correct state in the CRS control room log (Step 10) Review Attachment A, Effects of Pressurizer Pressure CRS Instrument Failure NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 3 Page 10 of 23 Event
Description:
Atmospheric Steam Dump Failure on "B" SG (Tech Spec)
Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- Insert Malfunction (AB) ABPV0002A_1, Value = 1.0, Ramp = 10 secs
- If contacted as Count Room Tech, acknowledge the time the "B" Steam Generator Atmospheric Steam Dump (ASD) was Open Indications Available:
T = 25 ANN 109F, SG PORV OPEN OTO-AB-00001, Steam Dump Malfunction CRS Implement OTO-AB-00001, Steam Dump Malfunction OTO-AB- #(Step 1) CHECK Reactor Power - Less than 100%
00001
- SE NI-41B
- SE NI-42B
- SE NI-44B
- BB TI-411A (T)
- BB TI-421A (T)
- BB TI-431A (T)
- BB TI-441A (T)
RO (Step 2) CHECK at least One SG ASD - Failed Open (SG B)
(Step 3) Place the affected SG ASD Controller in Manual and BOP CLOSE the Valve
(Step 4) Notify Count Room Technician of Opening and Closing BOP Times of the SG ASD
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 3 Page 11 of 23 Event
Description:
Atmospheric Steam Dump Failure on "B" SG (Tech Spec)
Proc /Time Position Applicants Actions or Behavior OTO-AB-BOP (Step 5) Go To Step 12 00001 BOP (Step 12) Initiate Actions to Repair the failed component (Step 13) Review Technical Specification 3.7.4 A CRS
- Restore required ASD line to Operable status within 7 days NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 4 Page 12 of 23 Event
Description:
Loss of ESF Transformer XNB02 causing Loss of NB02 / EDG "B" starts, ESW Pump "B" trips (Tech Spec)
Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- T = 30 minutes or at the discretion of the Lead Examine Loss of Startup Transformer / Loss of NB02 / EDG Starts / ESW Pump "B" Trips
- Insert Malfunction (NB) XNB02_1, Value = True
- Insert Malfunction (EF) PEF01B, Value = Trip (PRELOADED)
Indications Available:
T = 30 ANN 21B, NB02 BUS UV ANN 22A, XNB02 XFMR LOCKOUT ANN 22E, NB02 BUS DGRD VOLT OTO-NB-00002, Loss of Power to NB02 OTO-NB- #(Step 1) CHECK 4160 VAC Bus NB02 - DEENERGIZED 00002 CRS/ RO
- RNO GO TO Attachment A, Power Restored to NB02
- (Step A1) CHECK 4160VAC Bus NB02 - ENERGIZED
- 4.16KV Bus NB02 light - LIT - YES BOP/RO
- 4.16 KV Bus NB02 Voltage indicates approximately 4160 volts BOP/RO (Step A2) CHECK EDG B - RUNNING BOP/RO (Step A3) CHECK ESW Flow - Aligned to EDG B (Step A4) CHECK ESW Train A - Properly Aligned
- ESW Pump A - Running EF HIS-55A BOP/RO
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 4 Page 13 of 23 Event
Description:
Loss of ESF Transformer XNB02 causing Loss of NB02 / EDG "B" starts, ESW Pump "B" trips (Tech Spec)
Proc /Time Position Applicants Actions or Behavior OTO-NB- Stop Auxiliary Feedwater Flow to "B" and "D" SGs by taking 00002 BOP prudent operator action in accordance with ODP-ZZ-00025, Section 4.27 (Step A5) CHECK Reactor Power - Less Than 100%
- SE NI-41B
- SE NI-42B
- SE NI-44B
- BB TI-411A (T)
- BB TI-421A (T)
- BB TI-431A (T)
- BB TI-441A (T)
(Step A6) CHECK RHR - In Service Prior To The Event RO NOGo To RNOGo To Step A9 of this attachment ESW Pump B trips 3 minutes after starting - crew should perform the following using Step A3 RNO
- b. If ESW flow can not be established to EDG B AND control of the EDG is from the Control Room, THEN PRESS DG NE02 Stop switch to stop EDG B (This will not work because of the U/V)
(NOTE)
- c. If ESW flow can not be established to EDG B AND control of the EDG is local, THEN PERFORM the following
- 1) PLACE Master Transfer Switch in LOCAL/MAN
- 2) Press DG train B local STOP push-button to stop to stop EDG SIM Insert Remote Function (KJ) KJHS0109, Value = Local_Manual Operator SIM Insert Remote Function (KJ) KJHS0108B, Value = Stop
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 4 Page 14 of 23 Event
Description:
Loss of ESF Transformer XNB02 causing Loss of NB02 / EDG "B" starts, ESW Pump "B" trips (Tech Spec)
Proc /Time Position Applicants Actions or Behavior NOTE Crew should go back to continuous Action Step #1, since the Bus is now DEENERGIZED OTO-NB-00002 CRS #(Step 1) CHECK 4160 VAC Bus NB02 - DEENERGIZED RO (Step 2) CHECK Reactor Power - Less than 100%
(Step 3) CHECK CCW Pump A or C - running RO/BOP
- RNO - START CCW Pump A or CCW Pump C (Step 4) CHECK CCW Service Loop is being supplied from Train A:
- RNO - Perform the Following
- a. Close both CCW Surge Tank Vent Control valves
- d. Dispatch an Operator to locally close the following valves EGHV0016 EGHV0054
- e. OPEN both CCW Surge Tank Vent Control valves SIM When contacted as the Primary Ops Tech:
OPER Insert Remote Function (EG) EGHV0016, Value = 0 Insert Remote Function (EG) EGHV0054, Value = 0 Wait 5 min and inform the Control Room valves are CLOSED RO/BOP (Step 5) CHECK if CCW aligned to the RCPs (Step 6) CHECK RHR- IN Service Prior to Event CRS
- RNO - GO TO Step 9
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 4 Page 15 of 23 Event
Description:
Loss of ESF Transformer XNB02 causing Loss of NB02 / EDG "B" starts, ESW Pump "B" trips (Tech Spec)
Proc /Time Position Applicants Actions or Behavior OTO-NB- #(Step 9) CHECK Steam Generator NR Level Within One of the 00002 Following:
- Trending to between 45% and 55%
- Between 45% and 55%
(Step 10) CHECK Turbine Driven Auxiliary Feedwater Pump SECURED
- RNO:
- If Turbine Driven Auxiliary Feedwater Pump is NOT Required to maintain SG level, Then Throttle or CLOSE TD AFP AFW Reg Valves This may have been completed earlier in accordance with ODP-NOTE ZZ-00025, Section 4.27
- (Step 11) CHECK Pressurizer Level Within One of the Following
- At Program Level
- (Step 12) CHECK Pressurizer Pressure Within One of the Following:
- Trending to between 2225 psig and 2250 psig OR
- Between 2225 psig and 2250 psig (Step 13) ENSURE the following 4160VAC bus NB02 loads shed:
(Load Shed Emergency Load Sequencing (LSELS) actuation, handswitch lit green)
- ESW Pump B CRS/RO
- CCW Pump B/D
- SI Pump B
- Ctmt Spray Pump B
- RHR Pump B
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 4 Page 16 of 23 Event
Description:
Loss of ESF Transformer XNB02 causing Loss of NB02 / EDG "B" starts, ESW Pump "B" trips (Tech Spec)
Proc /Time Position Applicants Actions or Behavior OTO-NB- (Step 14) OPEN NB02 Normal Alternate Feeder Breakers 00002 RO
- NB HIS-4, NB02 Normal Supply Breaker NB0209
- NB HIS-5, NB02 Alternate Supply Breaker NB0212 NOTE 'B' Train CCW pump handswitches are placed in Pull-To-Lock to prevent breaker cycling while NB02 is de-energized Refer to the following Technical Specifications:
T.S. 3.8.1, AC Sources, Condition B; Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, perform Surveillance requirement 3.8.1.1 (OSP-NE-00003) for the offsite circuits AND once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
Restore DG to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> CRS T.S. 3.8.4, DC Sources, Condition A; Restore DC electrical power subsystem to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> T.S. 3.8.7, Inverters, Condition A; Restore inverter to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> T.S. 3.8.9, Distribution Systems, Condition A, Restore AC electrical power distribution subsystem to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Examiner There are numerous Technical Specifications to address following NOTE a Loss of NB Bus. Suggest waiting until after the Scenario is complete to ask the SRO which Tech Specs he would apply.
NOTE At Lead Examiners discretion move to the next Event
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 5/6/7 Page 17 of 23 Event
Description:
Loss of Offsite Power and Failure of EDG "A" to AUTO Start Post Trip PZR PORV Fails Partially Open and ESW Pump "A" Fails to AUTO Start Proc /Time Position Applicants Actions or Behavior Booth Operator Instructions:
- T = 50 minutes or at the discretion of the Lead Examiner
- Insert Malfunction (EF) PEF01A_1, Value = Block
- Run Lesson ALL/GENERIC/lossofswitchyard.lsn
- The Failure of EDG "A" to Auto Start is preloaded
- When contacted, respond as EDO. Acknowledge entry into the OTO.
Indications Available:
T = 50 ECA-0.0, Loss of All AC Power ECA-0.0 CRS Transition to ECA-0.0, Loss of All AC Power Notes:
- Steps 1 and 2 are immediate action steps
- CSF status trees should be monitored for information only.
Functional Restoration Procedures should NOT be implemented (Step 1) CHECK Reactor Trip
- Reactor Trip and Bypass Breakers -OPEN - NO RO
- Neutron Flux - Lowering - NO RNO - Manually TRIP reactor (Step 2) CHECK Turbine Trip BOP
- All Turbine Stop valves - CLOSED (Step 3) Check if RCS is Isolated
- BB HIS-455A
- BB HIS-456A
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 5/6/7 Page 18 of 23 Event
Description:
Loss of Offsite Power and Failure of EDG "A" to AUTO Start Post Trip PZR PORV Fails Partially Open and ESW Pump "A" Fails to AUTO Start Proc /Time Position Applicants Actions or Behavior ECA-0.0 (Step 3 cont'd) CHECK if RCS is isolated - NO
- b. Letdown isolation valves - CLOSE RO
- c. RCS to Excess Letdown valves -CLOSE
- d. Reactor Head Vent Valves - CLOSED (Step 4) Check AFW Flow - GREATER THAN 285,000 LBM/HR RNO PERFORM the following:
- a. CHECK TD AFW Pump running.
IF TD AFW Pump is NOT Running, THEN START TD AFW Pump:
- 1) Open AFP Turbine Loop Steam Supply valve(s)
- 2) OPEN AFP Turbine Mechanical Trip/Throttle valve:
- FC HIS-312A
- 3) If TD AFW Pump Trips or fails to start, THEN PERFORM the following:
The pump should be running BOP b. ENSURE TD AFW Valves in proper alignment:
- 1) TD AFW FLOW Control Valves are OPEN or THROTTLED:
- AL HK-8A for S/G A
- AL HK-10A for S/G B
- AL HK-12A for S/G C
- AL HK-6A for S/G D
- 2) ESFAS status panel SA066X AFAS section WHITE valve light is LIT:
- AP-V015 (15C)
- 3) IF AFW flow greater than 285,000 LBM/HR can NOT be established or maintained, THEN PERFORM the following:
Appropriate AFW flow should be established.
Appendix D Operator Action Form ES-D-2 Op Test No.: 2013301 Scenario # 4 rev.6 Event # 5/6/7 Page 19 of 23 Event
Description:
Loss of Offsite Power and Failure of EDG "A" to AUTO Start Post Trip PZR PORV Fails Partially Open and ESW Pump "A" Fails to AUTO Start Proc /Time Position Applicants Actions or Behavior ECA-0.0 (Step 5) TRY to Restore Power to Any AC Emergency Bus:
- a. Energize AC emergency bus with diesel generator:
- 2) CHECK AC emergency buses - AT LEAST ONE ENERGIZED - NB01 is now ENERGIZED RO/BOP b. CHECK AC emergency buses - AT LEAST ONE ENERGIZED - YES
- c. CHECK ESW Pump associated with energized AC emergency bus(es) - RUNNING - NO RNO c. Perform the following:
- 2) START ESW Pump(s) as necessary
- d. Return to procedure and step in effect and IMPLEMENT Functional Recovery Procedures as necessary At this time the CREW should attempt to start the "A" Emergency (NOTE) Diesel Generator and it will start and load onto the bus (BB PCV-455A fails open when NB01 reenergizes)
Critical Manually start ESW Pump A before Emergency Diesel CREW Task Generator NE01 trips on high temperature.
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 4 rev.6 Event # 6/7 Page 20 of 23 Event
Description:
Loss of Offsite Power and Failure of EDG "A" to AUTO Start Post Trip PZR PORV Fails Partially Open and ESW Pump "A" Fails to AUTO Start Proc /Time Position Applicants Actions or Behavior E-0, Reactor Trip Or Safety Injection E-0 CRS Implement E-0, Reactor Trip or Safety Injection (NOTE) Steps 1 through 4 are immediate action steps (Step 1) CHECK reactor trip:
- Rod bottom lights - all lit RO
- Reactor trip and bypass breakers - open
- Neutron flux - lowering (Step 2) CHECK turbine trip:
- a. All turbine stop valves - closed (Step 3) CHECK power to AC emergency buses:
- NB01 is now Energized
CREW
- PZR pressure less than or equal to 1849 psig CREW
- Any SG pressure less than or equal to 615 psig
- Containment pressure greater than or equal to 3.5 psig If SI is not required, then go to ES-0.1, Reactor Trip Response ES-0.1 CRS Implement ES-0.1, Reactor Trip Response Pressurizer PORV Fails Partially Open after Entry into procedure ES-0.1 SIM
- Insert Malfunction (BB) BBPCV0455A_1, Value = 0.1, OPER Ramp = 5 sec
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 4 rev.6 Event # 6/7 Page 21 of 23 Event
Description:
Loss of Offsite Power and Failure of EDG "A" to AUTO Start Post Trip PZR PORV Fails Partially Open and ESW Pump "A" Fails to AUTO Start Proc /Time Position Applicants Actions or Behavior Call STA to initiate CSF Status Tree Monitoring in accordance with CRS ODP-ZZ-00025, EOP/OTO User's Guide Critical CREW Manually close the PORV before receiving a Safety Injection.
Task ES-0.1 (Step 1) CHECK RCS temperature control:
- a. Check RCPs - any running - NO RNO a. - Transfer Condenser Steam Dumps to Steam RO Pressure Mode - Condenser is NOT available
- b. Check RCS temperature response - NORMAL
- RCS COLD LEG TEMPERATURES STABLE AT OR TRENDING TO 557°F IF NO RCP RUNNING - YES (Step 2) CHECK status of AC buses:
- Check generator output breakers - OPEN
- Check all AC buses - energized by offsite power - NO RNO b. PERFORM the following:
- 1) ENSURE Both PZR PORVs are in AUTO unless closed due to low PZR pressure:
- BB HIS -455A
- BB HIS-456A
- 2) ENSURE both PZR PORV Block Valves are energized and OPEN unless closed to isolate an Open PORV:
- BB HIS-8000A (NG01BBR3)
- BB HIS-8000B (NG01BDF1)
- 3) If any AC emergency bus(es) are NOT energized by offsite power, THEN ENSURE DGs have assumed their loads
- 5) Periodically CHECK status of Spent Fuel Pool Cooling
- 6) Try to restore Offsite power using EOP Addendum 7, Restoring Offsite Power
- 7) If Necessary, THEN LOAD equipment on AC emergency bus(es) using EOP Addendum 8, Loading Equipment on AC Emergency Buses
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 4 rev.6 Event # 6/7 Page 22 of 23 Event
Description:
Loss of Offsite Power and Failure of EDG "A" to AUTO Start Post Trip PZR PORV Fails Partially Open and ESW Pump "A" Fails to AUTO Start Proc /Time Position Applicants Actions or Behavior ES-0.1 (Step 3) CHECK PZR pressure control:
- a. Pressure - greater than 1849 psig
- b. Pressure - stable at or trending to 2235 psig RNO b. If pressure is less than 2235 PSIG AND lowering, THEN PERFORM the following:
IF any PORV can NOT be closed, THEN CLOSE associated Block Valve:
- BB HIS-8000A (BB HIS-455A)
- 2) Check PZR Spray Valves Closed - YES
- 3) Check PZR Heaters on - NO, no power (Step 4) CHECK PZR level control:
- a. PZR level - greater than 17%
- b. Check instrument air supply containment isolation valve -
- c. Check charging - in service
- d. Check letdown - in service
- e. PZR level - trending to 25%
(Step 5) CHECK shutdown reactivity status:
- a. Check all control rods - fully inserted RO
- b. Check if uncontrolled RCS dilution - in progress NO Go to RNO Go to Step 6 (Step 6) CHECK feedwater status:
- a. Check RCS Tavg - less than 564°F
- c. Check main feedwater reg valves - closed
- d. Check main feedwater reg bypass valves - closed
- e. Check total feed flow to SGs - greater than 285,000 lbm/hr
Operator Action Form ES-D-2 Appendix D Op Test No.: 2013301 Scenario # 4 rev.6 Event # 6/7 Page 23 of 23 Event
Description:
Loss of Offsite Power and Failure of EDG "A" to AUTO Start Post Trip PZR PORV Fails Partially Open and ESW Pump "A" Fails to AUTO Start Proc /Time Position Applicants Actions or Behavior (Step 7) CHECK SG Levels
- a. Narrow range levels - GREATER THAN 7%
- b. CONTROL feed flow to maintain narrow range levels between 7% and 52%
(Step 8) TRANSFER Condenser Steam Dumps to Steam Pressure Mode:
BOP a. CHECK condenser - AVAILABLE - NO RNO a. If Condenser steam dump is NOT available, THEN use SG ASD(s) as necessary for any subsequent cooldown.
NOTE Once Steam Dumps have been addressed or at the discretion EVAL of the Lead Examiner, the scenario can be STOPPED and the Simulator Frozen Examiner NOTE: Follow-up question to all Applicants Q. Why didn't the Reactor Trip upon loss of All AC power?
A. __________________________________________________________________
ES-301-5 rev. 3 Facility: Callaway Date of Exam: 3/18/2013 Operating Test No.: 2013301 A E Scenarios P V 1 2 3 4 T M P E (SPARE) O I L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(*)
T P S A B S A B S A B S A B R I U E R T O R T O R T O R T O O C P O C P O C P O C P RX 0 0 NOR 1 1 1 11 2 SROU-1 I/C 23 23 45 67 7 89 MAJ 6 5 2 1 TS 25 24 4 2 RX 0 0 NOR 1 1 1 9 2 SROU-2 I/C 23 34 67 7 89 MAJ 5 5 2 1 TS 24 2 2 RX 0 0 NOR 1 1 1 2
SROU-3 I/C 23 34 9 67 7 89 MAJ 5 5 2 1 TS 24 2 2 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301-5 rev. 3 Facility: Callaway Date of Exam: 3/18/2013 Operating Test No.: 2013301 A E Scenarios P V 1 2 3 4 T M P E (SPARE) O I L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(*)
T P S A B S A B S A B S A B R I U E R T O R T O R T O R T O O C P O C P O C P O C P RX *0 1 NOR 1 1 2 1 SROI-1 I/C 26 23 7 4 46 7
MAJ 5 5 2 2 TS 23 3 2 4
RX *0 1 NOR 1 1 2 1 SROI-2 I/C 26 23 7 4 46 7
MAJ 5 5 2 2 TS 23 3 2 4
RX *0 1 NOR 1 1 2 1 7 4 SROI-3 I/C 26 23 46 7
MAJ 5 5 2 2 TS 23 3 2 4
Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301-5 rev. 3 Facility: Callaway Date of Exam: 3/18/2013 Operating Test No.: 2013301 A E Scenarios P V 1 2 3 4 T M P E (SPARE) O I L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(*)
T P S A B S A B S A B S A B R I U E R T O R T O R T O R T O O C P O C P O C P O C P RX *0 1 NOR 1 1 2 1 RO-1 I/C 35 37 24 10 4 7 89 6 MAJ 6 5 5 3 2 TS 0 0 RX *0 1 NOR 1 1 1 4
RO-2 I/C 37 24 7 89 6 MAJ 5 5 2 2 TS 0 0 RX *0 1 NOR 1 1 1 4
RO-3 I/C 37 24 7 89 6 MAJ 5 5 2 2 TS 0 0 RX 5 1 1 NOR *0 1 4
RO-4 I/C 24 34 6 8 7 MAJ 6 5 2 2 TS 0 Instructions:
- 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301-5 rev. 3 Facility: Callaway Date of Exam: 3/18/2013 Operating Test No.: 2013301 A E Scenarios P V 1 2 3 4 T M P E (SPARE) O I L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y M(*)
T P S A B S A B S A B S A B R I U E R T O R T O R T O R T O O C P O C P O C P O C P RX 1 NOR 1 1 SPARE I/C 23 34 24 45 78 5 MAJ 6 6 6 TS 24 Instructions:
- 3. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 4. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301-5 rev. 3 Tuesday 3/19/12 SRO ATC BOP Scenario #
U1 I1 R1 3 U2 I2 R2 3 U3 I3 R3 3 Wednesday 3/20/12 SRO ATC BOP Scenario #
I1 R1 R4 4 I2 R2 U2 4 I3 R3 U3 4 U1 R4 R1 1 Standby scenario #2 used as needed
ES-301 Competencies Checklist Form ES-301-6 rev. 1 Facility: Callaway Date of Examination: 3/18/2013 Operating Test No.: 2013301 APPLICANTS SRO-U SRO-I RO Competencies SCENARIO SCENARIO SCENARIO 1 2* 3 4 1 2* 3 4 1 2* 3 4 Interpret/Diagnose 2, 3, 2, 3, 2, 3, 2, 3, 2, 3, 2, 5, 2, 3, 3, 7, Events and 5, 6 5, 8, 4. 5, 6 4, 5 4, 5, 8, 9
- 4. 5, 9 6, 7 6 6, 7 Conditions Comply With and Use 2, 3, 1, 2, 1, 2, 1, 2, 2, 3, 1, 2, 1, 2, 4, 5, 3, 5, 3, 4, 4, 5, 3, 5 Procedures (1) 6 8 5 5, 6 4, 5 6
3, 4, 5 Operate Control 1, 3, 1, 2, 3, 5, 1, 2, 1, 2, 3, 4, Boards (2) 5, 6, 5, 6 5, 6, 7, 8, 3, 4.
7 9 5, 6, 7 7, 8 Communicate and 2, 3, 1, 2, 1, 3, 1, 2, 2, 3, 1, 2, 3, 5, 2, 3, 4, 5, 3, 5, 5, 6, 4, 5, 3, 4, 7, 8, 4. 5, Interact 7 8, 9 7 5, 6 6 5, 6 9 6, 7 Demonstrate 2, 3, 2, 4, 5, 8, Supervisory Ability 5, 6 9 4, 5, 6, 7 (3)
Comply With and Use 2, 5 2, 4 2, 3 Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U (3) Only applicable to SROs.
- Scenario #2 is the Spare Instructions:
Circle the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
NUREG-1021, Revision 9