ML090790356
| ML090790356 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/06/2009 |
| From: | Brian Larson Operations Branch IV |
| To: | Pacific Gas & Electric Co |
| References | |
| 50-275/09-301, 50-323/09-301, DC-2009-02 50-275/09-301, 50-323/09-301 | |
| Download: ML090790356 (184) | |
Text
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061C-CO1-SRO
Title:
DETERMINATION OF SPENT FUEL POOL HEAT LOAD/REMOVAL PARAMETERS Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
OP B-8DS1, Core Unloading, Attachment 9.3 and 9.4, Rev. 39 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 Minutes Critical Steps: 2, 3, 4, 5 Job Designation: SRO Task Number: G2.1.23 Rating: 4.4 AUTHOR: GARY HUTCHISON DATE: 09/18/2008
JPM TITLE: DETERMINATION OF SFP HEAT LOAD/REMOVAL PARAMETERS JPM NUMBER: NRCADM061C-CO1-SRO INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.
Required Materials: Calculator Initial Conditions: Unit 1 is currently in Mode 6 with fuel offload in progress during 1R15.
Current Plant parameters are as follows:
- Mode 3 was entered 6 days ago at 1500
- Current time is 1500
- 165 fuel assemblies have been offloaded to the spent fuel pool
- CCW flow rate on FI-197 is 3200 gpm
- CCW Heat exchanger outlet temperatures are: TI-181 - 72°F TI-182 - 74°F
- Spent Fuel Pool Pump 1-2 D/P is 38 psid
- Spent Fuel Pool Temperature is 127°F Initiating Cue: Shift Foreman directs you to determine if Spent Fuel Pool Heat Load/Removal parameters are met by performing Attachment 9.3 and 9.4 of OP B-8DS1, Core Unloading.
Task Standard: Attachment 9.3 and 9.4 of OP B-8DS1, Core Unloading, completed and Shift Foreman notified of results.
NRCADM061C-CO1- PAGE 2 OF 7 REV. 0 SRO.DOC
JPM TITLE: DETERMINATION OF SFP HEAT LOAD/REMOVAL PARAMETERS JPM NUMBER:
NRCADM061C-CO1-SRO INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions Operator obtains OP B-8DS1,
- 1. Operator obtains the correct procedure. Attachments 9.3 & 9.4.
1.1 Note: Provide exam copy of OP B-8DS1, Attachments 9.3 & 9.4.
Step was: Sat: _______ Unsat _______*
Operator determines MODE 3 entry
- 2. **Determine Mode 3 Entry, date & date and time and enters on time. Attachment 9.3.**
2.1 Note: Operator should use a date that was 6 days ago and 1500 for the time.
Step was: Sat: _______ Unsat _______*
Operator enters current date and
- 3. **Determines current offload rate. 1500 on Attachment 9.3.**
3.1 3.2 Determines that 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> have elapsed from start of core offload and enters on Attachment 9.3.**
3.3 Determines that number of fuel assemblies offloaded is 165 and enters on Attachment 9.3.**
3.4 Determines that elapsed time and number of assemblies removed is within the acceptable area of chart.
Checks Yes.**
Step was: Sat: _______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-CO1- PAGE 3 OF 7 REV. 0 SRO.DOC
JPM TITLE: DETERMINATION OF SFP HEAT LOAD/REMOVAL PARAMETERS JPM NUMBER:
NRCADM061C-CO1-SRO INSTRUCTOR WORKSHEET Step Expected Operator Actions Operator enters current date and
- 4. **Determines Spent Fuel Pool Cooling 1500 on Attachment 9.4.**
System Status.
4.1 Note: The following steps do not need to be performed in this sequence; however, the SFM should be notified immediately when the SFP temperature is determined to be unacceptable.
4.2 Determines CCW flow rate from FI-197 is 3200 gpm and enters on Attachment 9.4.**
4.3 Determines that CCW flowrate is acceptable.
4.4 Determines that the CCW Heat Exchanger Outlet Temperatures are 72°F on TI-181 and 74°F on TI-182 and enters on Attachment 9.4.**
4.5 Determines that CCW Heat Exchanger Outlet Temperature is acceptable.
4.6 Determines that SFP Pump 1-2 D/P is 38 psid and enters on Attachment 9.4.**
4.7 Determines that SFP Pump 1-2 D/P is acceptable.
4.8 Determines that Spent Fuel Pool Temperature is 127°F.**
4.9 Determines that the Spent Fuel Pool temperature is unacceptable.**
Step was: Sat: _______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-CO1- PAGE 4 OF 7 REV. 0 SRO.DOC
JPM TITLE: DETERMINATION OF SFP HEAT LOAD/REMOVAL PARAMETERS JPM NUMBER:
NRCADM061C-CO1-SRO INSTRUCTOR WORKSHEET Step Expected Operator Actions Notifies Shift Foreman that Spent
- 5. **Notifies Shift Foreman Pool Heat Load/Removal Parameters are not met due to high Spent Fuel 5.1 Pool Temperature.**
Step was: Sat: _______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-CO1- PAGE 5 OF 7 REV. 0 SRO.DOC
EXAMINEE CUE SHEET JPM NUMBER:
NRCADM061C-CO1-SRO Initial Conditions: Unit 1 is currently in Mode 6 with fuel offload in progress during 1R12.
Current Plant parameters are as follows:
- Mode 3 was entered 6 days ago at 1500
- Current time is 1500
- 165 fuel assemblies have been offloaded to the spent fuel pool
- CCW flow rate on FI-197 is 3200 gpm
- CCW Heat exchanger outlet temperatures are: TI-181 - 72°F TI-182 - 74°F
- Spent Fuel Pool Pump 1-2 D/P is 38 psid
- Spent Fuel Pool Temperature is 127°F Initiating Cue: Shift Foreman directs you to determine if Spent Fuel Pool Heat Load/Removal parameters are met by performing Attachment 9.3 and 9.4 of OP B-8DS1, Core Unloading.
Task Standard: Attachment 9.3 and 9.4 of OP B-8DS1, Core Unloading, completed and Shift Foreman notified of results.
NRCADM061C-CO1- PAGE 6 OF 7 REV. 3 SRO.DOC
JPM TITLE: DETERMINATION OF SFP HEAT LOAD/REMOVAL PARAMETERS JPM NUMBER: NRCADM061C-CO1-SRO INSTRUCTOR WORKSHEET : ANSWER KEY ATTACHMENT 9.3 NOTE: Tracking offload rate is not required if 148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br /> have elapsed since MODE 3 entry.
- 1. The Control Operator shall verify every four hours that the rate of core offload does not exceed the ability of the SFP cooling system to dissipate the heat load by ensuring that the offload rate is within the parameters shown on the chart.
- 2. MODE 3 Entry, Date/Time: __6 days ago__/_1500 Current Hours Since Number of Fuel Offload Rate Date/Time Mode 3 Assemblies Acceptable?
Entry Offloaded Yes No Today /1500 144 165 [X] [ ]
________/________ [ ] [ ]
ATTACHMENT 9.4
- 5. Upon completion of core offload, forward Attachment 9.4 Data Sheets to the SFM for inclusion in the Operations Shift Log.
Sheet # Date Time SFP temp FI-197 TI-182 TI-181 SFP pp 1 SFP pp 2
<125°F 3000 - <75°F <75°F p p 1
4040 (VB-1) (VB-1) 53 psid 37 psid gpm AND 55 AND 39 psid psid Today 1500 127 3200 74 72 38 ANSWER KEY NRCADM061C-CO1- PAGE 7 OF 7 REV. 3 SRO.DOC
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
07/16/08 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE: Core Offload Rate OP B-8DS1 ATTACHMENT 9.3 1 2 AND NOTE: Tracking offload rate is not required if 148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br /> have elapsed since MODE 3 entry.
- 1. The Control Operator shall verify every four hours that the rate of core offload does not exceed the ability of the SFP cooling system to dissipate the heat load by ensuring that the offload rate is within the parameters shown on the chart.
- 2. MODE 3 Entry, Date/Time: ________/________
Current Hours Since Number of Fuel Offload Rate Acceptable?
Date/Time Mode 3 Entry Assemblies Offloaded Yes No
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
________/________ [ ] [ ]
rad844CA.Doc 02 0811.1434
Acceptable Number of Offloaded Fuel Assemblies Vs. Time Since Shutdown TITLE:
rad844CA.Doc 200 02 175 07/16/08 Core Offload Rate UNACCEPTABLE 0811.1434 150 125 OP B-8DS1 (UNITS 1 AND 2) 100 Number of Fuel Assemblies Offloaded 75 ATTACHMENT 9.3 50 ACCEPTABLE 25 0
50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 Hours Since Mode 3 Entry Page 2 of 2
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
07/16/08 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:
OP B-8DS1 ATTACHMENT 9.4 Spent Fuel Pool Cooling Parameters During Core Offload 1 2 AND
- 3. Record SFP cooling data every two hours when the core is not fully loaded.
- 4. Notify the SFM immediately if any parameter is approaching the stipulated bounds.
- 5. Upon completion of core offload, forward Attachment 9.4 Data Sheets to the SFM for inclusion in the Operations Shift Log.
Sheet # Date Time SFP temp <125°F FI-197 TI-182 TI-181 SFP pp 1 p SFP pp 2 p 3000 - 4040 gpm <75°F <75°F 53 psid AND 55 psid 37 psid AND 39 psid (VB-1) (VB-1)
[ ] Continued on next sheet rad844CA.Doc 02 0811.1434
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061C-CO2-SRO
Title:
REVIEW OUTAGE SAFETY CHECKLIST Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
AD8.DC55, Outage Safety Scheduling, Rev. 27 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2 Job Designation: SRO Task Number: 2.1.32 Rating: 3.8 AUTHOR: GARY HUTCHISON DATE: 09/18/2008 APPROVED BY: N/A DATE:
TRAINING LEADER APPROVED BY: N/A DATE:
LINE MANAGER REV. 0
JPM TITLE: REVIEW OUTAGE SAFETY CHECKLIST JPM NUMBER:
NRCADM061C-CO2-SRO INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.
Required Materials: o Handouts of Mode 6 RCS Level Greater Than or Equal to 111 Initial Conditions: Unit 1 was in Mode 6 when a loss of off site power occurred. All three diesels started, but a fault on Bus H occurred, leaving that bus deenergized. Power was restored within 5 minutes and the plant was stabilized, with the exception of Bus H. Plant Conditions are as follows:
o MDAFW Pump 1-3 was cleared.
o S/G 1-1 and 1-4 were drained for SG cleaning related work.
o S/G 1-2 and 1-3 are at 35% Narrow Range o CFCUs 1-1 and 1-3 are running The CO has just completed a new Outage Safety Checklist for current plant conditions.
Initiating Cue: The SFM has directed you to review the new Outage Safety Checklist Core Cooling section for compliance to the Outage Safety Plan.
Task Standard: The Outage Safety Checklist Core Cooling Section for current plant conditions is reviewed and SFM informed of your findings.
NRCADM061C-CO2- Page 2 of 4 REV. 0 SRO.DOC
JPM TITLE: REVIEW OUTAGE SAFETY CHECKLIST JPM NUMBER: NRCADM061C-CO2-SRO INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Review current Mode 6 Outage 1.1 Compare conditions in Initial Checklists. Conditions with the current checklist.
Step was: Sat: ______ Unsat _______*
- 2. Reports discrepancies. ** 2.1 Informs SFM of findings.
Step was: Sat: ______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-CO2- Page 3 of 4 REV.0 SRO.DOC
JPM NUMBER: NRCADM061C-CO2-SRO EXAMINEE CUE SHEET Initial Conditions: Unit 1 was in Mode 6 when a loss of off site power occurred. All three diesels started, but a fault on Bus H occurred, leaving that bus deenergized. Power was restored within 5 minutes and the plant was stabilized, with the exception of Bus H. Plant Conditions are as follows:
o MDAFW Pump 1-3 was cleared.
o S/G 1-1 and 1-4 were drained for SG cleaning related work.
o S/G 1-2 and 1-3 are at 35% Narrow Range o CFCUs 1-1 and 1-3 are running The CO has just completed a new Outage Safety Checklist for current plant conditions.
Initiating Cue: The SFM has directed you to review the new Outage Safety Checklist Core Cooling section for compliance to the Outage Safety Plan.
Task Standard: The Outage Safety Checklist Core Cooling Section for current plant conditions is reviewed and SFM informed of your findings.
NRCADM061C-CO2- Page 4 of 4 REV. 0 SRO.DOC
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
69-20401 11/07/07 Page 1 of 6 DIABLO CANYON POWER PLANT AD8.DC55 ATTACHMENT 7.4 TITLE: Unit 1 Outage Safety Checklist - Mode 6 RCS Level Greater Than or Equal to 111' CORE COOLING 2 of the following 1 of the following
{ FCV 495 and/or 496 (2nd ASW source) { 3 of the following
{ CCW Hx 1-1 Cavity level 23'
{ CCW Hx 1-2 Upper internals removed 2 of the following 1 of the following
{ ASW pump 1-1 { RHR 1-1 operable
{ ASW pump 1-2 { RHR 1-2 operable
{ ASW X-tie FCV-601 { 4 of the following 2 of the following RHR 1-1 operable
{ CCW pump 1-1 RHR 1-2 operable
{ CCW pump 1-2 1 of the following
{ CCW pump 1-3 { 2 of the following SI pump is not the boration flow 1 of the following path
{ Reactor head removed 1 of the following
{ 3 of the following { SI pump 1-1 & HL or CL path 2 incore thermocouples { SI pump 1-2 & HL or CL path 1 of the following { 2 of the following Charging pump is not the boration
{ 2 LTOP channels operable flow path
{ 2.07 square in vent path 1 of the following Rx head fully detensioned.
(If decay heat is >5 MW, at least one PZR { CCP 1-1 & its normal or charging inj. flow path safety must also be removed.)
{ CCP 1-2 & its normal or charging inj. flow path
{ Charging pump 1-3 & its normal flow path 1 of the following
{ 2 CFCU's available for high speed with 1650 gpm CCW flow
{ 3 of the following No TEMP CNMT PENS installed Decay heat level < 7.5 Mw 1 CFCU available for high speed with 1650 gpm CCW flow rad9125B.Doc 01B 1206.0839
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061C-EC-SRO
Title:
VERIFY AFD IS WITHIN TECH SPEC LIMITS Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This JPM requires that STP I-1C, Attachments 12.1 be filled out ahead of time. The required data is included in an attachment to this JPM.
References:
STP I-1C, Routine Weekly Checks Required By Licenses, Attachment 12.1, Rev. 87 Volume 9B, Curves and Miscellaneous Data, Figure R23-1F-1, Unit 1 Cycle 15 RAOC Limits, Rev. 236 Technical Specification 3.2.3, Axial Flux Difference (AFD), DCPP Units 1 & 2 COLR for DCPP Unit 1, Cycle 15, Rev. 0 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 Minutes Critical Steps: 2, 5, 7, 8, 9 Job Designation: SRO Task Number: G2.2.42 Rating: 4.6 AUTHOR: GARY HUTCHISON DATE: 09/18/2008 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCADM061C-EC-SRO INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.
Required Materials: Completed copy of STP I-1C, Routine Weekly Checks Required By Licenses, Attachment 12.1 (use instructions on page 7 of this JPM).
Volume 9B, Curves and Miscellaneous Data, Figure R23-1F-1, Unit 1 Cycle 15 RAOC Limits, Rev. 236 Technical Specification 3.2.3, Axial Flux Difference (AFD), DCPP Units 1 & 2 COLR for DCPP Unit 1, Cycle 15, Rev. 0 Initial Conditions: Unit 1 rapidly ramped down power due to a leak on the No. 2 Heater Drain Tank pump. Reactor power is currently stable at approximately 75%.
Current Axial Flux Difference (AFD) readings are as follows:
NI-41C -21.0%
NI-42C -23.0%
NI-43C -23.0%
NI-44C -21.0%
PK03-25, PPPC RX ALARM AXIAL FLUX/ROD POSITION input 1251 activated Indicated Reactor Power based on U1169A05 75.2%
U4300A05 is not available.
PPC MAX is 100.2%
Initiating Cue: Unit 1 BOPCO has just completed STP I-1C, Routine Weekly Checks Required By Licenses, Attachment 12.1, Step 1.
Review the completed STP Data sheet and determine if his assessment is correct and implement any actions needed based on your review.
Task Standard: STP I-1C, Routine Weekly Checks Required By Licenses, Attachment 12.1, Step 1, reviewed for completeness and any actions implemented based on your review.
NRCADM061C-EC- PAGE 2 OF 7 REV. 0 SRO.DOC
JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCADM061C-EC-SRO INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions Obtains STP I-1C, Attachment 12.1.
- 1. Obtain the correct procedure.
Note: Provide completed exam copy of 1.1 STP-I-1C, Attachment 12.1.
Step was: Sat: _______ Unsat _______*
Refers to NOTE 1 of Step 1.a for
2.1 2.2 Calculates U1169A05 value (75.2) /
PPC Max (100.2) x 100.
Note: Provide calculator (if necessary).
2.3 Verifies RTP % to be 75.0%**
Step was: Sat: _______ Unsat _______*
Obtains Figure R23-1F-1 for Unit 1
- 3. Obtain the correct Figure. from Volume 9.
3.1 Note: Provide exam copy of Figure R23-1F-1 (if necessary).
Step was: Sat: _______ Unsat _______*
References R23-1F-1.
- 4. Verify Upper AFD Limit.
4.1 4.2 Determines Upper AFD Limit to be
+17.5%.
4.3 Verifies +17.5% recorded for Upper AFD Limit.
Step was: Sat: _______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-EC- PAGE 3 OF 7 REV. 0 SRO.DOC
JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCADM061C-EC-SRO INSTRUCTOR WORKSHEET Step Expected Operator Actions References R23-1F-1.
- 5. **Verify Lower AFD Limit.
5.2 Determines Lower AFD Limit to be 5.1 -22.0%.
5.3 Determines that -22.0% recorded for Lower AFD Limit. is wrong. **
Step was: Sat: _______ Unsat _______*
Verifies indicated AFD values
- 6. Verify indicated AFD values recorded for each NI.
6.1 Step was: Sat: _______ Unsat _______*
Verifies that AFD is within limits for
- 7. **Verify AFD is within limits. NIs 41C and 44C and Yes boxes 7.1 marked.
7.2 Determines that AFD is outside the limits for NIs 42C and 43C and Yes boxes are incorrectly marked.**
Step was: Sat: _______ Unsat _______*
Determines that BOPCO has
- 8. **Verify that 2 excore channels exceed incorrectly initialed that no more than AFD Limit. one channel is exceeding the AFD 8.1 limit. **
Step was: Sat: _______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-EC- PAGE 4 OF 7 REV. 0 SRO.DOC
JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCADM061C-EC-SRO INSTRUCTOR WORKSHEET Step Expected Operator Actions Refers to Tech Spec 3.2.3.
- 9. **Determine AFD exceeds Tech Spec Limits.
Note: Provide exam copy of TS 3.2.3 (if 9.1 necessary).
9.2 Refers to Unit 1 COLR Figure 2.
Note: Provide exam copy of Unit 1 COLR Figure 2 (if necessary).
(Operator may use Figure R23-1F-1 instead of Unit 1 COLR Figure 2 because these figures provide the same information).
9.3 Determines AFD is not within limits.**
9.4 Determines actions to be either to return AFD within limits or to reduce thermal power to less than 50%
within 30 minutes.**
Step was: Sat: _______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-EC- PAGE 5 OF 7 REV. 0 SRO.DOC
EXAMINEE CUE SHEET JPM NUMBER: NRCADM061C-EC-SRO Initial Conditions: Unit 1 rapidly ramped down power due to a leak on the No. 2 Heater Drain Tank pump. Reactor power is currently stable at approximately 75%.
Current Axial Flux Difference (AFD) readings are as follows:
NI-41C -21.0%
NI-42C -23.0%
NI-43C -23.0%
NI-44C -21.0%
PK03-25, PPPC RX ALARM AXIAL FLUX/ROD POSITION input 1251 activated Indicated Reactor Power based on U1169A05 75.2%
U4300A05 is not available.
PPC MAX is 100.2%
Initiating Cue: Unit 1 BOPCO has just completed STP I-1C, Routine Weekly Checks Required By Licenses, Attachment 12.1, Step 1.
BOPCO has determined that the AFD for two (2) excore channels are not within the AFD limits.
Review the completed STP Data sheet and determine if his assessment is correct and implement any actions needed based on your review.
Task Standard: STP I-1C, Routine Weekly Checks Required By Licenses, Attachment 12.1, Step 1, reviewed for completeness and any actions implemented based on your review.
NRCADM061C-EC- PAGE 6 OF 7 REV. 0 SRO.DOC
JPM TITLE: VERIFY AFD IS WITHIN TECH SPEC LIMITS JPM NUMBER: NRCADM061C-EC-SRO ATTACHMENT 1: SIMULATOR SETUP The Simulator is not needed for the performance of this JPM.
NRCADM061C-EC- PAGE 7 OF 7 REV. 0 SRO.DOC
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
69-20250 05/15/07 Page 1 of 18 DIABLO CANYON POWER PLANT TITLE:
STP I-1C ATTACHMENT 12.1 MODES 1, 2, and 3 Weekly Checklist 1
OPERATING MODE 1 DATE TODAY TIME NOW INSTRUCTIONS: Indicate a step is ACCEPTABLE or performed with your INITIALS. A step is NOT ACCEPTABLE if any part of the check or verification is unacceptable for any reason. When a step is NOT ACCEPTABLE, make a note as to why in the REMARKS for this section and include the tracking document number, which should be the Tech. Spec. Sheet # for all TS or ECG items, then enter the note number in the unacceptable step. Indicate N/A for checks not required.
APPL TECH SPEC A. CHECK / VERIFICATION FROM CONTROL ROOM /
MODE REFERENCE ELECTRICAL ROOMS PERF 1 SR 3.2.3.1 1. AFD Monitor Alarm
- a. When above 50% Rated Thermal Power (RTP) and the AFD Monitor Alarm is OPERABLE, record the pertinent information in the table below. Determine if the AFD for each OPERABLE excore channel is within the AFD limits of Figure R23-1F-1, in Volume 9 of the Plant Manual, and record this in the table below. N/A [ ] GLH NOTE 1: For % RTP, use U4300A05 or U1169A05 x 100. "PPC MAX" is from current PPC MAX STP R-2B1 or STP R-2B2.
NOTE 2: Upper and Lower AFD limits are determined from Figure R23-1F-1 based on the power level recorded in the column labeled % RTP.
RTP Upper Lower Indicated AFD AFD
% AFD AFD Within Limit Limit Limits Yes No NI-41C -21.0 [X ] [ ]
75.0 17.5 -25.0 NI-42C -23.0 [X ] [ ]
NI-43C -23.0 [X ] [ ]
NI-44C -21.0 [X ] [ ]
- b. Verify no more than 1 excore channel exceeding the AFD Limits. N/A [ ] GLH radC7837.Doc 06 05250930
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in the COLR.
NOTE-----------------------------------------------
The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.
APPLICABILITY: MODE 1 with THERMAL POWER 50% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.1 Reduce THERMAL 30 minutes POWER to < 50% RTP.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore 7 days channel.
DIABLO CANYON - UNITS 1 & 2 8S9IDH02.DOA - 8 3.2-8 Unit 1 - Amendment No. 135 R2 Unit 2 - Amendment No. 135
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 0 PAGE 5 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 2.9 Axial Flux Difference (TS 3.2.3) 2.9.1 The Axial Flux Difference (AFD) Limits are provided in Figure 2.
2.10 Boron Concentration (TS 3.9.1)
The refueling boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the more restrictive of the following limits:
2.10.1 A keff of 0.95 or less, with the most reactive control rod assembly completely withdrawn, or 2.10.2 A boron concentration of greater than or equal to 2000 ppm.
2.11 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits 2.11.1 Pressurizer pressure is greater than or equal to 2175 psig.
2.11.2 RCS average temperature is less than or equal to 581.7°F.
NOTE: The DNBR RCS Tavg limit is based on the slightly lower and bounding value associated with Unit 1 in order to have the same surveillance limits for both Unit 1 and Unit 2.
- 3. TABLES 3.1 Table 1, "FQ Margin Decreases in Excess of 2% Per 31 EFPD."
3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 5,000 MWD/MTU as a Function of Core Height."
3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 22,000 MWD/MTU as a Function of Core Height."
- 4. FIGURES 4.1 Figure 1, "Control Bank Insertion Limits Versus Rated Thermal Power."
4.2 Figure 2, "AFD Limits as a Function of Rated Thermal Power."
- 5. RECORDS None
- 6. REFERENCES 6.1 "Diablo Canyon Unit 1 Cycle 15 Final Reload Evaluation, Revision 1,"
May, 2007.
6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994.
rad3DFEE.Doc 04B 0815.0139
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 0 PAGE 12 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 120
(-14,100) (+10,100) 100 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION 80
% Of Rated Thermal Power ACCEPTABLE OPERATION 60
(-30,50) (+25,50) 40 20 0
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference (DELTA I) %
FIGURE 2: AFD Limits as a Function of Rated Thermal Power rad3DFEE.Doc 04B 0815.0139
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061C-EP-SRO
Title:
PERFORM AN OFF-SITE DOSE ASSESSMENT - FHB ACCIDENT Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments: The Simulator is not required for the performance of this JPM.
EP R-2, Attachment 10.1 & 10.2 answer key is included for evaluator use Examinee Data Sheet should be printed in color.
References:
EP R-2, Release of Airborne Radioactive Materials Initial Assessment, Rev. 25 OP AP-22, Spent Fuel Pool, Low Level/High Temp/Hi Rad, Rev. 14A EP G-1, Emergency Classification and Emergency Plan Activation, Rev. 37 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 2, 3, 4, 5, 7 Job Designation: SRO Task Number: G 2.4.41 Rating: 4.6 AUTHOR: GARY HUTCHISON DATE: 09/18/2008 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - FHB JPM NUMBER:
ACCIDENT NRCADM061C-EP-SRO INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: Calculator and copies of Attachments 10.1 and 10.2 of EP R-2.
Examinee Data Sheet EAL Charts Initial Conditions: Unit 1 is is off loading the core. OP AP-22, Spent fuel pool, low level/high temp/hi rad, is in progress on Unit 1 due to high radiation in the Fuel Handling building from a dropped fuel assembly.
FR-12 is OOS.
1 FHB Fan, 1 AUX Bldg Exh fan, and 1 GE/GW fan running Initiating Cue: The Shift Manager directs you to perform a dose assessment and to make a recommendation of the emergency classification based on your dose assessment. The program for R-2 calculations is unavailable.
Task Standard: Dose assessed and a recommendation made for the emergency classification in accordance with plant procedures.
NRCADM061C-EP- PAGE 2 OF 11 REV.0 SRO.DOC
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - FHB JPM NUMBER:
ACCIDENT NRCADM061C-EP-SRO ATTACHMENT 1, SIMULATOR SETUP Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References EP R-2.
Step was: Sat: ______ Unsat _______*
- 2. Determine the plant vent flow 2.1 References Attachment 10.1, rate. page 1, of EP R-2.
2.2 Fills out section 1.
2.3 Requests plant vent flow rate from FR-12 chart recorder.
2.4 Uses alternate method to determine plant vent flow rate.
2.5 Calculates plant vent flow rate of 134,250 cfm. **
Step was: Sat: ______ Unsat _______*
NRCADM061C-EP- PAGE 3 OF 11 REV.0 SRO.DOC
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - FHB JPM NUMBER:
ACCIDENT NRCADM061C-EP-SRO ATTACHMENT 1, SIMULATOR SETUP Step Expected Operator Actions
- 3. Determine the Noble Gas 3.1 Determines RE-14/87 reading from the Release Rate radiation monitors of 3.27E-02 uci/cc.
3.2 Calculates Noble Gas release rate to be 2.07 Ci/sec +/-0.1**
Step was: Sat: ______ Unsat _______*
- 4. Determine the total effluent 4.1 Determines Total Effluent Coversation release rate. Factor to be 1.11 (GAP).**
4.2 Calculates total effluent release rate to be 2.3 Ci/sec +/-0.1.**
Step was: Sat: ______ Unsat _______*
- 5. Perform dose calculations. 5.1 References Attachment 10.2 of EP R-2.
5.2 Determines wind speed at 10M level of 11 m/sec.
5.3 Determines wind direction at 10M level of 290 degrees.
5.4 Determines Site Boundary X/Q at 0.8km of 5.1E-06 Sec/m3.
5.5 Determines DCF for TEDE to be 3.0 E+6 (GAP).**
5.6 Calculates TEDE rate of 35.2 mrem/hr
+/-1.5 and a total dose **
(Continue Step on next page.)
NRCADM061C-EP- PAGE 4 OF 11 REV.0 SRO.DOC
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - FHB JPM NUMBER:
ACCIDENT NRCADM061C-EP-SRO ATTACHMENT 1, SIMULATOR SETUP Step Expected Operator Actions Cue: If asked, tell examinee to use DEFAULT release information.
5.7 Calculates TEDE dose of 105.6 mrem
+/-4.6.**
5.8 Determines DCF for CDE to be 6.5 E+7 (GAP)**
5.9 Calculates Thyroid CDE rate of 762.5 mrem/hr +/-33.2**
5.10 Calculates Thyroid CDE dose to be 2287.4 mrem +9.5 Step was: Sat: ______ Unsat _______*
- 6. Obtain the correct procedure. 6.1 References EP G-1, Attachment 7.1 Step was: Sat: ______ Unsat _______*
7.2 Reports recommendation to the Shift Manager.
Step was: Sat: ______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
NRCADM061C-EP- PAGE 5 OF 11 REV.0 SRO.DOC
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - FHB JPM NUMBER:
ACCIDENT NRCADM061C-EP-SRO ATTACHMENT 1, SIMULATOR SETUP Initial Conditions: Unit 1 is is off loading the core. OP AP-22, Spent fuel pool, low level/high temp/hi rad, is in progress on Unit 1 due to high radiation in the Fuel Handling building from a dropped fuel assembly.
FR-12 is OOS.
1 FHB Fan, 1 AUX Bldg Exh fan, and 1 GE/GW fan running Initiating Cue: The Shift Manager directs you to perform a dose assessment and to make a recommendation of the emergency classification based on your dose assessment. The program for R-2 calculations is unavailable.
Task Standard: Dose assessed and a recommendation made for the emergency classification in accordance with plant procedures.
Classification NRCADM061C-EP- PAGE 6 OF 11 REV.0 SRO.DOC
04/21/08 Page 1 of 3 DIABLO CANYON POWER PLANT EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.1 TITLE: Release Rate Calculations PLANT VENT RELEASE
- 1. GENERAL INFORMATION Date: Today Time: Now Assessment No. 1 Assessment By: Name of Examinee Unit Releasing 1
- 2. PLANT VENT FLOW RATE DETERMINATION A. DIRECT - Plant Vent Flow Rate FR-12 (0-30x104 CFM (CFM) = OOS (CFM)
OR B. ALTERNATE - Operating Ventilation Equipment (Max No. possible) #Fans (CFM/Fan)
FHB Exhaust (1) 1 x 35,750 = 35.750 (CFM)
Aux Bldg Exhaust (2) 1 x 73,500 = 73,500 (CFM)
GE/GW Area (1) 1 x 25,000 = 25,000 (CFM)
Cont. Purge (1) x 55,000 = (CFM)
Cont. Hydrogen (1) x 300 = (CFM)
Plant Vent Flow Rate = 134,250 (CFM)
- 3. RELEASE RATE CALCULATION CAUTION: Do NOT use SPDS to obtain monitor readings.
A. NOBLE GAS RELEASE RATE Circle Reading (Units) Conversion Plant Vent Noble Gas Monitor Factor Flow Rate Release Used (CFM) Rate (Ci/sec)
Primary RE-14/14R/87 3.27 E-2 Ci/cc x 4.72E-04 x 134,250 Backup RE-29 mR/hr x 4.72E-06 x = 2.07 B. TOTAL EFFLUENT RELEASE RATE NOTE: Refer to Page 3 for criteria in choosing RCS, GAP, or CORE below.
Noble Gas Release Total Effluent Total Effluent Rate (Ci/sec) Conversion Factor Release Rate (Ci/sec) 2.07 x 1.00 (RCS) = 2.3 1.11 (GAP) 1.50 (CORE)
NOTE: If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3 of this attachment.
GO TO ATTACHMENT 10.2 NRCADM061C-EP- PAGE 7 OF 11 REV. 0 SRO.DOC
04/21/08 Page 2 of 3 DIABLO CANYON POWER PLANT EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.1 TITLE: Release Rate Calculations
- 1. GENERAL INFORMATION ATMOSPHERIC STEAM RELEASE Date: Time: Assessment No.
Assessment By: Unit Releasing CAUTION: WHEN CRITICAL, N-16 ACTIVITY SEEN BY MSL RAD MONITORS CAUSES INVALID READINGS FOR OFFSITE DOSE. POST-TRIP, RE-7X READING IS VALID IF THE RE-7X MONITOR SHOWED AN INITIAL N-16 RESPONSE, OR RESPONDS TO CHECKSOURCE.
NOTE: If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3.
- 2. STEAM RELEASES - Use this form to calculate steam releases to the atmosphere WHEN NOT critical.
A. Required Information (RUPTURED GENERATOR ONLY)
Check MSL Rad Reading S/G Lvl Level S/G Flow Flow Rate Ruptured S/G Monitor (cpm) Narrow (%) Rate (lbs/hr)
Range If <4E5 use 4E5 SG 1 RE-71 LI-517 FI-512 SG 2 RE-72 LI-527 FI-522 SG 3 RE-73 LI-537 FI-532 SG 4 RE-74 LI-547 FI-542 B. Alternate Steam Flow Rate (Only if the RUPTURED S/G Flow Rate is otherwise not available)
Valve Type # Valves Capacity (lbs/hr) Flow Rate (lbs/hr)
Lifted 10% Steam Dump (1 per S/G) x 4.0E+05 =
Safety Reliefs (5 per S/G) x 8.5E+05 =
Total Steam Flow Rate (lbs/hr) (lbs/hr)
- 3. RADIATION MONITOR FACTORS (Determined based on S/G NR Level indication) (Enter in Section 4 below.)
S/G Level EMPTY NORMAL FLOODED Narrow Range < 4% 4% - 96% > 96%
Monitor Factor 6.08E-10 6.75E-10 3.07E-10 (DEFAULT)
- 4. RELEASE RATE CALCULATIONS A. TOTAL EFFLUENT RELEASE RATE (RE-7x)
MSL Monitor Reading Flow Rate Monitor Factor Total Effluent Release (cpm) (lbs/hr) Rate (Ci/sec) x x GO TO ATTACHMENT 10.2 NRCADM061C-EP- PAGE 8 OF 11 REV. 0 SRO.DOC
04/21/08 Page 3 of 3 DIABLO CANYON POWER PLANT EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.1 TITLE: Release Rate Calculations
- 1. SOURCE TERM SELECTION AND DEFAULT RELEASE RATES NOTE: Use default release rate only if actual data is not available or if the release is not being monitored.
A. Check the accident type which most closely resembles the current event.
Default Release Source Rate (Ci/sec) Term Accident Source Condition LOCA (w/ core melt) 1.74 E+1 RE-30 or 31 >300R/hr CORE LOCA (w/o core melt) 5.74 E+0 RE-30 or RE-31 <300R/hr GAP RE-30 or RE-31 not on scale RCS Main Steam Line Break 8.61 E-3 RCS Feedwater Line Break 8.61 E-3 RCS Blackout 8.62 E-1 RCS Locked Rotor 1.57 E-2 GAP X FHB Accident 1.45 E+1 GAP Rod Ejection 1.08 E-2 GAP GDT Rupture 4.14 E+1 RCS LHUT Rupture 3.10 E+1 RCS VCT Rupture 8.29 E-2 RCS S/G Tube Rupture 1.65 E+0 NR S/G Level < 4% SG - Empty NR S/G Level 4-96% SG- Normal NR S/G Level > 96% SG - Flooded Containment FHA S.B. Dose TEDE = 13.4 mrem/hr Go Accident with Equip. Rates Thy.CDE = 51.4 mrem/hr Directly to Hatch Open S.B. Doses TEDE = 6.7 mrem EP G-1 Thy. CDE = 25.7 mrem B. Record the Default Release Rate in Attachment 10.2, Section 4 and use the DCF choice that is listed for the specific accident source above.
GO TO ATTACHMENT 10.2 NRCADM061C-EP- PAGE 9 OF 11 REV. 0 SRO.DOC
08/05/94 Page 1 of 1 DIABLO CANYON POWER PLANT EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.2 TITLE: Off-Site Dose Calculations
- 1. GENERAL INFORMATION Date: Today Time: Now Assessment No. 1 Assessment By: Name of Examinee Unit Releasing 1
- 2. METEOROLOGICAL DATA - PPC (Plant Process Computer)
Turn On Codes for Met Data are "METP" (Primary Data) or "METB" (Back-up Data)
Parameter Reading Units DEFAULT Wind Speed (10 Meter Level) 11 meters/sec Wind Direction (10 Meter Level) 290 Degrees Site Boundary X/Q (0.8 km) 0.51 E-5 Sec/m3 5.29E-04
- 3. DCF Determination - Select the most appropriate source term for the DCF using the criteria in Attachment 10.1. Circle the corresponding DCF in Section 4 below.
- 4. DOSE CALCULATIONS - (From data calculated using Attachment 10.1)
A. TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)
Total Effluent or Site Projected TEDE Default Release Boundary DCF TEDE Release (mrem)
Rate X/Q (0.8 km) (circle one) Rate Duration (hr) 3 (Ci/sec) (Sec/m ) (mrem/hr (DEFAULT 3 hrs)
)
1.1E + 05 (RCS) 3.0E + 06 (Gap )
2.3 x 0.51 E-5 x 1.1E + 07 (Core) = 35.2 x 3 = 105.6 Attachment 10.1 1.1E + 05 (SG-Empty) 4.3E + 04 (SG-Normal )
9.3E + 05 (SG-Flooded)
B. THYROID COMMITTED DOSE EQUIVALENT (CDE) (DO NOT COMPLETE FOR GDT, LHUT, OR VCT RUPTURE)
Total Effluent or Site Projected Default Release Boundary DCF Thyroid Release Thyroid Rate X/Q (circle one) CDE Duration (hr) CDE (Ci/sec) (0.8 km) Rate (DEFAULT 3 hrs) (mrem)
(Sec/m3) (mrem/hr) 1.5E + 06 (RCS) 6.5E + 07 (Gap )
2.3 0.51 E-5 x 7.7E + 07 (Core) = 762.5 x 3 = 2287.4 Attachment 10.1 1.5E + 06 (SG-Empty) 1.5E + 05 (SG-Normal )
1.4E + 07 (SG-Flooded)
- 5. REPORTING THE RESULTS - (Refer to Section 7.3 of Instructions for details)
A. Refer to EP G-1 for EAL criteria.
B. Implement EP RB-10 for PAR criteria NRCADM061C-EP- PAGE 10 OF 11 REV. 0 SRO.DOC
JPM NUMBER:
NRCADM061C-EP-SRO EXAMINEE DATA SHEET NRCADM061C-EP- PAGE 11 OF 11 REV. 0 SRO.DOC
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061C-RC-SRO
Title:
Review Liquid Radwaste Discharge Checklist.
Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for SRO Candidates in a classroom setting.
References:
OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 35A CAP A-5, Liquid Radwaste Discharge Management, Rev. 41A Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 4 Job Designation: SRO K/A: G 2.3.6; Ability to approve release permits.
Rating: 3.8 AUTHOR: GARY HUTCHISON DATE: 08/12/2008 REV. 0
JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-RC-DISCHARGE CHECKLIST SRO INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.
Required Materials: OP G-1:II, Liquid Radwaste System - Discharge of Liquid Radwaste, Rev. 35A Completed Attachments 9.1 & 9.5 CAP A-5 Completed Attachment 11.1 Parts 1 & 2.
Initial Conditions: A discharge permit has been issued for PWR 0-1. OP G-1:II Attachments 9.1 & 9.5 have been completed.
Initiating Cue: As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.
Task Standard: DO NOT READ TO STUDENTS: 2 Technical errors are identified and discharge authorization is not approved. This will be documented on the student handout.
NRCADM061C-RC- Page 2 of 6 REV. 0 SRO.DOC
JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-RC-DISCHARGE CHECKLIST SRO INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Review checks on page 1 of 1.1 Determines Batch number matches CAP Attachment 9.1. A-5 Att. 11.1 number.
1.2 Identifies that Valve alignment is complete.
1.3 Identifies that independent verification of Valve alignment is complete.
1.4 Identifies that dilution flowrate is adequate.
1.5 Identifies that RE-18 setpoint doesnt require adjustment.
Step was: Sat: ______ Unsat _______*
Step was: Sat: ______ Unsat _______*
Step was: Sat: ______ Unsat _______*
- 4. Determine if Authorization 4.1 Determines that the Authorization should be approved. should not be approved, based on either condition not meeting the procedural requirements.
Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-RC- Page 3 of 6 REV. 0 SRO.DOC
JPM TITLE: REVIEW LIQUID RADWASTE JPM NUMBER: NRCADM061C-RC-DISCHARGE CHECKLIST SRO INSTRUCTOR WORKSHEET Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCADM061C-RC- Page 4 of 6 REV. 0 SRO.DOC
JPM NUMBER: NRCADM061C-RC-SRO EXAMINEE CUE SHEET Initial Conditions: A discharge permit has been issued for PWR 0-1. OP G-1:II Attachments 9.1 & 9.5 have been completed.
Initiating Cue: As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.
Technical Errors Identified:
[ ] APPROVE Discharge [ ] DO NOT Approve Discharge NRCADM061C-RC- Page 5 of 6 REV. 0 SRO.DOC
REVIEW LIQUID RADWASTE DISCHARGE CHECKLIST JPM NUMBER: NRCADM061C-RC-SRO ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.
NRCADM061C-RC- Page 6 of 6 REV. 0 SRO.DOC
JPM TITLE: AUTHORIZE GAS DECAY TANK JPM NUMBER: NRCADM061-RC-SRO DISCHARGE ANSWER KEY Initial Conditions: A discharge permit has been issued for PWR 0-1. OP G-1:II Attachments 9.1 & 9.5 have been completed.
Initiating Cue: As the Unit 1 Shift Foreman, review OP G-1:II Attachments 9.1 & 9.5 Discharge Checklists for accuracy and completeness. Document any discrepancies noted and determine if the discharge checklist should be approved or not approved based on your review.
Technical Errors Identified: .1 page 2, CCW HX 1-2 is circled to be used for the release, but SW-1-67 is opened when SW-1-68 should be opened. .5 has PWR 0-2 aligned when PWR 0-1 should be.
[ ] APPROVE Discharge [ X ] DO NOT Approve Discharge NRCADM061C-RC- Page 7 of 6 REV. 0 SRO.DOC
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
07/08/08 Page 1 of 2 DIABLO CANYON POWER PLANT OP G-l:11 ATTACHMENT 9.1 TITLE: Liauid Radwaste Discharge Checklist The following checklist shall be performed prior to any overboard discharge from the Floor Drain Receivers, Processed Waste Receivers, Laundry/Distillate Tanks, Laundry and Hot Shower Tanks, or the Chemical Drain Tanks or the Demin Regen Receivers.
Equipment ri;ain Receivers will normally be processed through the in-plant waste process stream, Le., Media Filters and/or Radwaste Ion Exchangers to ultimately end up back in a Processed Waste Receiver (PWR) to be discharged.
Usual operation will be as follows:
- 1. CDTs, LHSTs, L/DTs and PWRs will be normally discharged through RW filters 0-3 and 0-4 to overboard.
- 2. EDRs will normally be processed per OP G-l:IV through the Media Filters, Ion Exchangers, Filter 0-5 and on to the Processed Waste Receivers (PWRs).
- 3. FDRs will usually be discharged through RW filter 0-1 with the exception of during outages when they may be processed due to the presence of colloidal cobalt.
- 4. DRRs will usually be discharged unless colloidal cobalt is present and processing is required.
In all cases, chemistry will determine the proper method oftreatrnent and disposal of the waste water.
The Discharge Checklist required for discharge should be completed in accordance with OP1.DCI0, "Conduct of Operations." The checklist shall be reviewed by the SFM and be attached to the Liquid Discharge Authorization.
NO DISCHARGE SHALL BE INITIATED UNTIL THIS CHECKLIST HAS BEEN COMPLETED AND REVIEWED.
Liquid Waste Batch No:2.06 ~- 0 - .;;3G YES NO Valve alignment for tank to be discharged complete [~ [ ]
Independent verification of valve alignment complete [vi [ ]
Dilution flowrate adequate per discharge authorization requirements [,/ [ ]
Does RE-18 setpoint require adjustment? [] [~
(Refer to discharge permit section 2)
If yes, contact the chemistry foreman to verify they have requested a setpoint change ofRE-18 per CAP A-5.
rad765F7.Doc 02 0715.0725
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
07/08/08 Page 2 of 2 OP G-1 :11(UNITS 1 AND 2)
ATTACHMENT 9.1 TITLE: Liauid Radwaste Dischanze Checklist VERIFICATION FORALLTANKSTOBEDISCHARGED InServiceCCWHXto beusedfor LiquidRadwasteDischarge:
(circleone) 1-1 If.2\ 2.1 2-2
~------------------------------------------------------------------------------_.
MANUALVALVELINEUPVERIFICATION VALVE REQUIRED POSITION VALVEPOS. INIT VERIFINIT LWS-0-436 Openif 1-1or 1-2CCW FLTR DISCHTO hxeralignedfor discharge Dee-A K-UNIT1 OVERBOARD Otherwiseclosed LWS.O-439 Openif 2.1or 2.2 CCW FLTR DISCHTO hxeralignedfor discharge. c...tI,.-
UNIT2 OVERBOARD Otherwiseclosed '\f0--
SW-1-67 Openif 1-1CCWhxer FLTRDISCHTO 1-1 alignedfor discharge.
ASW OVERBOARD Otherwiseclosed Dee r-.
SW-1-68 Openif 1-2CCWhxer FLTRDISCHTO1.2 alignedfor discharge. GL q ..,.....
ASWOVERBOARD Otherwise closed SW.2-67 Openif 2.1CCWhxer FLTR DISCHTO 2-1 " .
alignedfor discharge. CL- \:
ASWOVERBOARD Otherwiseclosed SW-2-68 Openif 2-2CCWhxer FLTR DISCHTO 2-2 alignedfor discharge. c.l-ASW OVERBOARD Otherwiseclosed SealedValveChecklistOPK-1OLComplete CCWHxerAlignedfor Discharge Verifiedto beInServicebyChecking HxerDIP(VB-1) (L ChecklistPerformed By ChecklistVerifiedBy ~~~ ignat~
(Signature)
(Staplethis checklistto thedischargepermit) ~
Init Liquidradwastedischargechecklistcompleteand satisfactory (SFMSignature) (Date/Time)
Comments rad765F7.Doc 02 0715.0725
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
01/13/98 Page 1 of 1 DIABLO CANYON POWER PLANT OPG-l:II ATTACHMENT 9.5 1 2AND TITLE: PWR 0-1and 0-2DischanzeChecklist TANK TO BEDISCHARGED BATCHNO. BATCH NO.2.00 'g C 36 PROCESSEDWASTERECEIVER 0-1 PROCESSED WASTERECEIVER 0-2 VALVE - REO.POS. INIT VERIF VALVE REO.POS. INIT VERIF INIT INIT LWS-0-FCV-722 LWS.O.FCV.
722 PWRRECIRC CLOSED PWRRECIRC CLOSED LWS-O-FCV-443 LWS.O.FCV
-443 SPENTRESIN CLOSED SPENTRESIN CLOSED SLUICE SUPPLY SLUICESUPPLY FROMPWRs FROMPWRS Pr/-
LWS-0-FCV-446 LWS-0-FCV-446 PWRTO WASTE OPEN PWRTOWASTE OPEN FILTERS FILTERS LWS-O-FCV -473 LWS-0-FCV-473 COTPUMPDISCH CLOSED COTPUMPDISCH CLOSED TO WASTEFLTRS TO WASTEFLTRS -?-1\l-LWS-O-FCV-475 LWS-0-FCV-475 LAUNPUMPDISCH CLOSED LAUNPUMPDISCH CLOSED TO WASTEFLTRS TO WASTEFLTRS (A\YL LWS-0-FCV-477 LWS-0-FCV-477 WASTEFLTRS CLOSED WASTEFLTRS DISCH CLOSED DISCH TO EDRs TOEDRs LWS-0-RCV-18 LWS.0.RCV-18 UOWASTETO OPEN UOWASTETO OPEN OVERBOARD OVERBOARD \YL.
LWS-0-935 LWS-0-936 PWR CLOSED PWR CLOSED PP 0-1 EDUC ISOL PP0-2EDUCISOL LWS-0-934 LWS-0-937 PWR OPEN PWR OPEN PP0-1DISCH PP0-2DISCH cb- i (SECOND OFF) (SECONDOFF)
{z:.\
LWS.0.936
- LWS-0-1 065 **
LWS-0-1065 LAUN/DISTL TANKS CLOSED LAUN/DISTLTANKS CLOSED TO RWFILTERS TO RWFILTERS kt>-
REMARKS:
- ManualValve
- Manualvalvelocatedin LlDTRoom radFB056.Doc 02 0715.0725
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
69-20877 04/29/05 Page 1 of 2 DIABLO CANYON POWER PLANT CAP A-5 ATTACHMENT 11.1 TITLE:
Parts1 and2 of this formmustbecompleted priorto releaseof theliquidradwastebatch.
Part3 mustbecompleted bytheShift Foreman supervising therelease.Returnthecompleted formto Chemistry.
- 1. SAMPLt9NFORMA TIONANDANALYSIS Batch No. 2..DO~ a 3b
- a. TankNumber andName f' 0 ~ 0 -I
- b. Tank Level '\-'\ .., 0 Volume: 74-" 0 gal
- c. Treated by: r ~\ ~ r-r..-A ,'.::1 ,...,
- d. Recirculation Flowrate ~ 0 gpm
- e. Date/Time Started: '""\ 0 de.- U\.. / 02.0 0
- 1. Date/Time SampleCollected:First ~ J.", / 0 <\-0 <::) Second n I 0-
- g. Didthetankrecirculatefor at leastdoublethe meof thetankcontentsORat least1.5hoursof recirculation for EDRT.FORT,DRRandpossiblyPWR.YES! NO! I Inthecaseof a PWRwhichrecircoptionwasused? X Eductor(1.5hr) Normal(8 hr)
- h. Sample pH G. \
- i. Activity TotalConcentration 2 .~ '2..e...- 0 \ flCi/ml ECLI. \3 e .\r 0 \ flCi/ml Second Sample 1'\0-.. flCi/ml ECL (\0.. flCi/ml TotalActivity ~ ,2~ e. ~ 0 r; flCi TotalConcentration Z. '2,.Gte. .. C~ flCi/ml (excluding Tritium)
- j. Prerelease CalculatedDoses Remaining Allowable,mrem Quarterly Annually TotalBody ~ "L.?e.- oS
\ mrem I. ~O e. .;-00 3.00 e.. ~"o
- 2. RELEASE MaximumOrgan Basis:Batchflowrate AUTHORIZATION
\ . b ~ e.- 0 4,-
(CHEM)
, 0 mrem gpm 5.00 e.. -\- DO circflowrate q . 4:-9 e + c S
\ . 00 e~
gpm 0 \
- a. IFORINOPERABLE RE.18 Date/TimeCAUTION TAGattachedto FCV.647KeySwitch () I Date/Time14.dayperiodexpires " /4 SECOND SAMPLE COLLECTION ANDANALYSIS INDEPENDENT RELEASE RATECALCULATION VERIFIED BY: ('\ ~ VERIFIED BY:
- b. Thisbatchisapproved fordischarge atthestatedrateof release.
Actual(existing)RE.18HASP(AdminLimit)settingis ~0 00 0 cpm.
Expected RE-18readingabovebackground is 2..'\ S cpm.
NotifytheShiftChemistry Techin accordance with OPG.1:11.OP1.DC2 applies.
- c. Limitingbatch flowrate ~0 gpm d. Minimumdilutionwaterflowrate &.4:C\, e.1-05 gpm
- e. Signed Date/Time -rod a. \1\ / 0 Sb 0 ChemistrySupervision or Authorized Personnel radOC009.Doc 08 0411.1539
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
69-20877 04/29/05 Page 2 of 2 CAP A-5 (UNITS 1 AND 2)
ATTACHMENT 11.1 TITLE: Authorization for Discharge of Liauid Radwaste Batch BatchNo.
- 3. RELEASE INFORMATION ANDAPPROVAL
- a. RE-18InstrumentCheck Calibration ExpirationDate _
Sourcecheckreading _ cpm (If inoperable,referto OPG-l:11.)
Operable [ ] Inoperable [ ]
FW-20:Operable [ ] Inoperable [ ] (If inoperable, referto OPG-l:11.)
- b. Thefollowingrequirements mustbemetpriorto therelease:
- 1) Neverdischarge viacartridgefilter 0-2unlessauthorized byseniorchemistryengineer.
- 2) Flush %of tankcontentsbackto anEDR/DRR perOPG-l:11.
- c. Signed / Approved /
Operator Date/Time ShiftForeman Date/Time CAUTION:If thetanklevelis differentby> 1%priorto flushfromthetanklevelstatedpreviouslyinSectionl.b., THENTHIS PERMITISINVALID.
Discharge Adequate StartTime Adequate StartTime Adequate StartTime Adequate StartTime Dilution? +3 hours Dilution? +6 hours Dilution? +9 hours Dilution?
[]Yes []No []Yes []No [ ]Yes [ ] No [ ] Yes [ ] No If atanytimedurin!! dischar!!e dilutionflowrateisNOTadeQuate, immediatelvreferto OPG-l:11 Flowintegratorreadingat endof discharge (assumes setto 0 at start of discharge) Date/Time Totaltimedischarge is interrupted(e.g.,filter change out) Min.
Actualdischarge time(beginning - end- interruptions) Min.
- e. Performa channelcheckonliquidradwasteflow recorderFR-20.Date/Time Verifyflow is recording duringthereleaseperiod.
- f. Avg.FlowrateindicatedbyFR-20 gpm
- g. TankLevelpriorto flush %
Tanklevelpriorto discharge % gal Tanklevelafterdischarge % gal VolumeDischarged gal
- h. Performed By /
Operator(signature) Date/Time
- i. Comments
- j. Reviewed: / Noted ShiftForeman Date/Time ChemistrySupervision Date radOC009.Doc 08 0411.1539
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061C-S1
Title:
ISOLATE A RUPTURED VCT Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
OP AP-14, Tank Ruptures, Rev. 13 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2, 4, 5, 6, 9, 13 Job Designation: RO/SRO Task Number: 02/004/A2.04 Rating: 3.7/4.1 AUTHOR: GARY HUTCHISON DATE: 09/18/2008 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: ISOLATE A RUPTURED VCT JPM NUMBER: NRC061C-S1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: None Initial Conditions: Unit 1 is in MODE 1 at 100% power. RCP seal return is aligned to the top of the VCT. VCT auto makeup has initiated and level is still dropping.
Initiating Cue: It has been determined that the VCT is ruptured. The Shift Foreman directs you to isolate the VCT in accordance with step 8 of OP AP-14.
Task Standard: The VCT is isolated in accordance with step 8 of OP AP-14.
NRC061CLJC-S1.DOC PAGE 2 OF 7 REV.0
JPM NUMBER: NRC061C-S1 EXAMINEE CUE SHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References OP AP-14.
Step was: Sat: ______ Unsat _______*
- 2. Place LCV-112A control switch in 2.1 Places LCV-112A in DIVERT. **
the DIVERT position.
2.2 Verifies LCV-112A is in DIVERT.
Step was: Sat: ______ Unsat _______*
- 3. Verify charging pump suction is 3.1 Verifies 8805A and B are open.
aligned to the RWST.
3.2 Verifies LCV-112B and C are closed.
Note: Charging pump suction may have automatically aligned to the RWST prior to operator actions.
Step was: Sat: ______ Unsat _______*
- 4. Terminate VCT makeup. 4.1 May press STOP on makeup controller to terminate AUTO makeup 4.2 Presses OFF on the makeup controller. **
Step was: Sat: ______ Unsat _______*
NRC061CLJC-S1.DOC PAGE 3 OF 7 REV.0
JPM NUMBER: NRC061C-S1 EXAMINEE CUE SHEET Step Expected Operator Actions
- 5. Verify RCP seal return aligned to 5.1 May contact the auxiliary building charging pump suction. watch to check the line-up.
Cue: Seal return is aligned to the top of the VCT.
5.2 Closes 8100 and/or 8112. **
Step was: Sat: ______ Unsat _______*
- 6. Isolate Letdown 6.1 Closes 8149C. **
6.2 Closes LCV-459 and LCV-460. **
Step was: Sat: ______ Unsat _______*
- 7. Reduce charging to minimum. 7.1 Closes HCV-142 and throttles FCV-128 controller to obtain 8 gpm RCP seal injection flow.
Step was: Sat: ______ Unsat _______*
isolation CVCS-8101.
Step was: Sat: ______ Unsat _______*
NRC061CLJC-S1.DOC PAGE 4 OF 7 REV.0
JPM NUMBER: NRC061C-S1 EXAMINEE CUE SHEET Step Expected Operator Actions
- 9. Verify closed pressurizer liquid 9.1 Verifies 9355A and B are closed. **
and steam sample lines, 9355A and B, 9354A and B.
9.2 Verifies 9354A and B are closed.
Step was: Sat: ______ Unsat _______*
- 10. Place excess letdown in service. 10.1 Refers to OP B-1A:IV Cue: Another operator will complete the actions of step 8.
Step was: Sat: ______ Unsat _______*
Step Expected Operator Actions Stop Time:
Total Time: (Enter total time on the cover page)
NRC061CLJC-S1.DOC PAGE 5 OF 7 REV.0
JPM NUMBER: NRC061C-S1 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is in MODE 1 at 100% power. RCP seal return is aligned to the top of the VCT. VCT auto makeup has initiated and level is still dropping.
Initiating Cue: It has been determined that the VCT is ruptured. The Shift Foreman directs you to isolate the VCT in accordance with step 8 of OP AP-14.
Task Standard: The VCT is isolated in accordance with step 8 of OP AP-14.
NRC061CLJC-S1.DOC PAGE 6 OF 7 REV.0
JPM TITLE: ISOLATE A RUPTURED VCT JPM NUMBER: NRC061C-S1 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
Enter drill file xxxx or manually insert the following:
Command Description
- 1. loa cvc10 act,1,0,0,d,0 Opens 8373, seal return to top of VCT
- 2. loa cvc9 act,0,0,0,d,0 Closes 8375, seal return to ccp suction
- 3. ramp acvcvctw 6500,60,0,d,0 Lowers VCT level
- 4. mal cvc 4A act,30,0.1,0,d,0 VCT rupture at bottom of tank
- 5. run 60 Runs the simulator for 60 seconds Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRC061CLJC-S1.DOC PAGE 7 OF 7 REV.0
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJC-S2
Title:
RESPOND TO PRESSURE CONTROL CHANNEL PT-456 FAILED HIGH Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
OP AP-5, Malfunction of Protection or Control Channel, Rev. 28B Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2, 4 Job Designation: RO/SRO Task Number: 03/010/A3.02 Rating: 3.6/3.5 AUTHOR: GARY HUTCHISON DATE: 08/14/08 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: RESPOND TO PRESSURE CONTROL CHANNEL PT- JPM NUMBER:
456 FAILED HIGH NRC061CLJC-S2 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: None Initial Conditions: Unit 1 has been operating at 100% power with all systems aligned for normal full power operation.
Within the last minute,
- several annunciators alarmed,
- PZR PORV PCV-456 cycling open and close
- PZR backup heaters automatically energized.
Initiating Cue: The Shift Foreman directs you to respond to the transient using OP AP-5 Malfunction of Eagle 21 Protection or Control Channel.
Task Standard: Procedural actions have been completed so that normal automatic pressurizer pressure control may be restored.
NRC061CLJC-S2.DOC PAGE 2 OF 6 REV. 0
JPM TITLE: RESPOND TO PRESSURE CONTROL CHANNEL PT- JPM NUMBER:
456 FAILED HIGH NRC061CLJC-S2 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure 1.1 References OP AP-5.
Step was: Sat: ______ Unsat _______*
- 2. Verify control systems properly 2.1 Determines that the PZR pressure controlling in AUTO. control system is NOT working in AUTO. (Controller demand is acceptable for current plant pressure, pressurizer heaters, and spray valves controlling in AUTO but PCV 456 still has an OPEN signal from PT 456.)
2.2 After one or more cycles of PCV-456, the operator places PCV-456 control switch in CLOSE. (This may be done at anytime but must be completed before the end of the task.) **
Note: Operator may take manual control of the PZR PRESS CONTROL HC-455K. However it will not stop PCV-456 cyclic response.
Step was: Sat: ______ Unsat _______**
- 3. Determine extent of instrument 3.1 Observes that PK06-01 and PK06-03 failure. are OFF.
Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRC061CLJC-S2.DOC PAGE 3 OF 6 REV. 0
JPM TITLE: RESPOND TO PRESSURE CONTROL CHANNEL PT- JPM NUMBER:
456 FAILED HIGH NRC061CLJC-S2 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Verify affected Instrument(s) 4.1 Determines PT-456 is the Instrument Channel Outputs are NOT Inputs to PZR pressure.
selected for Control or Backup, 4.2 Verifies Affected Instrument Channel as required. (PT-456) Outputs are not selected for control.
4.3 Positions the P/455A CONTROL PRESS / RELIEF VLVS switch to PT 455 / PT 474. **
Note: Operator may take HC-455K to manual to shift control channels Step was: Sat: ______ Unsat _______*
- 5. Verify Failed Channel NOT 5.1 Determines that PT-456 is NOT Selected as Recorder Input. selected as recorder input.
Cue: Other operators will complete OP AP-5.
Step was: Sat or N/A: ____ Unsat ____*
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRC061CLJC-S2.DOC PAGE 4 OF 6 REV. 0
JPM NUMBER:
NRC061CLJC-S2 EXAMINEE CUE SHEET Initial Conditions: Unit 1 has been operating at 100% power with all systems aligned for normal full power operation.
Within the last minute,
- several annunciators alarmed,
- PZR PORV PCV-456 cycling open and close
- PZR backup heaters automatically energized.
Initiating Cue: The Shift Foreman directs you to respond to the transient using OP AP-5 Malfunction of Eagle 21 Protection or Control Channel.
Task Standard: Procedural actions have been completed so that normal automatic pressurizer pressure control may be restored.
NRC061CLJC-S2.DOC PAGE 5 OF 6 REV. 0
JPM TITLE: RESPOND TO PRESSURE CONTROL CHANNEL PT- JPM NUMBER:
456 FAILED HIGH NRC061CLJC-S2 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-501 (100%, BOL).
Enter drill file 1143 or manually insert the following:
Command Description xmt pzr18 3,2515,0,0,d,0 Fails PT-456 high (back up channel for control) run 10 Runs simulator for 10 seconds Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRC061CLJC-S2.DOC PAGE 6 OF 6 REV. 0
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJC-S3
Title:
ISOLATE A LOCA OUTSIDE CONTAINMENT Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
EOP ECA-1.2, LOCA Outside Containment, Rev. 6A Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 4, 5 Job Designation: RO/SRO Task Number: 04P/E04/EA1.1 Rating: 4.0/4.0 AUTHOR: GARY HUTCHISON DATE: 08/14/08 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
MANAGER OPERATIONS REV. 0
JPM TITLE: ISOLATE A LOCA OUTSIDE CONTAINMENT JPM NUMBER:
NRC061CLJC-S3 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: None Initial Conditions: Unit 1 has experienced a Safety Injection. Automatic actuation of safeguards equipment was verified. It was determined that SI cannot be terminated and abnormal radiation has been observed in the auxiliary building.
Initiating Cue: The Shift Foreman directs you to perform the actions for a LOCA outside containment, in accordance with ECA-1.2.
Task Standard: All actions to respond to a LOCA outside containment have been performed and the correct procedure for recovery has been identified.
NRC061CLJC-S3.DOC PAGE 2 OF 6 REV. 0
JPM TITLE: ISOLATE A LOCA OUTSIDE CONTAINMENT JPM NUMBER:
NRC061CLJC-S3 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References EOP ECA-1.2.
Step was: Sat: ______ Unsat _______*
- 2. Verify the following valves 2.1 Observes that the following valves closed: are closed:
8702, RCS RHR Suct LP4 HL 8702 8701, RCS RHR Suct LP4 HL 8701 8703, RHR to hot legs 1 and 2 8703 8802A, SI to hot legs 1 and 2 8802A 8802B, SI to hot legs 3 and 4 8802B Step was: Sat: ______ Unsat _______*
- 3. Try to identify and isolate the leak 3.1 Cuts in series contactor toggle by closing 8809A, RHR to cold switch for 8809A.
legs 1 and 2.
3.2 Closes 8809A.
3.3 Diagnoses that RCS pressure (PI-405, PR-403, PPC, or SPDS) is still lowering.
3.4 Reopens 8809A.
Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRC061CLJC-S3.DOC PAGE 3 OF 6 REV. 0
JPM TITLE: ISOLATE A LOCA OUTSIDE CONTAINMENT JPM NUMBER:
NRC061CLJC-S3 INSTRUCTOR WORKSHEET Step Expected Operator Actions
legs 3 and 4 Note: The operator shall receive an UNSAT for the following critical sub-step if he later reopens 8809B.
4.2 Closes 8809B. **
4.3 Diagnoses that RCS pressure (PI-405, PR-403, PPC, or SPDS) is stable or increasing.
Step was: Sat: ______ Unsat _______*
5.2 Identifies EOP E-1 as correct procedure for recovery. **
Step was: Sat: ______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRC061CLJC-S3.DOC PAGE 4 OF 6 REV. 0
JPM NUMBER:
NRC061CLJC-S3 EXAMINEE CUE SHEET Initial Conditions: Unit 1 has experienced a Safety Injection. Automatic actuation of safeguards equipment was verified. It was determined that SI cannot be terminated and abnormal radiation has been observed in the auxiliary building.
Initiating Cue: The Shift Foreman directs you to perform the actions for a LOCA outside containment, in accordance with ECA-1.2.
Task Standard: All actions to respond to a LOCA outside containment have been performed and the correct procedure for recovery has been identified.
NRC061CLJC-S3.DOC PAGE 5 OF 6 REV. 0
JPM TITLE: ISOLATE A LOCA OUTSIDE CONTAINMENT JPM NUMBER:
NRC061CLJC-S3 ATTACHMENT 1, SIMULATOR SETUP Select IC-510. Click the BYPASS SW CHECK button on the expert screen to continue after control boards are aligned.
Enter drill file 1118 or manually enter the following::
Command Description ovr xv2o225r act,0,0,0, d, red lite off 8701.
Ovr xv2o225g act,1,0,0,d,0 green lite on 8701 ovr xv2o226g act,1,0,0,d,0 green lite on 8702 ovr xv2o226r act,0,0,0,d,0 red lite off 8702 ovr xs01d08 act,0,0,0,d,0 8701/8702 monitor lite off vlv RHR2 2,1,0,0,d,0 #RRHH8702 actions to keep rcs pressure decreasing mal rhr1 act,5000,5,0,d,0 set csis8803=0.01 set rrhh8701=0.1 8701 opened to 10%
vlv rhr1 2,0,1,0,c,rrhh8809(2) .lt.0.1,0 8701 will shut when 8809b goes
- rrhh8701 closed Ovr xc2i030c act,1,0,0,d,5 #cc2038a Actuate SI run run Trip RCPs , Reset SI, Reset Phase A Isolation, Open FCV-584, then Go to Freeze.
Scroll chart for PR-403 forward so operator has a reference point for RCS pressure trends.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRC061CLJC-S3.DOC PAGE 6 OF 6 REV. 0
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJC-S4
Title:
MANUALLY ISOLATE CVI COMPONENTS Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
EOP E-0, Reactor Trip or Safety Injection, Rev 33A Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3 Job Designation: RO/SRO Task Number: 05/103/A3.01 Rating: 3.9/4.2 AUTHOR: GARY HUTCHISON DATE: 09/18/2008 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: MANUALLY ISOLATE CVI COMPONENTS JPM NUMBER:
NRC061CLJC-S4 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: None Initial Conditions: A Containment Vent was in progress when Unit 1 reactor trip and safety injection occurred.
Initiating Cue: You are directed by the Shift Foreman to verify Containment Vent Isolation by performing Appendix E, step 3, of EOP E-0.
Task Standard: All Containment Vent Isolation valves have been verified closed.
NRC061CLJC- PAGE 2 OF 6 REV. 0 S4.DOC
JPM TITLE: MANUALLY ISOLATE CVI COMPONENTS JPM NUMBER:
NRC061CLJC-S4 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References EOP E-0, Appendix E, Step 3.
Step was: Sat: ______ Unsat _______*
- 2. Verify Containment Vent 2.1 Observes the following on the Isolation. CONTAINMENT VENT ISOLATION portion of Monitor Light Box B:
Train A red activate light - OFF Train B red activate light - OFF White status lights - OFF Step was: Sat: ______ Unsat _______*
- 3. Manually actuate CONTMT ISOL Note: Operator may position CONTMT PHASE A ISOL PHASE A TRAINS A & B OR switch to ACTUATE; however, Manually close the Cnm Vent this will not work.
isolation valves with white status 3.1 Turns the Phase A actuation switch to lights - ON ACTUATE. (optional) 3.2 Positions the MONITOR LIGHT TEST switch to TEST.
3.3 Identifies open Cnm Vent Isol valves using the CONTAINMENT VENT ISOLATION portion of Monitor Light Box B or Control Board switch indications.
(Continue step on next page.)
NRC061CLJC- PAGE 3 OF 6 REV. 0 S4.DOC
JPM TITLE: MANUALLY ISOLATE CVI COMPONENTS JPM NUMBER:
NRC061CLJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions 3.4 Closes each open Containment Vent Isolation valve. **
- Positions FCV-678 to CLOSE
- Positions FCV-679/681 to CLOSE
- Positions FCV-662 to CLOSE
- Positions FCV-663 to Neutral Note: The above step has been performed Sat if all Phase A white lights are off at the completion of the step.
3.5 Verifies that each Containment Isolation Phase A valve has closed.
Step was: Sat: ______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
NRC061CLJC- PAGE 4 OF 6 REV. 0 S4.DOC
JPM NUMBER NRC061CLJC-S4 EXAMINEE CUE SHEET Initial Conditions: A Containment Vent was in progress when Unit 1 reactor trip and safety injection occurred.
Initiating Cue: You are directed by the Shift Foreman to verify Containment Vent Isolation by performing Appendix E, step 3, of EOP E-0.
Task Standard: All Containment Vent Isolation valves have been verified closed.
NRC061CLJC- PAGE 5 OF 6 REV. 0 S4.DOC
JPM TITLE: MANUALLY ISOLATE CVI COMPONENTS JPM NUMBER:
NRC061CLJC-S4 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
Take FCV-662 control switch to nuetral Take FCV-663 control switch to Press Rel position and Depress until red light on Enter drill file 6615 or manually insert the following:
Command Description ovr xv1o404o act,0,0,0,d,0 CVI red light trn A off ovr xv1o405o act,0,0,0,d,0 CVI red light trn B off vlv ven22 2,1,0,0,d,xv4i385c Opens FCV-678, closes when C/S to Close vlv ven23 2,1,0,0,d,xv4i384c Opens FCV-679, closes when C/S to Close vlv ven35 2,1,0,0,d,xv4i384c Opens FCV-681, closes when C/S to Close vlv ven19 2,1,0,0,d,xv4i160c Opens FCV-662, closes when C/S to Close Vlv ven29 2,1,0,0,d,xv4i163a Opens FCV-663, close when C/S to Neutral Run 75 ovr xc2i030c act,1,0,0,d,5 Manual Safety Injection Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRC061CLJC- PAGE 6 OF 6 REV. 0 S4.DOC
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJC-S5
Title:
RESPOND TO A LOSS OF CCW FLOW TO ONE RCP Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
AR PK01-08, CCW HEADER C, Rev 17 OP AP-11, Malfunction of Component Cooling Water System, Rev 24 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 4,5,6 Job Designation: RO/SRO Task Number: 008/08/A2.01 Rating: 3.3/3.6 AUTHOR: GARY HUTCHISON DATE: 08/14/08 REVIEWED BY: N/A DATE:
TRAINING LEADER APPROVED BY: N/A DATE:
LINE MANAGER REV. 0
JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO ONE RCP JPM NUMBER: NRC061CLJC-S5 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: None Initial Conditions: Unit 1 is operating at 100% power.
Initiating Cue: PK01-08, CCW HEADER C, has just alarmed. Input 428, RCP Thermal Barrier CCW Flow Lo is causing the alarm.
Task Standard: The alarms have been responded to and appropriate actions have been taken in accordance with applicable plant procedures.
NRC061CLJC- PAGE 2 OF 7 REV. 0 S5.DOC
JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO ONE RCP JPM NUMBER:
NRC061CLJC-S5 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References AR PK01-08.
Note: Operator may go directly to OP AP-11 Step was: Sat: ______ Unsat: _______*
2.2 Observes that FCV-355 and FCV-356 are open.
Note: Operator may use PPC PICTURE RCP or Group Display PK05-02 to monitor RCP 1-2.
2.3 Observes RCP lower bearing temps normal and proper seal injection flow on RCPs.
2.4 Refers to OP AP-11, Section E.
Step was: Sat: ______ Unsat _______*
Lube Oil Coolers:
3.2 Observes that the following valves
- a. Verify CCW Vlvs - OPEN are open:
- FCV-355 Alarm (PK01-08) - NOT IN
- FCV-356
- FCV-749 (PK05-01), 02, 03, 04) - NOT
- FCV-363 IN 3.3 Observes that PK01-08 is in alarm.
3.4 Determines RCP Lube Oil coolers have CCW flow.
Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps NRC061CLJC- PAGE 3 OF 7 REV. 0 S5.DOC
JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO ONE RCP JPM NUMBER:
NRC061CLJC-S5 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. VERIFY RCP Seal Injection In 4.1 Observes Seal Injection flow less Service. than 8 gpm.
- 4.2 Adjusts HCV-142 to increase seal injection flow between 8 and 13 gpm. **
4.3 Observes RCP Seal #1 Outlet Temps and Radial Brg Outlet Temps NORMAL.
Step was: Sat: ______ Unsat _______*
Thermal Barriers Normal.
5.2 Verifies FCV-357 Closed and PK01-08 IN.
- 5.3 Goes to Step 5.b of Section B.**
Step was: Sat: ______ Unsat _______*
- 6. Isolate Leak. ** 6.1 Closes FCV-750. **
Cue: An Operator in the field will close the valves.
6.3 Monitors containment sump for expected level increase.
6.4 Implements OP AP-1 for excessive RCS leakage.
Cue: The SFM will take care of sump monitoring and AP-1.
Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps NRC061CLJC- PAGE 4 OF 7 REV. 0 S5.DOC
JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO ONE RCP JPM NUMBER:
NRC061CLJC-S5 INSTRUCTOR WORKSHEET Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps NRC061CLJC- PAGE 5 OF 7 REV. 0 S5.DOC
JPM NUMBER:
NRC061CLJC-S5 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is operating at 100% power.
Initiating Cue: PK01-08, CCW HEADER C, has just alarmed. Input 428, RCP Thermal Barrier CCW Flow Lo is causing the alarm.
Task Standard: The alarms have been responded to and appropriate actions have been taken in accordance with applicable plant procedures.
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JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO ONE RCP JPM NUMBER: NRC061CLJC-S5 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
Manually insert the following:
Command Description
- 2. run 90 Runs 90 seconds Open HCV-142 to get seal injection flow at ~ 6.5 gpm, must be < 8 gpm without seal injection flow lo alarms on PK05-01 thru 04 in alarm.
Ensure the annunciator CRT and alarm viewer contains the alarm inputs required by the JPM.
o Acknowledge and reset alarms. This should show the RCP Thermal Barrier Return Flow low alarm input (PK01-08) and a Hi Rad alarm. The High Flow for RCP Thermal Barrier alarm clears on closure of 357. The students must diagnose this cause and affect.
Ensure PPC alarms acknowledged.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee completes reading the cue sheet.
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NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJC-S6
Title:
RCS COOLDOWN FOR A STEAM GENERATOR TUBE RUPTURE Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
U1 EOP E-3, Steam Generator Tube Rupture, Rev. 29 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2, 6, 8 Job Designation: RO/SRO Task Number: 04S/041/A4.06 Rating: 2.9/3.1 AUTHOR: GARY HUTCHISON DATE: 08/14/08 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
MANAGER OPERATIONS REV. 0
JPM TITLE: RCS COOLDOWN FOR A STEAM GENERATOR JPM NUMBER:
TUBE RUPTURE NRC061CLJC-S6 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: None Initial Conditions: A tube rupture in steam generator 1-2 occurred. All actions of EOP E-3 up to the preparation for RCS cooldown are complete.
Initiating Cue: The Shift Foreman directs you to perform a cooldown of the RCS in accordance with EOP E-3, starting at Step 7.
Task Standard: The RCS has been cooled down to the required temperature in accordance with EOP E-3.
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JPM TITLE: RCS COOLDOWN FOR A STEAM GENERATOR JPM NUMBER:
TUBE RUPTURE NRC061CLJC-S6 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References EOP E-3.
Step was: Sat: ______ Unsat _______*
- 2. Determine required core exit 2.1 Reads CAUTION prior to step.
thermocouple temperature.
2.2 Checks ruptured S/G pressure.
Note: Evaluator should verify that steam generator pressure is accurate for plant conditions (approximately 1020-1030 psig).
2.3 Determines required core exit temperature based on ruptured S/G pressure using the table Step 7.a. **
Note: Evaluator should verify that the target temperature is accurate based on actual S/G pressure Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
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JPM TITLE: RCS COOLDOWN FOR A STEAM GENERATOR JPM NUMBER:
TUBE RUPTURE NRC061CLJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Check if condenser steam dump 3.1 Observes that 3 MSIVs are open.
should be used in the pressure control mode. 3.2 Observes PK08-14, CONDENSER AVAILABLE C ON.
or Observes adequate condenser vacuum on PI-44 and one circulating water pump running.
3.3 Observes that FCV-230 is closed.
3.4 Depresses the HC-507 MANUAL pushbutton and adjusts controller as necessary to achieve 0% output.
Note: The operator may note that HC-507 has failed at this time.
3.5 Positions the TAVG / STM PRESS /
C7A & C7B RESET switch to the STEAM PRESS position.
3.6 Observes that the steam dump valves are closed, with a DUMP DEMAND (UI-500) of 0%.
Step was: Sat: ______ Unsat _______*
- 4. Block Low Steamline Pressure 4.1 Reads CAUTIONS prior to step.
Safety Injection.
4.2 Observes that RCS pressure is greater than 1915 psig.
Cue: Other operators will complete Step 8 prior to any S/G pressure decreasing to less than 700 psig.
Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
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JPM TITLE: RCS COOLDOWN FOR A STEAM GENERATOR JPM NUMBER:
TUBE RUPTURE NRC061CLJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 5. Initiate RCS cooldown using 40% 5.1 Reads NOTES prior to step.
steam dumps.
5.2 Observes PK08-07, LO-LO TAVG PERMISSIVE P ON.
5.3 Positions the STEAM DUMP CONTROL BYPASS SELECT switches to BYPASS INTLK.
5.4 Verifies P-12 is bypassed by observing PK07-05, STM DUMP CONTROL BYPASS - ON.
5.5 Depresses the HC-507 controller INCREASE pushbutton to begin dumping steam.
5.6 Diagnoses that the 40% steam dump valves are NOT opening.
Step was: Sat: ______ Unsat _______*
- 6. Use intact S/G 10% steam dump 6.1 Fully opens PCV-19, 21, and 22. **
and manually or locally dump steam at maximum rate possible.
6.2 Verifies PCV-19, 21, and 22 are fully opened.
Step was: Sat: ______ Unsat _______*
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
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JPM TITLE: RCS COOLDOWN FOR A STEAM GENERATOR JPM NUMBER:
TUBE RUPTURE NRC061CLJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 7. Check core exit thermocouples 7.1 Checks core exit thermocouples.
less than required temperature (SPDS/PAM 3/4). 7.2 Continues to Step 11 until target temperature is reached.
Cue: Other operators will perform Steps 11 through 17 while you continue the cooldown.
Step was: Sat: ______ Unsat _______*
Step was: Sat: ______ Unsat _______*
- 9. Maintain the required temperature 9.1 Determines new 10% steam dump with steam dumps in AUTO. setpoint by dividing the average intact S/G pressure by 120.
9.2 Adjust the PCV-19, 21, and 22 controller pots to the new setpoint and shifts the controller to AUTO.
Step was: Sat: ______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
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JPM NUMBER:
NRC061CLJC-S6 EXAMINEE CUE SHEET Initial Conditions: A tube rupture in steam generator 1-2 occurred. All actions of EOP E-3 up to the preparation for RCS cooldown are complete.
Initiating Cue: The Shift Foreman directs you to perform a cooldown of the RCS in accordance with EOP E-3, starting at Step 7.
Task Standard: The RCS has been cooled down to the required temperature in accordance with EOP E-3.
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JPM TITLE: RCS COOLDOWN FOR A STEAM GENERATOR JPM NUMBER:
TUBE RUPTURE NRC061CLJC-S6 ATTACHMENT 1, SIMULATOR SETUP Select JPM IC-620. Click the BYPASS SWCK button on the expert screen to continue after control boards are aligned.
Enter drill file 1090 or manually insert the following:
Command Description cnh mss1 2,0,0,0,d,0 #xcnh507 Fails HC-507 to 0% in Auto or Manual ovr xc2i025c act,1,0,0,c,lpplp11,5 block stm line press si at P-11 ovr xc2i026c act,1,0,0,c,lpplp11,5 This SNAP allow entry into EOP E-3 at Step 7 with ruptured steam generator 1-2 level at approximately 24% and increasing slowly.
Display PCC screen E3 on one of the CC2 PPC monitors.
Display the THERMOCOUPLE MAP ON SPDS panel B.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
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NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJC-S7
Title:
Verify RM-44A Operable Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
OP H-4:I Containment Ventilation Make Available and Place In Service, Rev. 31.
Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3 Job Designation: RO/SRO Task Number: Sys. 073/ A4.03 Rating: 3.1 / 3.2 AUTHOR: GARY HUTCHISON DATE: 08/13/08 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: VERIFY RM-44A OPERABLE JPM NUMBER:
NRC061CLJC-S7 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: Marked up OP H-4:1 Attachment 9.4.
Initial Conditions: Unit 1 is at 100% power.The Containment Vent Checklist is being performed. Steps 1-4 of Attachment 9.4 of OP H-4:I have been completed.
Initiating Cue: You are directed by the Shift Foreman to verify RM-44A operable per step 5 of Attachment 9.4 of OP H-4:I.
Task Standard: Step 5 performed and SFM informed of RM-44A status.
NRC061CLJC- PAGE 2 OF 6 REV. 0 S7.DOC
JPM TITLE: VERIFY RM-44A OPERABLE JPM NUMBER:
NRC061CLJC-S7 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Check RM-44A status on the 1.1 Checks status:
Control Room RDU.
- LOCAL POWER ON/OFF keyswitch in ON
- LOCAL POWER light lit.
- Program Mode keyswitch in RUN
- No alarm lights lit
- Normal light lit
- CR PNL light lit.
- No clearances or work orders in progress.
Step was: Sat: ______ Unsat _______*
- 2. Checks indications prior to 2.1 Checks the following:
performing source check.
- NORM lamp "ON"
- C/S pushbutton lamp "OFF"
- TEST lamp "OFF"
- Records initial RM-44A reading.
Step was: Sat: ______ Unsat _______*
- 3. Starts source check rountine. 3.1 Press the C/S pushbutton lamp (should hold for at least 3 seconds.)**
3.2 Verify that the C/S light starts flashing.
3.3 While the C/S light is flashing, Records the background reading in CPM. **
(Continue step on next page.)
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JPM TITLE: VERIFY RM-44A OPERABLE JPM NUMBER:
NRC061CLJC-S7 INSTRUCTOR WORKSHEET Step Expected Operator Actions 3.4 Verify the change in RM-44A status
- C/S pushbutton lamp "ON" solid after flashing 30 seconds
- NORM lamp "OFF"
- TEST lamp "ON" 3.5 Records RM-44A reading.**
3.6 Verifies RDU counts have increased by at least 150 cpm. **
3.7 Press the C/S pushbutton lamp.**
3.8 Verify change in RM-44A status:
- NORM lamp "ON"
- C/S pushbutton lamp "OFF"
- TEST lamp "OFF" 3.9 Verify counts have returned to normal.
- 4. Reports status to SFM. Informs SFM that RM-44A is operable.
Step was: Sat: ______ Unsat _______*
Stop Time:
Total Time: (Enter total time on the cover page)
NRC061CLJC- PAGE 4 OF 6 REV. 0 S7.DOC
JPM NUMBER NRC061CLJC-S7 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is at 100% power.The Containment Vent Checklist is being performed. Steps 1-4 of Attachment 9.4 of OP H-4:I have been completed.
Initiating Cue: You are directed by the Shift Foreman to verify RM-44A operable per step 5 of Attachment 9.4 of OP H-4:I.
Task Standard: Step 5 performed and SFM informed of RM-44A status.
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JPM TITLE: VERIFY RM-44A OPERABLE JPM NUMBER:
NRC061CLJC-S7 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
No Drill file is needed for this JPM.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRC061CLJC- PAGE 6 OF 6 REV. 0 S7.DOC
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP H-4:I NUCLEAR POWER GENERATION REVISION 31 DIABLO CANYON POWER PLANT PAGE 1 OF 4 OPERATING PROCEDURE UNIT TITLE: Containment Ventilation Make Available and Place In Service 1
INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This procedure covers the system alignment for the Containment Ventilation System and provides instructions for performing a Containment Vent or Purge.
- 2. DISCUSSION 2.1 This procedure provides uniform instructions to align the Containment Ventilation System. It does not verify the system is capable of Containment Ventilation Isolation due to high plant vent radiation level or presence of a safety injection signal. That task is performed by:
PROCEDURE CALLED OUT BY OP G-4 (Proc Rad Monitors) Mode transition checklist STP V-9 (Refuel: hi-rad CVI demo) OP L-6 STP M-16M1 Mode transition checklist
- 3. RESPONSIBILITIES 3.1 The Shift Foreman (SFM) is responsible for:
3.1.1 Designating the components/valves to be lined up using step 1 of the Instruction Sheet. (Attachment 9.1) 3.1.2 Performing the valve alignment verification according to the checklist.
(Attachment 9.2) 3.1.3 Performing Containment purges utilizing an approved Authorization for Discharge of Containment Atmosphere and a Containment Purge Checklist.
(Attachment 9.3) 3.1.4 Performing Containment vents utilizing an approved Authorization for Discharge of Containment Atmosphere and a Containment Vent Checklist.
(Attachment 9.4) 3.1.5 Performing Attachment 9.5, Starting and Stopping Fans During a Continuous Purge.
3.2 The chemistry foreman is responsible for authorizing Containment releases by venting or purging by issuance of Form 69-9355, "Authorization For Discharge of Containment Atmosphere."
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP H-4:I DIABLO CANYON POWER PLANT REVISION 31 PAGE 2 OF 4 TITLE: Containment Ventilation Make Available and Place In UNIT 1 Service
- 4. PREREQUISITES 4.1 Instrument Air System in service.
4.2 The 480 Volts Nonvital System in service.
4.3 125 VDC System in service.
- 5. PRECAUTIONS AND LIMITATIONS 5.1 Venting or purging is not allowed unless it is specifically authorized by chemistry, via an Authorization for Discharge of Containment Atmosphere. Refer to "Gaseous Radwaste Discharge Management" procedure, CAP A-6 on plant policy concerning this matter. A Containment Purge Checklist (Attachment 9.3) or a Containment Vent Checklist (Attachment 9.4) must accompany the completed authorization for each discharge.
5.2 After each operation of the Containment Ventilation Isolation Valves, applicable valve leak test (STP V-661, V-662, V-663) must be performed within the time frame specified by TS SR 3.6.3.7.
5.3 ECG 23.3 limits the use of the Containment Ventilation System during Modes 1, 2, 3, and 4. To ensure the limit is not exceeded, in addition to logging the purge time on the Discharge Permit, record of this time shall be kept in the Containment Purge Valve Record Log so the information can be transferred to Weekly STP I-1C.
5.4 During core alteration or movement of irradiated fuel within the Containment, TS 3.9.4 on Containment Ventilation Isolation System applies.
5.5 At all times, CONTAINMENT INTEGRITY/CONTAINMENT PENETRATIONS must be maintained in accordance to Operational Mode requirements, TS 3.6.1, 3.6.3 and 3.9.4.
5.6 The opening or closing of FCV-663 may cause movement of dampers M-8A and M-8B in the Auxiliary Building Ventilation System.
5.7 TS 3.3.6 restricts the opening of Containment Purge Supply and Exhaust Valves (RCV-11, 12, FCV-660, 661, 662, 663 and 664) in Modes 1, 2, 3 and 4 unless both RM-44A and RM-44B are OPERABLE.
5.8 Do NOT open RCV-11, RCV-12, FCV-660, and FCV-661 in MODES 1-4 without operations manager permission. These valves have shown susceptibility to failure of local leakrate testing; therefore, unless an extreme need exists, do NOT cycle these valves in MODES 1-4. If these valves are opened in MODES 1-4, STP V-2E, V-2Q, V-3T7 and M-16M1 must be current, as applicable.
5.9 Venting or purging containment increases the risk of a Large Early Release. In MODES 1 - 4, manage the risk in accordance with AD7.DC6, "On-Line Maintenance Risk Management."
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP H-4:I DIABLO CANYON POWER PLANT REVISION 31 PAGE 3 OF 4 TITLE: Containment Ventilation Make Available and Place In UNIT 1 Service
- 6. INSTRUCTIONS 6.1 SYSTEM MAKE AVAILABLE 6.1.1 Review all Prerequisites, and Precautions and Limitations.
6.1.2 Perform System Alignment Verification Checklist per Attachment 9.2.
CAUTION: Review Precautions and Limitations before opening or closing FCV-663.
6.1.3 Perform STP V-2E on FCV-661, 663, 664 and RCV-12.
6.1.4 Perform STP V-2Q on FCV-660, 662 and RCV-11.
6.1.5 System alignment is now complete.
6.2 CONTAINMENT PURGE 6.2.1 Verify Attachment 9.2 of this procedure is complete.
6.2.2 Verify the Authorization for Discharge of Containment Atmosphere is current.
6.2.3 Perform a containment purge in accordance with the Authorization for Discharge of Containment Atmosphere and the Containment Purge Checklist (Attachment 9.3).
6.2.4 The system is now in a standby status.
6.2.5 IF desired to start or stop fans while a continuous purge is in progress, THEN perform Attachment 9.5, "Starting and Stopping Fans During a Continuous Purge."
6.3 CONTAINMENT VACUUM RELIEF 6.3.1 Verify Attachment 9.2 of this procedure is complete.
6.3.2 Notify chemistry engineer that a vacuum relief is being performed on Containment.
6.3.3 Verify that a negative pressure exists in Containment.
6.3.4 Open FCV-662 and FCV-664.
6.3.5 When vacuum relief is complete (desired negative pressure or 0 psig containment pressure is reached), close FCV-662 and FCV-664.
6.3.6 Determine the total open time for the containment vacuum relief and enter it in the Containment Purge Valve Record Log.
6.3.7 Perform STP V-663 within the time frame specified by TS SR 3.6.3.7.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP H-4:I DIABLO CANYON POWER PLANT REVISION 31 PAGE 4 OF 4 TITLE: Containment Ventilation Make Available and Place In UNIT 1 Service 6.4 CONTAINMENT VENT 6.4.1 Verify Attachment 9.2 of this procedure is complete.
6.4.2 Verify the Authorization for Discharge of Containment Atmosphere is current.
6.4.3 Perform a containment vent in accordance with the Authorization for Discharge of Containment Atmosphere and the Containment Vent Checklist (Attachment 9.4).
6.4.4 The system is now in standby status.
- 7. REFERENCES 7.1 Operating Valve Identification Drawings:
7.1.1 106723, Ventilation and Air Conditioning System 7.1.2 106725, Instrument Air/Service Air System
- 8. RECORDS 8.1 Send the completed alignment checklist to the shift engineer. It will be kept in the Control Room until superseded.
8.2 Route superseded alignment checklists to the control room assistant for entry into the Records Management System (RMS).
8.3 The Containment Purge Checklist (Attachment 9.3) or Containment Vent Checklist (Attachment 9.4) SHOULD be attached to the Authorization for Discharge of Containment Atmosphere and forward to the chemistry foreman for review and disposition. The Discharge Permit is archived in RMS and SHOULD have the applicable Checklist attached.
- 9. ATTACHMENTS 9.1 "Containment Ventilation - Alignment Verification Instruction Sheet," 10/17/06 9.2 "Containment Ventilation - Alignment Verification Checklist," 11/01/00 9.3 "Containment Purge Checklist," 03/24/08 9.4 "Containment Vent Checklist," 03/24/08 9.5 "Starting and Stopping Fans During a Continuous Purge," 03/24/08 rad6D897.Doc 02 0325.0841
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03/24/08 Page 1 of 4 DIABLO CANYON POWER PLANT TITLE: Containment Vent Checklist OP H-4:I ATTACHMENT 9.4 1
Authorization for Discharge of Containment Atmosphere Batch No. ___2009-1-002__________________
NOTE: This checklist is required to be completed and attached to EACH discharge authorization, even if a continuous vent is in progress.
INITIALS
- 1. Verify current System Alignment Checklist (Attachment 9.2) complete per Attachment 9.1 of this procedure. GLH
- 2. Verify Authorization for Discharge of Containment Atmosphere is current. GLH
- 3. IF in MODES 1-4, perform risk management actions per AD7.DC6 (otherwise mark "N/A"). GLH
- 4. Determine operability requirements of RM-44A and RM-44B: GLH
- a. Record the plant operating MODE: __1__
- b. Mark the appropriate box below and follow its instructions.
[X] MODES 1-4 Both RM-44A and RM-44B required.
Perform steps 5 and 6.
[ ] MODE 5
[ ] MODE 6 with NO CORE ALTERATIONS Neither RM-44A nor RM-44B required.
AND no movement of irradiated fuel in Containment in progress N/A steps 5 and 6 and GO TO step 7.
[ ] Reactor defueled
[ ] MODE 6 with CORE ALTERATIONS Either RM-44A or RM-44B required.
OR irradiated fuel being moved in Perform steps 5 and/or 6 on the operable Containment RM(s). N/A one of these steps if not performed.
- 5. IF applicable, verify RM-44A OPERABLE as follows (otherwise check "N/A" and leave blank substeps 5.a and 5.b): N/A [ ]
- a. Check RM-44A status on the Control Room RDU:
- LOCAL POWER ON/OFF keyswitch in ON. ______
- LOCAL POWER light lit. ______
- Program Mode keyswitch in RUN. ______
- No alarm lights lit. ______
- Normal light lit. ______
- CR PNL light lit ______
- No clearances or work orders in progress. ______
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03/24/08 Page 2 of 4 OP H-4:I (UNIT 1)
ATTACHMENT 9.4 TITLE: Containment Vent Checklist INITIALS
- b. Perform source check on RM-44A as follows:
- 1) Check the following:
- NORM lamp "ON" ______
- C/S pushbutton lamp "OFF" ______
- TEST lamp "OFF" ______
- Initial reading RM-44A uci/cc______ ______
- 2) Press the C/S pushbutton lamp and hold for at least 3 seconds. ______
- 3) Verify that the C/S light starts flashing. ______
NOTE: RM-44A will display readings in CPM while the C/S light is either flashing or lit solid, regardless of the scale displayed in the NORM operating mode.
- 4) While C/S light is flashing (approximately 30 seconds), record the background reading from the display: RM-44A CPM ____________. ______
- 5) Verify the change in RM-44A status:
- C/S pushbutton lamp "ON" solid after flashing 30 seconds (C/S solenoid energizes) ______
- NORM lamp "OFF" ______
- TEST lamp "ON" ______
- RM-44A CPM __________ ______
- 6) Verify RDU counts have increased by at least 150 cpm. ______
- 7) Press the C/S pushbutton lamp (deenergizes C/S solenoid; if pushbutton is not pressed, solenoid is automatically deenergized after 3 minutes). ______
- 8) Verify the change in RM-44A lamp status:
- NORM lamp "ON" ______
- C/S pushbutton lamp "OFF" ______
- TEST lamp "OFF" ______
- 9) Verify that RM-44A counts have returned to normal levels recorded in step 5.b.1). ______
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03/24/08 Page 3 of 4 OP H-4:I (UNIT 1)
ATTACHMENT 9.4 TITLE: Containment Vent Checklist INITIALS
- 6. IF applicable, verify RM-44B OPERABLE as follows (otherwise check "N/A" and leave blank substeps 6.a and 6.b): N/A [ ]
- a. Check RM-44B status on the Control Room RDU:
- LOCAL POWER ON/OFF keyswitch in ON. ______
- LOCAL POWER light lit. ______
- Program Mode keyswitch in RUN. ______
- No alarm lights lit. ______
- Normal light lit. ______
- CR PNL light lit. ______
- No clearances or work orders in progress. ______
- b. Perform source check on RM-44B as follows:
- 1) Check the following:
- NORM lamp "ON" ______
- C/S pushbutton lamp "OFF" ______
- TEST lamp "OFF" ______
- Initial reading RM-44B uci/cc______ ______
- 2) Press the C/S pushbutton lamp and hold for at least 3 seconds. ______
- 3) Verify that the C/S light starts flashing. ______
NOTE: RM-44B will display readings in CPM while the C/S light is either flashing or lit solid, regardless of the scale displayed in the NORM operating mode.
- 4) While C/S light is flashing (approximately 30 seconds), record the background reading from the display: RM-44B CPM ____________. ______
- 5) Verify the change in RM-44B status:
- C/S pushbutton lamp "ON" solid after flashing 30 seconds (C/S solenoid energizes) ______
- NORM lamp "OFF" ______
- TEST lamp "ON" ______
- RM-44B CPM__________ ______
- 6) Verify RDU counts have increased by at least 150 cpm. ______
- 7) Press the C/S pushbutton lamp (deenergizes C/S solenoid; if pushbutton is not pressed, solenoid is automatically deenergized after 3 minutes). ______
rad6D897.Doc 02 0325.0841
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03/24/08 Page 4 of 4 OP H-4:I (UNIT 1)
ATTACHMENT 9.4 TITLE: Containment Vent Checklist INITIALS
- 8) Verify the change in RM-44B lamp status:
- NORM lamp "ON" ______
- C/S pushbutton lamp "OFF" ______
- TEST lamp "OFF" ______
- 9) Verify that RM-44B counts have returned to normal levels recorded in step 6.b.1) ______
- 7. Perform Release Information Sections of the Authorization for Discharge Form (steps 3a-e). ______
- 8. Obtain SFM approval per step 3f of the Authorization For Discharge Form. ______
NOTE 1: LERF Risk Assessment per AD7.DC6 required.
NOTE 2: Steps 9 and 10 can be marked N/A if a continuous vent is in progress.
- 9. IF applicable, start venting as follows (Check "N/A" and leave blank all substeps if a continuous vent is in progress): N/A [ ]
- a. OPEN FCV-662, Inside Containment Vent Isolation Valve. ______
- b. OPEN FCV-663, Outside Containment Pressure Relief Isolation Valve. ______
- 10. At the completion of vent, secure as follows (Check "N/A" and leave blank all substeps if a continuous vent is in progress): N/A [ ]
- a. CLOSE FCV-662, Inside Containment Vent Isolation Valve. ______
- b. CLOSE FCV-663, Outside Containment Pressure Relief Isolation Valve. ______
- 11. Perform Release Information and Approval Section of the Authorization For Discharge Form (steps 3h-k). ______
- 12. IF in MODES 1-4, update the Containment Vent Valve Record Log (otherwise mark "N/A"). ______
- 13. Return the Authorization for Discharge of Containment Atmosphere to SFM/SE. ______
Comments:
Checklist Complete (SFM or SE): Date/Time: /
NOTE: This checklist SHOULD be attached to the Authorization for Discharge of Containment Atmosphere. Forward to chemistry for their review and disposition.
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NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJP-P1
Title:
TRANSFER PRESSURIZER HEATER GROUP 12 TO BACKUP POWER Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
OP A-4A:I, Pressurizer - Make Available, Rev. 24 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 3, 4, 5, 6, 8, 10, 11 Job Designation: RO/SRO Task Number: 06/062/A2.12 Rating: 3.2/3.6 AUTHOR: GARY HUTCHISON DATE: 09/18/2008 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV.0
JPM TITLE: TRANSFER PRESSURIZER HEATER GROUP 12 TO JPM NUMBER:
BACKUP POWER NRC061CLJP-P1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: A copy of OP A-4A:I, Section 6.4.
Initial Conditions: Unit 1 is in MODE 1. An electrical fault has deenergized 480VAC bus 13D. Offsite power is available.
Initiating Cue: The Shift Foreman directs you to transfer pressurizer heater group 12 to its backup power supply in accordance with OP A-4A:I, Section 6.4.
Task Standard: Pressurizer heater group 12 has been transferred to the backup power supply in accordance with OP A-4A:I.
NRC061CLJP- PAGE 2 OF 7 REV..0 P1.DOC
JPM TITLE: TRANSFER PRESSURIZER HEATER GROUP 12 TO JPM NUMBER:
BACKUP POWER NRC061CLJP-P1 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Reference procedure step. 1.1 Reads Caution and Note.
Cue: Another Operator has been assigned to monitor the loading of Bus G 480V transformer.
1.2 Recognizes that off-site power is available and goes to Section 6.4.1.c.
Step was: Sat: ______ Unsat _______*
- 2. Place control switch for heater 2.1 Goes to or calls the control room to group 12 in the OFF position. check the position of the control switch for heater group 12.
Cue: The control switch for heater group 12 is in the OFF position and the green light is ON.
Step was: Sat: ______ Unsat _______*
- 3. Verify that heater group 12 3.1 Locates the normal breaker for heater normal breaker 52-13D-6 is group 12 on load center 13.
open.
3.2 Verifies that the breaker is open. **
Note: If breaker is closed due to plant conditions, Cue examinee that breaker is open.
Step was: Sat: ______ Unsat _______*
4.2 Places the control power toggle switch in the OFF position. **
Step was: Sat: ______ Unsat _______*
NRC061CLJP- PAGE 3 OF 7 REV..0 P1.DOC
JPM TITLE: TRANSFER PRESSURIZER HEATER GROUP 12 TO JPM NUMBER:
BACKUP POWER NRC061CLJP-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 5. Check heater group 12 backup 5.1 Locates the heater group 12 backup breaker 52-1G-72 open. breaker.
5.2 Checks that the breaker is open. **
Step was: Sat: ______ Unsat _______*
Cue: You may open the cabinet.
6.2 Verifies that the knife switch is open. **
Cue: The knife switch is open.
Step was: Sat: ______ Unsat _______*
- 7. Verify that both white potential 7.1 Locates the manual transfer switch on lights on the manual transfer the wall next to the 52-1G-72 breaker.
switch are not lit.
Note: Since the normal breaker is available, a white light may be ON.
7.2 Observes that neither white light is ON.
Cue: Both lights are OFF.
Step was: Sat: ______ Unsat _______*
NRC061CLJP- PAGE 4 OF 7 REV..0 P1.DOC
JPM TITLE: TRANSFER PRESSURIZER HEATER GROUP 12 TO JPM NUMBER:
BACKUP POWER NRC061CLJP-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 8. Move the transfer switch down to **********************************
the backup (vital bus) position. Cue: The Shift Foreman has assigned another operator to complete all required seal valve change forms.
8.1 Removes seal. (Simulates.)
8.2 Positions the switch to the backup supply. **
Step was: Sat: ______ Unsat _______*
- 9. Rack in or check racked in 52-1G- 9.1 Racks in or checks racked in 52-1G-
- 72. 72.
Cue: Breaker is Racked In.
Step was: Sat: ______ Unsat _______*
backup breaker.
Step was: Sat: ______ Unsat _______*
- 11. Verify the D.C. Charging Power 11.1 Locates the D.C. charging power Switch for heater group 12 switch on the lower front of 52-1G-72.
backup breaker (52-1G-72) is on and springs charged.
11.2 Verifies the following:
- CHARGING POWER switch in the ON position **
- SPRINGS CHARGED flag displayed Step was: Sat: ______ Unsat _______*
NRC061CLJP- PAGE 5 OF 7 REV..0 P1.DOC
JPM TITLE: TRANSFER PRESSURIZER HEATER GROUP 12 TO JPM NUMBER:
BACKUP POWER NRC061CLJP-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 12. Notify the control room of the 12.1 Notifies the control room that heater status of heater group 12. group 12 has been transferred to the backup power supply.
Cue: The Control Operator will complete the procedure and energize heater group 12.
Step was: Sat: ______ Unsat _______*
Stop Time: ____________
Total Time: ____________ (Enter total time on the cover page)
NRC061CLJP- PAGE 6 OF 7 REV..0 P1.DOC
JPM NUMBER:
NRC061CLJP-P1 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is in MODE 1. An electrical fault has deenergized 480VAC bus 13D. Offsite power is available.
Initiating Cue: The Shift Foreman directs you to transfer pressurizer heater group 12 to its backup power supply in accordance with OP A-4A:I, Section 6.4.
Task Standard: Pressurizer heater group 12 has been transferred to the backup power supply in accordance with OP A-4A:I.
NRC061CLJP- PAGE 7 OF 7 REV..0 P1.DOC
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP A-4A:I NUCLEAR POWER GENERATION REVISION 24 DIABLO CANYON POWER PLANT PAGE 1 OF 13 OPERATING PROCEDURE UNIT TITLE: Pressurizer - Make Available 1
INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This procedure provides direction for making the pressurizer and its associated instrumentation and control systems available in order to properly fill and vent the Reactor Coolant System (RCS) as specified in OP A-2:I.
1.2 Instructions are provided for making individual pressurizer heater groups available after maintenance at power.
1.3 Instructions are provided for placing individual spray valves in service after maintenance at power.
- 2. DISCUSSION 2.1 The basis of this procedure is to provide instructions for making the pressurizer heaters available from both the normal and backup power supplies, and returning to the normal power supply from the backup power supply.
2.2 Instructions are also provided for placing extra pressurizer heaters in service during normal plant operation. This is primarily utilized for equalizing boron in the RCS, or during unit ramps, or in preparation for a clearance.
2.3 The procedure instructions address six separate evolutions as follows:
2.3.1 Section 6.1 - Pressurizer - Make Available 2.3.2 Section 6.2 - Pressurizer Heaters - Make Available 2.3.3 Section 6.3 - Pressurizer Heaters - Make Individual Heater Groups Available 2.3.4 Section 6.4 - Pressurizer Heaters - Make Available from Backup Power Supply 2.3.5 Section 6.5 - Pressurizer Heaters - Return to Normal Power Supply from Backup 2.3.6 Section 6.6 - Placing Backup Heaters in Service and Shutdown Proportional Heaters 2.3.7 Section 6.7 - Returning to Proportional Heaters Only 2.3.8 Section 6.8 - Returning RCS-1-PCV-455A to Service After Maintenance at Power 2.3.9 Section 6.9 - Returning RCS-1-PCV-455B to Service After Maintenance at Power rad2BE28.Doc 02 0515.1353
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP A-4A:I DIABLO CANYON POWER PLANT REVISION 24 PAGE 2 OF 13 TITLE: Pressurizer - Make Available UNIT 1
- 3. RESPONSIBILITIES 3.1 Operations personnel are responsible for the performance of the steps described in this procedure.
- 4. PREREQUISITES 4.1 The following systems should be in service as applicable to the tasks being performed.
4.1.1 Instrument Air System 4.1.2 Plant Electrical System 4.1.3 Pressurizer Relief Tank 4.2 Pressurizer System Alignment Verification Checklist has been completed.
- 5. PRECAUTIONS AND LIMITATIONS 5.1 When placing instrumentation in service, only the root valves are operations' responsibility. Contact maintenance to cut in, fill and vent instrumentation as required.
5.2 The low pressurizer level automatic trip (<17%) for pressurizer heater groups 1-2 and 1-3 is defeated when the heaters are on vital backup power.
5.3 An SI Signal trips the pressurizer heater groups backup (vital) power supply and will prevent reenergizing the heaters from backup source until SI is reset.
NOTE: The following step is posted on a lamicoid at Pressurizer Heater Distribution Panel 11 (PNPH 11).
5.4 Maintain no more than 5 of the 6 Group 11 heater breakers closed at a time due to inadequate fuse rating for the full heater group.Ref 7.1/7.2/7.3/7.6 5.5 Review the following Technical Specification (Tech Spec/ECG) Items:
5.5.1 TS 3.3.3 and ECG 7.8 - Accident Monitoring Instrumentation 5.5.2 TS 3.4.10 - Pressurizer Safety Valves - Operating 5.5.3 TS 3.4.9 - Pressurizer 5.5.4 TS 3.4.11 - Pressurizer Relief Valves (PORVs) and Block Valves 5.5.5 TS 3.4.12 - Overpressure Protection Systems 5.5.6 ECG 7.3 - RCS Safety Valves -Shutdown 5.6 Consider potential changes in reactivity that could occur due to actions taken in this procedure, and perform a reactivity brief if required by the Reactivity Management Program.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP A-4A:I DIABLO CANYON POWER PLANT REVISION 24 PAGE 3 OF 13 TITLE: Pressurizer - Make Available UNIT 1 5.7 480V vital bus loading is a concern when transferring loads that are not normally connected to the bus (i.e. pressurizer heaters, fire pumps, TSC and Spent Fuel Pool pumps).Ref 7.5 5.7.1 All three 480v vital transformers have the potential to be loaded beyond normal continuous rating.
5.7.2 During abnormal or emergency conditions the 480V vital transformers can be loaded to 106% or 113% of rated for short periods of time.
- a. PK16-22, PK17-22 and PK18-22 provide time and load restrictions for operating beyond the continuous rating of the transformers.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP A-4A:I DIABLO CANYON POWER PLANT REVISION 24 PAGE 8 OF 13 TITLE: Pressurizer - Make Available UNIT 1 6.3.4 Pressurizer Heater Group 14 - Make Available
- a. Verify heater group 14 control switch is in the OFF position.
- b. Verify racked in and open breaker 52-13E-5.
- c. Verify heater group 14 control transfer relay 43X-3E-5 is RESET.
- d. Verify DC control power toggle switch for heater group 14 is ON.
- e. Check heater group 14 control switch green and white lights are on.
- f. When ready for automatic operation, place heater group 14 control switch in AUTO.
CAUTION: Monitor the load on 480V Vital Bus/Transformer when transferring pressurizer heaters to the backup power supply. Pressurizer heaters ON and CFCUs in FAST speed could result in exceeding transformer normal rated load.Ref 7.5 NOTE: RED tick marks on transformer MW meter face indicate normal continuous rating value.
6.4 Pressurizer Heaters - Make Available from Backup Power Supply 6.4.1 IF off-site power is available to energize the pressurizer heaters from the back up power supply, THEN go to step 6.4.1c below; OR IF off-site power is not available (diesels supplying vital busses) to energize the pressurizer heaters from the back up power supply, THEN perform the following:
- a. Select the backup power supply to be used (vital Bus G for heater group 12 or vital Bus H for heater group 13), based on the bus with the lowest load indicated on the diesel.
- b. Determine if loads must be stripped from the selected vital bus.
- 1. IF the bus load is <2.6 MW, THEN go to step 6.4.1c below, it will not be necessary to strip any loads.
rad2BE28.Doc 02 0515.1353
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP A-4A:I DIABLO CANYON POWER PLANT REVISION 24 PAGE 9 OF 13 TITLE: Pressurizer - Make Available UNIT 1 CAUTION: Any safety injection signal must be reset before loads can be stripped and before the heaters can be energized. Reset only if applicable reset criteria is met in the specific Emergency Operating Procedures.
- 2. IF the bus load is >2.6 MW, THEN strip some load using the criteria below:
a) IF all containment fan coolers are running and average containment air temperature is below 120°F, THEN shut down fan cooler 1-3, 1-4 or 1-5, as applicable.
b) IF all three component cooling water pumps are running, THEN one may be shut down. (Either 1-2 or 1-3, as applicable.)
c) IF the ECCS pump shutdown criteria in the applicable Emergency Operating Procedure is met, THEN the following may be shut down as applicable.
- 1) SI Pump 1-2
- c. Energize the heaters as follows:
- 1. Place the control switch for the selected heater group (12 or 13) to the OFF position and check the green light on.
- 2. Verify that the selected heater group normal breaker is open:
a) 52-13D-6 for heater group 12, (480V bus 13D) b) 52-13E-2 for heater group 13,( 480V bus 13E)
- 3. Place the D.C. Control Power Switch for the selected heater group normal breaker in the OFF position (located at Load Center 13 D or E).
- 4. Check the selected heater group backup breaker open:
a) 52-1G-72 for heater group 12, (vital bus room G).
b) 52-1H-74 for heater group 13, (vital bus room H).
- 5. Check open the D.C. Control Power Knife Switch for the selected heater group backup breaker (located above the vital breaker).
- 6. Verify that both white potential lights on the manual Pressurizer Heater Transfer Switch are not lit.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP A-4A:I DIABLO CANYON POWER PLANT REVISION 24 PAGE 10 OF 13 TITLE: Pressurizer - Make Available UNIT 1
- 7. Move the manual Pressurizer Heater Transfer Switch down to the backup (VITAL) bus position.
a) Fill out the Sealed Component Change Form in accordance with OP1.DC20.
- 9. Close the D.C. Control Power Knife Switch for the selected heater group backup breaker (located above the vital breaker).
- 10. Verify the D.C. Charging Power Switch for the selected heater group backup breaker is in the ON position (located on the lower front of the vital breaker) and springs are charged.
CAUTION: The pressurizer heater group breaker auto trip on low pressurizer level is defeated when heaters are on backup power supply. Manually turn heaters OFF if pressurizer level drops below 17%.
- 11. Place the control switch for the selected heater group in the ON position in the Control Room.
NOTE: The indicating lights for this group will not illuminate since they are associated with the normal power supply breaker position.
- 12. Verify that the heaters are energized by observing the individual wattmeter for the selected heater group.
- 13. If the selected heater group does not energize as indicated by the associated watt meter, manually close breaker as follows:Ref.7.4 a) Verify the control switch on CC1 is selected to AUTO.
b) Verify closing springs are charged (charging the closing springs electrically requires the local DC knife switch above the breaker to be closed and the toggle switch on the breaker to be in the "ON" position).
c) Pull up on the local close lever.
- 14. Verify that the diesel generator is not overloaded by referencing the capability curve in OP J-6B.
- 15. Verify 4KV / 480V XFMR HIGH SIDE MWATTS are less than or equal to the red tick mark on meter face.
a) IF transformer Megawatts are greater than red tick mark, THEN refer to associated "480V BUS" AR PK for guidance on reducing loads on the 480V vital bus.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER OP A-4A:I DIABLO CANYON POWER PLANT REVISION 24 PAGE 11 OF 13 TITLE: Pressurizer - Make Available UNIT 1 6.5 Pressurizer Heaters - Return to Normal Power Supply from Backup 6.5.1 To energize pressurizer heaters from the normal power supply after being energized from the backup power supply proceed as follows:
- a. Place the control switch for the selected heater group (12 or 13), to the OFF position.
- b. Verify that the selected heater group backup breaker is open
- 1. 52-1G-72 for heater group 12, (480 V vital bus room G).
- 2. 52-1H-74 for heater group 13), (480 V vital bus room H).
- c. Open the D.C. Control Power Knife Switch for the selected heater group backup breaker (located above the vital breaker).
- d. Check the selected heater group normal breaker OPEN,
- 1. 52-13D-6 for heater group 12, (480V 13D)
- 2. 52-13E-2 for heater group 13, (480V 13E)
- e. For heater group 13 only, place 480V Transformer THH10 fan control pad in AUTO. (Located in 480V Bus H room.)
- 1. Check AUTO/ON light is on (amber.)
- f. Verify the D.C. Control Power Cut Out Switch for the selected heater group normal breaker is in the OFF position. (Upper section of 480V Bus 13D OR 13E).
- 1. 52-13D-6 if heater group 12 is being transferred from backup to normal.
- 2. 52-13E-2 if heater group 13 is being transferred from backup to normal
- g. Verify that both white potential lights on the manual Pressurizer Heater Transfer Switch are not lit, (mounted on wall behind vital breaker.)
- h. Move the manual Pressurizer Heater Transfer Switch up to the NORMAL bus position.
- 1. Complete the Sealed Component Change Form in accordance with OP1.DC20.
- j. Place the D.C. Control Power Switch for the selected heater group normal breaker in the ON position (located at Load Center 13D or E).
rad2BE28.Doc 02 0515.1353
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJP-P2
Title:
ALIGN CHARGING PUMP SUCTION FROM RWST Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Give Cue sheet to examinee outside of Radiological Controlled Area.
The first steps deal with operations outside the RCA.
References:
U2 OP AP-8B, Control Room Inaccessibility - Hot Standby to Cold Shutdown, Rev OTSC for Rev. 15 Operating Order O-9: Manual "Seating" of Motor Operated Valves, Rev.
19.
Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2, 3, 4 Job Designation: RO/SRO Task Number: 02/004/A4.12 Rating: 3.8/3.3 AUTHOR: GARY HUTCHISON DATE: 09/18/2008 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: ALIGN CHARGING PUMP SUCTION FROM RWST JPM NUMBER:
NRC061CLJP-P2 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: Copy of OP AP-8B, Step 7.e.
Initial Conditions: A fire has occurred in the Unit 2 Control Room, forcing evacuation. A cooldown to cold shutdown has commenced from the Hot Shutdown Panel. VCT level cannot be maintained in AUTO.
Initiating Cue: The SFM directs you to align the Unit 2 charging pumps suction to the RWST, in accordance with OP AP-8B, Step 7.E. RNO.
Task Standard: Charging Pump suction has been aligned to the RWST.
NRC061CLJP-P2.DOC PAGE 2 OF 5 REV. 0
JPM TITLE: ALIGN CHARGING PUMP SUCTION FROM RWST JPM NUMBER:
NRC061CLJP-P2 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Opens either 8805A and/or 8805B ***********************************
supply breakers. Cue: The 480V breakers for 8805A and 8805B have not been opened.
Note: Operator must open the supply breaker(s) for the valves he will operate. If only 1 valve is operated then only that breaker step is critical.
1.1 Opens 52-2F-19 for 8805A. **
1.2 Opens 52-2G-14 for 8805B. **
Step was: Sat: ______ Unsat _______*
- 2. Opens either LCV-112B and/or Note: Operator must open the supply LCV-112C supply breakers. breaker(s) for the valves he will operate. If only 1 valve is operated then only that breaker step is critical.
Cue: The 480V breakers for LCV-112B and LCV-112C have not been opened.
2.1 Opens 52-2F-12 for LCV-112B. **
2.2 Opens 52-2G-11 for LCV-112C. **
Step was: Sat: ______ Unsat _______*
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JPM TITLE: ALIGN CHARGING PUMP SUCTION FROM RWST JPM NUMBER:
NRC061CLJP-P2 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Opens either 8805A and/or 1.1 Locates 8805A and 8805B in the 85' 8805B. pen alcove.
1.2 Engages manual handwheel and opens 8805A and/or 8805B. **
Step was: Sat: ______ Unsat _______*
- 4. Closes either LCV-112B and/or 2.1 Locates LCV-112B and LCV-112C LCV-112C. in CVCS BlenderRoom, 100'Aux Bldg.
2.2 Engages manual handwheel and closes LCV-112B and/or LCV-112C. **
Step was: Sat: ______ Unsat _______*
(Enter total time on the cover page)
Stop Time:
Total Time:
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JPM NUMBER:
NRC061CLJP-P2 EXAMINEE CUE SHEET Initial Conditions: A fire has occurred in the Unit 2 Control Room, forcing evacuation. A cooldown to cold shutdown has commenced from the Hot Shutdown Panel. VCT level cannot be maintained in AUTO.
Initiating Cue: The SFM directs you to align the Unit 2 charging pumps suction to the RWST, in accordance with OP AP-8B, Step 7.E. RNO.
Task Standard: Charging Pump suction has been aligned to the RWST.
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Control Room Inaccessibility - Hot Standby to Cold U2 OP AP-8B Shutdown REV. 15 PAGE 6 OF 35 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. INITIATE RCS Cooldown to Cold Shutdown: (Continued)
- d. Manually Open the 10% Steam d. Locally control the 10% Steam Dumps PER Dumps to achieve desired cooldown OP C-2:II to achieve the desired cooldown rate in the RCS rate.
- e. Check VCT level being maintained in e. Verify charging pump suction aligned to AUTO (unless previously aligned to RWST the RWST).
- 1) If auto makeup remains in 1) Verify 8805A or 8805B Open locally.
service, a cooldown rate of (85' Pen alcove) approximately 40°F/hr should be used if not on natural circulation. 2) Verify Closed LCV-112B or LCV-112C Modify the cooldown rate as locally. (CVCS Blender Room, 100')
necessary to stay within the VCT auto makeup capability.
- 8. VERIFY NO RETURN TO Criticality by Stop the cooldown and allow the RCS to Monitoring NI-53 and NI-54 During the heatup to return to a subcritical condition.
Cooldown PERFORM STP R-19 CAUTION: Alternate water sources will be necessary if CST level decreases to LESS THAN 10%.
REFER TO OP D-1:V.
NOTE 1: S/G levels are cold calibrated. Correct indicated level to actual level using either Figure 2 for wide range level at the HSDP or Figure 3 for the narrow range level at the DSDP.
NOTE 2: IF S/G levels are being properly maintained in automatic, THEN LCV-110, 111, 115 and 113 should be left in AUTO.
- 9. MAINTAIN S/G Levels:
- a. Verify S/G levels maintained 87% a. Ensure S/G levels maintained 65% actual actual WR level NR level.
- 1) Figure 2, LI-501, 502, 503, 504 1) Figure 3, LI-516, 526, 536, 546 at DSD at HSD panel panel.
- b. Periodically check CST level b. IMPLEMENT OP D-1:V.
GREATER THAN 10% on LI-195 (100' FHB Hallway PM-186) 02 rad8BDA0.Doc 0405.1308 Page 6 of 36
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC061CLJP-P3
Title:
DE-ENERGIZE SSPS TO BLOCK SAFETY INJECTION Examinee:
Evaluator:
Print Signature Date Results: Sat Unsat Total Time: minutes Comments:
References:
OP AP-8B, Control Room Inaccessibility - Hot Standby to Cold Shutdown, Unit 1, Rev. 16 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 5 minutes Critical Steps: 2, 4 Job Designation: RO/SRO Task Number: 07/012/A2.02 Rating: 3.6/3.9 AUTHOR: GARY HUTCHISON DATE: 08/14/08 REVIEWED BY: DATE:
TRAINING LEADER APPROVED BY: DATE:
LINE MANAGER REV. 0
JPM TITLE: DE-ENERGIZE SSPS TO BLOCK SAFETY INJECTION JPM NUMBER:
NRC061CLJP-P3 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.
Required Materials: Copy of OP AP-8B, Step 6.
Initial Conditions: Unit 1 is transitioning from HOT STANDBY to COLD SHUTDOWN from the Hot Shutdown Panel due to Control Room inaccessibility.
Initiating Cue: The Shift Foreman directs you to defeat the Low Steam Line Pressure and Low Pressurizer Pressure Safety Injections in accordance with OP AP-8B, Step 6. You are supplied with a portable phone.
Task Standard: SSPS is de-energized to inhibit Safety Injection actuation.
NRC061CLJP-P3.DOC PAGE 2 OF 4 REV.0
JPM TITLE: DE-ENERGIZE SSPS TO BLOCK SAFETY INJECTION JPM NUMBER:
NRC061CLJP-P3 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Locate PY-11 cabinet and breaker 1.1 Reads CAUTION.
PY-1115.
1.2 Locates PY-11 on the 115 area H, battery charger room 1.
1.3 Opens the panel door and locates breaker PY-1115.
Step was: Sat: ______ Unsat: _______*
- 2. Open breaker PY-1115. 2.1 Opens breaker PY-1115. **
Step was: Sat: ______ Unsat: _______*
- 3. Locate PY-14 cabinet and breaker 3.1 Locates PY-14 on the 115, Area H, PY-1418. battery charger room 3.
3.2 Opens the panel door and locates breaker PY-1418.
Step was: Sat: ______ Unsat: _______*
- 4. Open breaker PY-1418. 4.1 Opens breaker PY-1418. **
4.2 Notifies SFM that OP AP-8B, Step 6 is complete.
Step was: Sat: ______ Unsat: _______*
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRC061CLJP- PAGE 3 OF 4 REV.0 P3.DOC
JPM NUMBER:
NRC061CLJP-P3 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is transitioning from HOT STANDBY to COLD SHUTDOWN from the Hot Shutdown Panel due to Control Room inaccessibility.
Initiating Cue: The Shift Foreman directs you to defeat the Low Steam Line Pressure and Low Pressurizer Pressure Safety Injections in accordance with OP AP-8B, Step 6. You are supplied with a portable phone.
Task Standard: SSPS is de-energized to inhibit Safety Injection actuation.
NRC061CLJP- PAGE 4 OF 4 REV.0 P3.DOC
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
Control Room Inaccessibility - Hot Standby to Cold U1 OP AP-8B Shutdown REV. 16 PAGE 4 OF 34 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Appendix H will NOT be implemented without the approval of the site emergency coordinator.
- 4. VERIFY All CRDM Fans - RUNNING START all fans and ensure their dampers (CRDM cabinet located adjacent to are open.
MCC 12J):
- Verify Dampers Open for Running IF CRDM cooling fans are NOT in Fans operation due to loss of nonvital power, THEN Implement Appendix H to reenergize the nonvital buses if desired by the SFM and emergency operations coordinator.
CAUTION: All indicators at the HSDP are susceptible to damage and may not be reliable during a Control Room or CSR fire. REFER TO Appendix A for alternate indication if the HSDP indication does not appear to be functioning correctly. The SPDS or PPC displays in the TSC may provide additional information.
NOTE: If using alternate PZR Level indication at the DSDP, convert indicated level to actual level using Figure 1.
- 5. ESTABLISH PZR Level 50%:
- a. Slowly adjust PZR level to 50%
actual level
- b. During RCS cooldown ensure PZR b. Suspend the RCS cooldown until PZR level level does not drop below 22% can be maintained GREATER THAN 22%
actual level actual level.
CAUTION: AUTO and MANUAL SI is NOT available with PY-1115 and PY-1418 OPEN.
Deactivation is a violation of the Technical Specification and must be approved by a senior reactor operator. This action is authorized pursuant to 10 CFR 50.54(x) and requires a one (1) hour nonemergency report to the NRC per 10 CFR 50.72. Refer to XI1.ID2.
- 6. DEFEAT Lo Stml Press And Low PZR Press SI:
- a. Assign an operator with a means of communication to remain near PY-1115 and PY-1418 whenever the breakers are open
- THIS STEP CONTINUED ON NEXT PAGE -
02 rad0C963.Doc 0405.1303 Page 4 of 35
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
Control Room Inaccessibility - Hot Standby to Cold U1 OP AP-8B Shutdown REV. 16 PAGE 5 OF 34 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. DEFEAT Lo Stml Press And Low PZR Press SI: (Continued)
- 1) Train A Output Cab, PY-1115
- 2) Train B Output Cab, PY-1418
- 7. INITIATE RCS Cooldown to Cold Shutdown:
- a. Begin recording cooldown data approximately every 30 minutes on Attachment 6.1 (Form 69-20682)
- b. Maintain RCS temp and press within operating band of Figure 4 using PI-406 and TI-406 (DSD panel)
- c. If an RCP is in operation, limit cooldown rate to LESS THAN 100°F/hr. If performing a natural circulation cooldown limit cooldown rate to LESS THAN 25°F/hr. (Use TI-406 cold leg/hot leg avg at the DSP Panel)
- d. Manually Open the 10% Steam d. Locally control the 10% Steam Dumps PER Dumps to achieve desired cooldown OP C-2:II to achieve the desired cooldown rate in the RCS rate.
- e. Check VCT level being maintained in e. Verify charging pump suction aligned to AUTO (unless previously aligned to RWST the RWST).
- 1) If auto makeup remains in 1) Verify 8805A or 8805B Open locally.
service, a cooldown rate of (85' Pen alcove) approximately 40°F/hr should be used if not on natural circulation. 2) Verify Closed LCV-112B or LCV-112C Modify the cooldown rate as locally. (CVCS Blender Room, 100')
necessary to stay within the VCT auto makeup capability.
02 rad0C963.Doc 0405.1303 Page 5 of 35
Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 1 Op-Test No.: L061C-1 Examiners: Operators:
Initial Conditions: 100% Reactor power, BOL, Boron at 1182 ppm CFCU 1-2 cleared.
Turnover: High Swell warning is expected in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ODM has decided to ramp both units to 25% power at 3 MW/min. OP O-28 actions are complete. OP L-4 preparations are done, at step 6.3.3.m. Turn Pzr Backup heaters on and commence ramp.
Event Malf. No. Event Event Description and Time Line No. Type*
1 N Turn Pzr Backup Heaters ON.
2 R Ramp unit to 25% power.
3 Xmt rcs15 I Loop 1 narrow range Tcold fails high and causes rods to step in. (TS 3.3.1.E & X and 3.3.2.M) 4 Pmp ven C CFCU 11 overcurrent trip. (TS 3.6.6.C )
5 Cnv mfw6 C FCV-540 FW reg valve to S/G 14 fails open 6 mal tur1 C No Automatic turbine trip, must trip manually. (CT) 7 mal rcs3a M Small break LOCA (4) 3 minutes after turbine trip. Will require RCP Trip criteria.(CT) 8 Mal eps C 4KV Bus G differential trip on Safety Injection.
9 pmp cvc1 C Charging pump 11 doesnt auto start. (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-1__ Scenario No.: __01__ Event No.: _1 & 2___ Page _1_ of _7_
Event
Description:
__Turn on heaters and Ramp unit to 25% power Time Position Applicants Actions or Behavior RO Turns on Pzr backup heaters RO Adjusts HC-455K to open sprays and returns to Auto.
SRO Tailboard ramp to 25%
SRO Provide SRO oversight for reactivity changes RO Commence boration BOP/RO Commence ramp to 25% at 3 MW/min L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-1__ Scenario No.: __01__ Event No.: _3___ Page _2_ of _7_
Event
Description:
__ Loop 1 narrow range Tcold fails high ______
Time Position Applicants Actions or Behavior RO/BOP Diagnoses Loop Tavg failure RO Places rods in manual SRO Enters AP-5 RO Defeats Loop 1 for Tavg and T RO Withdraws or inserts rods in manual to restore Tavg SRO Refers to Tech Specs (3.3.1.E & X and 3.3.2.M)
SRO/RO Returns rod control to AUTO (as time allows)
SRO Determines bistables to be tripped SRO Notifies I&C to investigate L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-1__ Scenario No.: __01__ Event No.: _4___ Page _3_ of _7_
Event
Description:
__CFCU 11 Overcurrent trip ____________________
Time Position Applicants Actions or Behavior RO/BOP Diagnoses CFCU 11 has tripped SRO Refers to PK01-21 CONTMT FAN CLRS BOP/RO Starts additional CFCU per OP H-2:I, "Containment Fan Cooler Units-Make Available and System Operation."
SRO Directs Maintenance to investigate CFCU 11 trip.
SRO REFER TO TS 3.6.6, "Containment Spray and Cooling Systems".
L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-1__ Scenario No.: __01__ Event No.: _5_ Page _4_ of _7_
Event
Description:
__FCV-540 fails open _______________________
Time Position Applicants Actions or Behavior RO/BOP Diagnoses FCV-540 is fully open.
RO/BOP Attempts to close FCV-540 in manual. Reports no success in isolating FCV-540.
SRO Directs manual reactor trip.
RO Trips Reactor.
L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-1__ Scenario No.: __01__ Event No.: _6 _ Page _5_ of _7_
Event
Description:
__ NO Automatic Turbine trip _____________________________
Time Position Applicants Actions or Behavior SRO Enters E-0 ALL Perform immediate actions of E-0 Reactor Trip or Safety Injection RO **** Performs manual turbine trip.
ALL Will probably get Lo Stmline press Safety Injection from the turbine not automatically tripping. This will require the crew to continue in E-0.
SRO If a Safety Injection does not occur, then crew will transition to E-0.1 Reactor Trip
Response
RO Observes Pzr level is decreasing and recommends SI.
RO ACTUATES SI SRO Transitions back to E-0 from E-0.1
- Denotes Crew Critical Task L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-1__ Scenario No.: __01__ Event No.: _7, 8& 9_ Page _6_ of _7_
Event
Description:
__ Small break LOCA , 4KV Bus G diff trip, and CCP 11 doesnt auto start___
Time Position Applicants Actions or Behavior BOP Diagnoses failure of 4kV Bus G ALL **** Recognize RCP trip criteria and trips RCPs RO Implement Appendix E, ESF Auto Actions, Secondary And Auxiliaries Status
- Starts CCP 1-1 Calls for local isolation on FCV-439.
- Verify Containment Spray & MSL isolation not required,
- CHECK ECCS flow and VERIFY pump operation
- Informs SFM of CCP 1-1 failure to auto start
- Calls operator to align Battery 12 to Charger 121.
BOP Determines TDAFW pp is running (RPM shows zero due to loss of PY-16 from 4KV Bus G trip). May close FCV-37 & 38 or send out operators to throttle flow when S/G level control is required.
SRO Determines RCS not intact and recognizes procedure transition criteria met RO/BOP Places 2nd CCW heat exchanger in service, requests FCV-431 to be locally opened.
SRO Directs transition to E-1
- Denotes Crew Critical Task L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-1__ Scenario No.: __01__ Event No.: __ Page _7_ of _7_
Event
Description:
__Response to Small Break LOCA_____________________________
Time Position Applicants Actions or Behavior SRO Conducts tailboard RO Performs E-1 verifications BOP Shuts down D/Gs; returns them to Auto RO Aligns CCW cooling to RHR HXs SRO Determines transition criteria to E-1.2 met SRO Directs transition to E-1.2 RO Aligns CCW cooling to RHR HXs SRO Transitions to E-1.2 SRO Conducts tailboard RO Secures RHR pumps (if pressure increasing)
RO Places steam dumps in Steam Pressure Mode SRO Determines cooldown requirements (may commence cooldown depending on temperature at time of decision)
Terminate after C/D decision reached or Cooldown commenced L061C Scenario 1.doc Rev. 0
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES A. Crew places Pzr Backup Heaters in service and commences ramps 25% power at 3 MW/min.
B. Loop 1 Tcold fails high, causing rods to step in rapidly. Reactor operator should place rods in manual and crew will respond per OP AP-5.
C. CFCU 11 will trip on overcurrent. Another CFCU will be placed in service per AR PK01-21.
D. FCV-540 Main Feedwater Regulation valve will fail open. The crew should perform a manual Reactor trip after attempting manual control of the valve.
E. The crew enters E-0 and will transition to E-0.1. The Main Unit Turbine must be manually tripped as part of E-0 immediate actions.
F. A small break LOCA on loop 1 cold leg comes in over 5 minutes requiring the crew to perform a Safety Injection and return to EOP E-0. The RCPs should be tripped after RCS pressure goes below 1300 psig.
G. On the Safety Injection, 4KV Bus G will get a differential trip, which will remove power to Charging pumps 12 & 13. The crew must manually start Charging pump 11, which will fail to auto start on the Safety Injection Signal.
H. The crew will transition from E-0 to E-1, and then to E-1.2.
I. The scenario is terminated after the crew has transitioned to E-1.2 and the decision whether the cooldown can be started has been made.
L061C Scenario 1.doc Rev. 0
ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Init 501 100% power, BOL, CB = 1182 per Checklist
- Integrators: BA - 2 and PW -0
- Tags: CFCU 12 Setup Drill 81 Reset normal engineering values Setup Dsc ven1 act,0,0,0,d,0 Clears CFCU 12 Setup loa cws8 act,2,0,0,d,0 Starts screen wash pumps loa cws32 act,2,0,0,d,0 CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary.
Primary integrator = 0 gal, Boron = 2 gal.
Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 1182 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.
o PEN running.
o R2B blowdown flows at 90 gpm.
o Reactor trip status correct 1 (Pg 2 of Group display Mode-1).
o Operational mode correct for current conditions. 2 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
Communications systems are turned on and functional 1
If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.
2 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.
Follow menu to manually override to correct mode.
L061C Scenario 1.doc Rev. 0
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6611 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min mal tur1 act 3,0,0,d,xc3i021c main turbine auto trip failure, clears on cc3 trip sw 0 min pmp cvc1 1,0,0,0,d,0 CCP 11 doesnt start automatically 30 minutes after xmt rcs15 3,679,10,1800,c,ggo,0 Loop 1 Tcold RTD fails high ramp started 30 min after TE- pmp ven5 4,0,0,1800, CFCU 11 trip 410 > 670 F c,txmt410b(1).gt.670,0 30 min from cfcu cnv mfw6 2,1,90,1800, FCV-540 (MFW Reg valve to S/G 14) fails trip c,XV1O231G,0 open X After RX trip Drill 32 NO Action on reactor trip 5 min after turbine mal rcs3a act,4,300,300,c,jmltur1,0 Small break LOCA (4) on loop 1 cold leg trip On Safety mal eps4d act,2,0,0,c,jpplsi,0 4kv bus G differential trip Injection Signal X When requested Vlv mfw2 2,0,300,0,d,0 Locally close FCV-439.
X When requested Drill 47 Swaps Batt 12 to charger 121 X If requested Drill 97 Swaps PY-16 to backup X If requested Drill 55 Places H2 analyzers in service X If requested Vlv ccw5 2,1,150,0,d,0 Locally open FCV-431.
L061C Scenario 1.doc Rev. 0
Drl_6611.txt
- L082 NRC exam scenario #2
- glh1, 8/20/08
- all events have 30 min time delay for nrc input
- init 501
- loop 1 tcold fails high 30 min from ramp start xmt rcs15 3,679,10,1800,c,ggo,0 #txmt410b(1)
- cfcu 11 trip 30 min from rtd failure pmp ven5 4,0,0,1800,c,txmt410b(1).gt.670,0 #ochfs11
- fcv-540 fails open 30 min from cfcu trip cnv mfw6 2,1,90,1800,c,XV1O231G,0 #rfwf540
- main turbine auto trip failure, clears on cc3 trip sw mal tur1 act 3,0,0,d,xc3i021c
- 8000 gpm loca 5 minute after reactor trip mal rcs3a act,4,300,300,c,jpplp4,0
- 4kv bus g differential trip on si mal eps4d act,2,0,0,c,jpplsi,0
- prevent charging pp 11 from auto starting pmp cvc1 1,0,0,0,d,0 #ocvp11 L061C Scenario 1.doc Rev. 0
DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 100 %
GROSS GENERATION: 1198 MWe NET GENERATION 1155 MWe DAYS AT POWER: 10 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: Green PROTECTED EQUIPMENT: Train A/B, Bus F,G,&H, Prot. Sets I, II,III,IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:
ACTIVE SHUTDOWN TECH SPECS / ECGS:
CFCU 12 cleared for Bearing Replacement (info only)
TURNOVER ITEMS:
- High Swell warning is expected in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ODM has decided to ramp both units to 25% power at 3 MW/min. OP O-28 actions are complete, camera is not available at intake. OP L-4 preparations are done, at step 6.3.3.m. with the exception of placing Pzr Backup Heaters in service.
OPERABILITY ITEMS:
- None PRIORITY ITEMS FOR NEXT SHIFT:
- Place Pzr Backup Heaters in service and ramp unit to 25% power.
ANNUNCIATORS IN ALARM
- None L061C Scenario 1.doc Rev. 0
SHIFT FOREMAN TURNOVER COMMENTS:
- 1. Reactivity management:
- a. Time in core life: BOL
- b. Power History: At 100%
- c. Boron concentration is 1182 ppm from a sample taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.
- d. Borate 40 gallon batches every 20 minutes for first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of ramp per Reactor Engineering.
- e. Ramp at 3 MW/min to 280 MW.
- f. Leave rods in auto, go to manual if needed to maintain I with +/- 2% of target.
- 2. No one is in Containment, no entries are expected
- 3. U-2 is operating at 100% power COMPENSATORY MEASURES:
None CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.
L061C Scenario 1.doc Rev. 0
Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 2 Op-Test No.: L061C-2 Examiners: Operators:
Initial Conditions: 75% Reactor power, MOL, Boron at 848 ppm ASW pp 12 cleared.
Turnover:
Event Malf. No. Event Event Description and Time Line No. Type*
1 Vlv pzr5 C PCV-456 Pzr PORV fails open, must isolate using block valve. (TS 3.4.11 )
(CT) 2 Mal R - CO Ramp unit to 50% power due to FWP 11 high vibration.
mfw2a C - BO 3 Xmt mfw37 I LT-459 Pzr level channel fails to 10% (TS 3.3.1.M, 3.3.3.F, 3.3.4)
N - CO Restores letdown flow.
N -BOP 4 Mal rcs4c M S/G 13 tube leak ramps to 400 gpm (CT) 5 Pmp asw1 C ASW pp 11 trips on overcurrent on reactor trip, requires x-tie with U-2. (CT) 6 Cnv mss C PCV-21 fails open after RCS cooldown complete. Transition to ECA 3.1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 2.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-2__ Scenario No.: __02__ Event No.: _1___ Page _1_ of _6_
Event
Description:
__PCV-456 fails open _________________________________________________
Time Position Applicants Actions or Behavior BOP Diagnose PORV PCV-456 has opened partially.
RO Determine that PORV PCV-456 should be closed based on Pressurizer Pressure.
SRO Direct BOP to close PORV PCV-456.
BOP Diagnose that PORV PCV-456 will not close and report to SRO SRO Direct BOP to close PORV Block Valve 8000C.
BOP Closes PORV Block valve 8000C. ****
RO Acknowledge alarm PK 05-20, input 1211, PZR Relief/Safety Valve OPEN SRO Responds per Annunciator Response Procedure PK 05-20.
- Refers to Tech Spec 3.4.11B (Determines 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> close block valve and remove power from block valve, also 72 hrs to restore PORV.)
- May refer to AP-13, Malfunction of Reactor pressure Control System.
- Denotes Critical Task L061C Scenario 2.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-2__ Scenario No.: __02__ Event No.: _2___ Page _2_ of _6_
Event
Description:
__ FWP 11 high vibration __________________________________
Time Position Applicants Actions or Behavior SRO Respond to PK09-13 MAIN FEEDWATER PUMP 11 RO/BOP Determines Pump bearing vibration > 5 mils from VB4.
SRO Directs ramp to 50% with a ramp rate of 50 - 200 MW/min.
SRO Refers to OP AP-25 Rapid Load Reduction.
RO/BOP Commences ramp to 550 MW.
RO Verfies Rods inserting properly in Auto RO Turns Backup Heaters on.
BOP Verifies a CCP in service.
RO/BOP Takes charging to manual to prevent flashing in letdown system.
RO/BOP Verifies DFWCS controlling S/G levels RO Commences boration SRO Provides Reactivity Oversight.
BOP Trips MFW pp 11 when unit load at 550 MW.
L061C Scenario 2.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-2__ Scenario No.: __02__ Event No.: _3_ Page _3_ of _6_
Event
Description:
__LT-459 Pzr level channel fails to 10% _______________________
Time Position Applicants Actions or Behavior SRO Diagnoses LT-459 failing low BOP Takes manual control of PZR level control SRO Enters AP-5 SRO Selects B/U channel for control SRO Re-establishes letdown SRO Refers to Tech Specs 3.3.1.M, 3.3.3.F, 3.3.4 SRO Determines bistables to be tripped SRO Directs Asset Team to investigate L061C Scenario 2.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-2__ Scenario No.: __02__ Event No.: _4 & 5 _ Page _4_ of _6_
Event
Description:
__ 400 GPM S/G 13 tube leak and ASW pp 11 overcurrent trip______
Time Position Applicants Actions or Behavior SRO Responds to AR PK11-18 and/or PK11-06 SRO Diagnoses S/G tube rupture; may enter AP-3.
RO Determines leak too large to maintain Pzr level SRO Directs SI and enters E-0 ALL Perform remaining immediate actions of E-0 Reactor Trip or Safety Injection
- VERIFY reactor tripped
- VERIFY turbine tripped
- VERIFY vital 4kV buses energized
- CHECK SI - Actuated BOP/RO Implements Appendix E BOP/RO Determines ASW pp 11 has tripped on overcurrent and Unit has no ASW flow.
BOP/RO Refers to AP-10 BOP/RO
- coordinates with U-2 to align ASW flow from U-2.
BOP/RO
- Opens FCV-601 and verifies Heat Exchanger DP increases****
SRO May directs early isolation of S/G 1-3 SRO Determines S/G 1-3 is ruptured and recognizes procedure transition criteria met ALL Implements F-0; monitors CSFSTs SRO Directs transition to E-3
- Denotes Critical Task L061C Scenario 2.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _L061C-2__ Scenario No.: __02__ Event No.: _6_ Page _6_ of _6_
Event
Description:
__ PCV-21 fails open____________________
Time Position Applicants Actions or Behavior RO/BOP Isolates S/G 13 *****
- Sets 10% steam dump to 8.67 turns RO/BOP
- Isolates S/G 1-3 MSIV RO/BOP
- Isolates AFW flow when S/G level > 6%
RO/BOP
- Isolates steam to TDAFP (close FCV-38)
SRO Determines cooldown target temperature RO Blocks Lo Stm Line Press SI RO Cools down the RCS SRO Continues with E-3 while cooling RCS to target temperature BOP Shuts down the RHR pumps RO Stabilizes RCS at target temperature BOP Checks S/G 13 pressure - Determines PCV-21 has failed open BOP
- Places PCV-21 controller in manual and decreases demand to zero BOP
- Cuts in backup air and attempts to close PCV-21 BOP
- Dispatches operators to locally isolate PCV-21 SRO Determines S/G pressure continues to decrease to LESS THAN 250 PSI above Intact S/Gs Pressure SRO Transitions to ECA 3.1 BOP Establish Instrument Air to containment (open FCV-584)
RO Turns Pzr Heaters Off.
SRO Evaluates Plant Status, RCS leakage not indicated.
Terminate scenario after ECA 3.1 step 10, Evaluation Of Plant Status
- Denotes Critical Task L061C Scenario 2.doc Rev. 0
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES A. PCV-456 Pzr PORV fails open. Operators try to close PORV, but must use block valve.
B. High Vibration alarm occurs on MFW pump 11. Responds per PK 09-13. Commences ramp to 50%
power using AP-25. RO should perform boration for the ramp.
C. LT-459, Pzr level channel fails to 10%. Crew responds per AP-5 and takes charging to manual to control pzr level. Crew should restore letdown flow after swapping to another level channel.
D. A 400 gpm tube leak occurs on S/G 13. The crew may respond per AP-3 and should perform a manual Safety Injection.
E. On the reactor trip, ASW pp 11 trips on overcurrent. Since ASW pp 12 was cleared, this will cause a complete loss of ASW. Crew should crosstie with Unit 2 per AP-10.
F. The crew should transition from E-0 to E-3 to isolate S/G 13. After completing the cooldown steps of E-3, PCV-21 (S/G 13 10% dump valve) will fail open. The crew should try to isolate the 10% dump, but will not be successful. This will require a transition to ECA 3.1.
G. The scenario is terminated after Evaluation Of Plant Status in step 10 of ECA 3.1.
L061C Scenario 2.doc Rev. 0
ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Init 511 75% power, MOL, CB = 848 per Checklist
- Integrators: BA - 0 and PW -40
- Tags: ASW pp 12 Setup Drill 81 Reset normal engineering values Loa ASW7 act,0,0,0,d,0 Place ASW pp 12 stby select switch to Ser 0219 act,0,0,0,d,0 manual CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary.
Primary integrator = 40 gal, Boron = 0 gal.
Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 848 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.
o PEN running.
o R2B blowdown flows at 90 gpm.
o Reactor trip status correct 1 (Pg 2 of Group display Mode-1).
o Operational mode correct for current conditions. 2 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
Communications systems are turned on and functional 1
If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.
2 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.
Follow menu to manually override to correct mode.
L061C Scenario 2.doc Rev. 0
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6612 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 30 minute delays btwn events to allow NRC to direct each event 5 min vlv pzr5 2,1,10,1800,d,0 PCV-456 fails open X When requested Dsc pzr3 act,0,0,0,d,0 Opens bkr for 8000c After 8000C mal mfw2a act,11,600,1800, MFW pp 11 high vibration closed c,XV2I197C,0 after ramp started xmt pzr40 3,10,10,1800, LT-459 fails to 10%
c,ggo,0 After letdown mal rcs4c act,400,300,1800, 400 gpm tube leak on S/G 13 isolation c,XV2O214G,0 After reactor trip pmp asw1 4,0,0,5,c,jpplp4,0 ASW pp 11 overcurrent trip X After RX trip PA Drill 32 NO Action on reactor trip X When requested Loa asw5 act,1,0,0,d,0 Aligns ASW 22 to U-1 After RCS cnv mss24 2,1,5,1800, PCV-21 fails open cooldown < 515 F c,tcfmtc(48).lt.515,0 X When requested Cant get to PCV-21 to isolate due to steam in area.
L061C Scenario 2.doc Rev. 0
Drl_6612.txt
- L082 scenario # 3
- glh1, 9/16/8
- init 511
- use 30 min btwn events to allow nrc control
- PORV PCV-456 fails open vlv pzr5 2,1,10,1800,d,0 #rrcp456
- mfw pp 11 hi vibration after 8000C closed mal mfw2a act,11,600,1800,c,XV2I197C,0
- lt-459 fails to 10% after ramp started xmt pzr40 3,10,10,1800,c,ggo,0 #lqm459
- sg 13 tube leak, ramps to 400 gpm after l/d iso mal rcs4c act,400,300,1800,c,XV2O214G,0
- asw pp 11 oc trip on reactor trip pmp asw1 4,0,0,5,c,jpplp4,0 #ocwasp11
- pcv-21 opens after rcs < 515 f cnv mss24 2,1,5,1800,c,tcfmtc(48).lt.515,0 #rmsp21 L061C Scenario 2.doc Rev. 0
DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 75 %
GROSS GENERATION: 900 MWe NET GENERATION 865 MWe DAYS AT POWER: 120 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: Green PROTECTED EQUIPMENT: Train A, Bus F&H, Prot. Sets I, III, IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:
- None ACTIVE SHUTDOWN TECH SPECS / ECGS:
- ASW pp 12 (TS 3.7.8) cleared for bearing replacement.
TURNOVER ITEMS:
- Unit at 75% power at request of TOC for testing of new 500KV line impedance relays. Unit was ramped to 75% power yesterday morning. Relay testing should be completed tomorrow.
OPERABILITY ITEMS:
- None PRIORITY ITEMS FOR NEXT SHIFT:
- Continue 75% power operations.
ANNUNCIATORS IN ALARM
- None L061C Scenario 2.doc Rev. 0
SHIFT FOREMAN TURNOVER COMMENTS:
- 1. Reactivity management:
- a. Time in core life: MOL
- b. Power History: At 75%
- c. Boron concentration is 848 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- d. Diluting 40 gallons every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- e. Last dilution was 30 minutes ago.
- f. I stable with in target band.
- 2. No one is in Containment, no entries are expected
- 3. U-2 is operating at 100% power COMPENSATORY MEASURES:
None CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.
L061C Scenario 2.doc Rev. 0
Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 3 Op-Test No.: L061C-3 Examiners: Operators:
Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover: PRA Status: Yellow. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. RHR pp 11 is cleared for seal repair. U-2 at 100% power.
Event Malf. No. Event Event Description and Time Line No. Type*
1 mal cvc8 C RCP seal injection filter plugs up, reducing charging flow to seals.
2 R TOC requests ramp to 900 MW at 25 MW/min 3 xmt rcs93 I NI-44 fails high, requires rods to manual. ( TS 3.3.1.D, E, S, T) 4 mal eps4c C 4KV bus F diff trip (TS 3.0.3 due to loss of both RHR pumps )
5 mal mfw2a C Both MFW pumps trip spuriously.
mal mfw2b 6 mal ppl5a M Reactor trip breakers wont open from the control room. ATWS. (CT) mal ppl5b 7 ovr C 52-hd-13 fdr for bus 13d fails to open, so 1 MG set stays in service. Crew must xv5i245o insert rods and go to FR S.1. (CT) 8 vlv afw7 C TDAFW pp 11 fcv-95 won't open automatically, crew must open at VB3. (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 3.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L061C-3 Scenario No.: 3 Event No.: 1 Page 1 of 5 Event
Description:
RCP seal injection filter plugs.
Time Position Applicants Actions or Behavior RO Diagnose RCP seal injection filter plugging.
RO Acknowledge alarm PK 04-22, input 498, RCP Seal Injection Filter 1 Delta P Hi SRO Responds per Annunciator Response Procedure PK 04-22.
- Direct RO to throttle HCV-142 as needed to control flow.
- Direct Nuclear Operator to swap seal injection filters.
- Contacts Maintenance to replace seal injection filter.
RO Reestablish seal injection flow of >8 gpm using HCV-142.
BOP Monitor RCP parameters as directed by SRO.
L061C Scenario 3.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L061C-3 Scenario No.: 3 Event No.: 2 Page 2 of 5 Event
Description:
Ramp to 900 MW at 25 MW/min Time Position Applicants Actions or Behavior SRO Receives call from TOC - Ramp to 900 MW at 25 MW/MIN.
SRO Enters AP-25 Rapid Load Reduction or Shutdown.
BOP/RO Sets up ramp on DEHC Console per SRO direction using OP C-3:III, Main Unit Turbine - At Power Operations. (May use Committed Posting for Direction)
- Places MW feedback in service.
- Set desired Ram Rate. (25MW/Min)
- Set Target to desired load. (900 MW)
- Commence ramp by Pressing GO RO Verify Control Rods inserting in Auto in response to Ramp.
RO Verifies Backup Pressurizer Heater groups are ON.
BOP/RO Verify Charging System operation is adequate.
- Verifies at Least One Charging Pump is in service.
- Controls charging in Manual as needed to prevent Letdown system flashing.
RO Performs Boration of RCS using Boration Checklist and Makeup controller.
- Set Target Batch on flow controller (as determined by SRO)
- Verify Boric Acid Flow rate set to desired flow.
- Start Boration and verify response.
L061C Scenario 3.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L061C-3 Scenario No.: 3 Event No.: 3 Page 3 of 5 Event
Description:
NI-44 fails high at 1000 MW.
Time Position Applicants Actions or Behavior RO Reports unexpected control rod motion RO Diagnoses NI-44 failure RO Places Rod Control in Manual SRO May direct RO/BOP to place Ramp on HOLD.
SRO Enters AP-5, Malfunction of Eagle 21 Protection or Control Channel.
BOP Removes NI-44 from service per Attachment 4.1 RO Restores Tavg to Tref SRO Provides appropriate reactivity oversight SRO Refers to TS 3.3.1.D, E, S, T RO Returns Rod control to Automatic when Tavg/Tref is within 1F.
RO/BOP Resumes ramp (as time permits)
L061C Scenario 3.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L061C-3 Scenario No.: 3 Event No.: 4 Page 4 of 5 Event
Description:
4KV bus F diff trip Time Position Applicants Actions or Behavior BOP Diagnoses failure of 4kV Bus H RO Acknowledges multiple alarms - Determines PK 16-17 is highest priority, 4 kV bus H UV.
SRO Responds per Annunciator response Procedure PK16-17 (PK16-16 and 16-22)
- Determines AP-27, Loss of Vital 4 kV and/or 480V Bus is appropriate procedure to address event.
SRO Enters AP-27, Loss of Vital 4 kV and/or 480V Bus.
BOP Manually starts alternate equipment as required:
- CFCU 12 or 15 BOP Assigns Nuclear operators to :
- Transfer Batt 13 to charger 131 per OP J-9:II
- Transfer PY-15 to backup per OP J-10:VII
- Diesel Fuel Transfer PP 01 to backup per OP O-13.
- Comm. Room Power to backup per OP O-13.
- Control Room Vent Pwr Panel A-2 switch to backup per OP O-13.
BOP Positions PCV-456 to close BOP Shuts down D/G 1-1 SRO Refers to Tech Specs, determines unit in TS 3.0.3 due to a loss of both RHR pumps.
L061C Scenario 3.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L061C-3 Scenario No.: 3 Event No.: 5, 6, 7, 8 Page 5 of 5 Event
Description:
Feed Pumps trip / ATWS Time Position Applicants Actions or Behavior BOP Reports to SRO both MFW pumps are tripped, no main Feedwater flow is available.
SRO Directs a manual reactor trip.
RO/BOP Recognizes Reactor Trip Initiate without Actuation.
SRO SRO Directs RO and BOP to Perform Immediate Actions RO Attempts a manual Reactor Trip - Reports Reactor did not trip BOP Attempts to open 13D/13E breakers - Reports 13D will not open.
RO Manually inserts control rods ****
BOP Trips main turbine ****
SRO Enters E-0, Reactor Trip or Safety Injection
- Determines Reactor will not trip.
- Determines Transition to FR-S.1Response to Nuclear Power Generation ATWS is required.
SRO Enters FR-S.1, Response to Nuclear Power Generation ATWS BOP Dispatch personnel to open Reactor Trip Breakers Locally.
BOP Diagnoses that AFW Pump 1-1 has failed to start.
- Starts TDAFW pump ****
RO Initiates emergency boration BOP Manually closes CVI valves RO Checks Reactor is subcritical on Intermediate & Power Range channels.
SRO Requests STP R-19 Calculation for SDM SRO Transitions back to E-0 SRO Transitions to E-0.1 Terminate scenario at step 8 of E-0.1
- Denotes critical task L061C Scenario 3.doc Rev. 0
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES A. RCP seal injection filter plugs up, reducing charging flow to seals. Crew refers to PK 04-22 and swaps to other filter.
B. TOC requests ramp down to 900 MW at 25 MW/min.
C. At 1000 MW, a Loop 3 Tcold RTD fails high, which causes rods to drive in. Rod control is taken to manual and crew refers to AP-5 for actions.
D. 4KV Bus F de-energizes due to a differential trip. Crew refers to AP-27 for actions.
E. Both MFW pumps trip spuriously. Crew should try to manually trip the reactor. Crew goes from E-0 to FR S.1 since 52-HD-13 breaker will not open from the control room.
F. Turbine driven AFW pp 11 must be manually started from VB3.
G. Crew transitions back to E-0 from FR S.1 and then to E-0.1 for Reactor trip recovery.
H. Terminate scenario at step 8 of E-0.1.
L061C Scenario 3.doc Rev. 0
ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Init 510 100% power, MOL, CB = 782 per Checklist
- Integrators: BA - 0 and PW - 40
- ser 0219 act,0,0,0,d,0 alarm off to simulate Breaker racked out CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary.
Primary integrator = 40 gal, Boron = 0 gal.
Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 782 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.
o PEN running.
o R2B blowdown flows at 90 gpm.
o Reactor trip status correct 1 (Pg 2 of Group display Mode-1).
o Operational mode correct for current conditions. 2 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
Communications systems are turned on and functional.
1 If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.
2 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.
Follow menu to manually override to correct mode.
L061C Scenario 3.doc Rev. 0
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6607 After SRO reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min mal pp15a act,3,0,0,d,0 ATWS (13D & E Available) mal pp15b act,3,0,0,d,0 0 min ovr xv5i245o act,0,0,0,d,0 52-hd-13 fdr for bus 13d fails to open 0 min vlv afw7 1,0,0,0,d,xv3i219 tdafwp fcv-95 won't open automatically, clears when c/s taken to open 3 min mal cvc8 act 100,120,1800,d,0 SEAL INJECTION FILTER 11 PLUGGED X When requested Report Seal Injection Filter 11 dP is pegged high.
X Aux Bldg watch loa cvc3 act,1,30,0,d,0 valve in seal injection filter 12 X Aux Bldg watch loa cvc2 act,0,30,0,d,0 valve out seal injection filter 11 X When desired CALL AS TOC Require Ramp to 900 Mw Net. Start ramp within 5 minutes, request 25 MW/min ramp rate.
At 1000 MW mal nis6d act,200,120,0, NI-44 fails high c,smss.lt.1000,0 After NI-44 failure mal eps4e act 2,0,1800, c,,jmnis6d 4KV bus H diff trip X When requested Report burnt insulation smell from 4KV bus H room.
X When reqested Drill 96 transfers PY-15 to backup X When requested Drill 48 swap batt 13 -> chrg 131 After Bus H failure mal sei1 act,0.29,10,1800, 0.29 earthquake c,jmeps4e,0 On Siesmic mal mfw2a act 25,5,10,c,jmlsei1, both MFW pp's trip mal mfw2b act 25,5,10,c,jmlsei1, X When requested mal pp15a clr Locally opens Train A & B RTBs mal pp15b clr L061C Scenario 3.doc Rev. 0
Drl_6607.txt
- L061C Scenario 3 NRC simulator exam
- glh1, 9/18/08
- init 510 100% mol
- clears rhr pp 11
- open dc knife sw - loa rhr9 act,0,0,0,d,0 #jrocrhr1
- clear dc uv alarm - ser 0219 act,0,0,0,d,0 #alm337c
- all time delays 30 min to allow NRC to direct activation
- CVC8 SEAL INJECTION FILTER PLUGGED mal cvc8 act 100,120,1800,d,0
- use loa cvc3 act,1,30,0,d,0 to valve in seal inj filter 12
- use loa cvc2 act,0,30,0,d,0 to valve out seal inj filter 11
- Call as system dispatcher for ramp to 900 MW at 25 MW/min
- NI-44 fails high at 1000 MW mal nis6d act,200,120,0,c,smss.lt.1000,0
- 4KV bus h diff trip 30 min after ni-44 failure mal eps4e act 2,0,1800,c,jmnis6d,0
- use drill 48 to swap batt 13 -> chrg 131
- 30 min after bus diff -> Seismic of 0.29 g ,ATWS mal sei1 act,0.29,10,1800,c,jmeps4e,0 mal ppl5a act 3,0,0,d,0 mal ppl5b act 3,0,0,d,0
- both MFW pp's trip on seismic mal mfw2a act 25,5,10,c,jmlsei1, mal mfw2b act 25,5,10,c,jmlsei1,
- 52-hd-13 fdr for bus 13d fails to open ovr xv5i245o act,0,0,0,d,0 #vb5100e
- tdafwp fcv-95 won't open automatically, clears when c/s taken to open vlv afw7 1,0,0,0,d,xv3i219o #rmsf095 L061C Scenario 3.doc Rev. 0
DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 100 %
GROSS GENERATION: 1198 MWe NET GENERATION 1155 MWe DAYS AT POWER: 120 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: YELLOW - RHR PP 1-1 MOW PROTECTED EQUIPMENT: Train B, Buses H & G, Prot. Sets II,III,IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Midway #3 line cleared AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:
- None ACTIVE SHUTDOWN TECH SPECS / ECGS:
- RHR PP 1-1 -pump seal repair. T.S 3.5.2.A - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Due in 62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br />.
TURNOVER ITEMS:
- RHR PP 1-1 was cleared 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago to repair a pump seal. It is expected to be returned to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
OPERABILITY ITEMS:
- None PRIORITY ITEMS FOR NEXT SHIFT:
- RHR PP 1-1 pump seal repairs.
ANNUNCIATORS IN ALARM
- None L061C Scenario 3.doc Rev. 0
SHIFT FOREMAN TURNOVER COMMENTS:
- 1. Reactivity management:
- a. Time in core life: MOL
- b. Power History: 100%
- c. Boron concentration is 782 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- d. Diluting 40 gallons every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- e. Last dilution was 30 minutes ago
- f. I is stable
- 2. No one is in Containment, no entries are expected
- 3. U-2 is operating at 100% power COMPENSATORY MEASURES:
None CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.
L061C Scenario 3.doc Rev. 0
Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: BU Op-Test No.: LO61C-BU Examiners: Operators:
Initial Conditions: 4% Reactor power, with Main Feedwater in service.
Turnover: CFCU 14 high vibration alarm occurred at 4 % power. Investigation showed dirty alarm contacts, which have been cleaned and CFCU 1-4 has been restarted. At OP L-3 step 6.26, ready to continue rod pull to 8% power. Continue with plant startup and parallel main generator, then increase power to 30%.
Event Malf. No. Event Event Description and Time Line No. Type*
1 R Increase power to 8% using rods.
2 Pmp ccw2 C CCW pp 12 overcurrent trip at 6 % power. (TS 3.7.7.A) 3 Ovr C 8149C ground, causes letdown isolation . (TS 3.6.3.A )
xv2i214c N Restores letdown with another orfice valve.
Ser 1147 C Ground alarm on DC bus 11 4 Cnh pzr2 I PCV-455B (Pzr Spray Valve Loop 2 controller) fails high in auto. (CT) 5 Mal mss2b M Steam line break to S/G 12 inside containment. (CT) 6 Vlv mss8 C FCV-42 MSIV to S/G 12 fails to close automatically. (CT) 7 Mal ppl1a C Phase A train A doesnt actuate on S.I. (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario BU.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _LO61C-BU__ Scenario No.: __BU__ Event No.: _1___ Page _1_ of _7_
Event
Description:
__Pull rods to 8% power_________________________________________________
Time Position Applicants Actions or Behavior SRO Tailboard power increase to 8%
SRO Provide SRO oversight for reactivity changes RO Increase reactor power to 8% by pulling one full rod step at a time.
RO Allows SUR to return to ~zero between steps.
BOP Verify PPC mode changes to power operation.
SRO Makes PA announcement that plant is in MODE 1.
L061C Scenario BU.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _LO61C-BU__ Scenario No.: __BU__ Event No.: _2___ Page _2_ of _7_
Event
Description:
__CCW pp 12 trip_________________________________________________
Time Position Applicants Actions or Behavior SRO Respond to PK01-09 CCW Pumps BOP Starts CCW pp 13 SRO/BOP Direct Turbine Bldg watch to walkdown 4KV Bus G SRO/BOP Direct Aux Watch to inspect CCW pump 12.
SRO Refers to TS. 3.7.7.a SRO Notifies Maintenance L061C Scenario BU.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _LO61C-BU__ Scenario No.: __BU__ Event No.: _3___ Page _3_ of _7_
Event
Description:
__8149C ground causes letdown isolation ____________________
Time Position Applicants Actions or Behavior SRO Respond to PK20-22 125V DC BUS 11, 12 13 GROUND SRO Respond to PK04-21 LETDOWN PRESS / FLO TEMP RO/BOP Observes letdown flow at zero and 8149C is closed.
BOP Contact I&C to investigate RO Reduces charging to seals only SRO Directs excess letdown to be placed in service.
SRO Tailboards reactivity change for placing excess letdown in service.
BOP Notifies Rad Protection to implement SPG-3.
BOP/RO Places letdown in service per OP B-1A:IV
- 1. Place or verify the excess letdown divert valve CVCS-1-8143 in the normal or divert position as required by plant operating conditions.
- 2. Open the CCW from Excess Letdown Heat Exchanger Isolation Valve FCV-361 at VB-1..
- 3. Check Excess Letdown Pressure Control Valve HCV-123 CLOSED
- 4. Open 8166 and 8167 at VB2.
- 5. SLOWLY open HCV-123 to establish excess letdown flow. Do not exceed 190°F on TI-122, excess letdown temperature
- 6. Adjust HCV-123 as necessary for letdown flow requirements.
- 7. Reduce demand on FCV-128 while adjusting RCP seal injection flow to maintain between 8 GPM and 13 GPM per RCP using HCV-142, until HCV-142 is fully closed.
- 8. Maintain RCS inventory control using HCV-123 as applicable.
SRO Refers to T.S. 3.6.3 Containment Isolation Valves after call received that 8149C solenoid has a short causing the ground.
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Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _LO61C-BU__ Scenario No.: __BU__ Event No.: _4_ Page _4_ of _7_
Event
Description:
__Pzr Spray controller fails high _______________________
Time Position Applicants Actions or Behavior BOP/RO Diagnoses PCV-455B open due to high controller demand RO **** Takes manual control of PCV-455B controller And reduces demand to close Pzr Spray valves.
RO Turns on backup heaters to restore pressure.
SRO Contacts maintenance about PCV-455B failure.
- Dentotes critical task L061C Scenario BU.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _LO61C-BU__ Scenario No.: __BU__ Event No.: _5 & 6_ Page _5_ of _7_
Event
Description:
__ Steam line break on S/G 12 inside containment Time Position Applicants Actions or Behavior SRO Enters E-0 ALL Perform remaining immediate actions of E-0 Reactor Trip or Safety Injection
- VERIFY reactor tripped
- VERIFY turbine tripped
- VERIFY vital 4kV buses energized
- CHECK SI - Actuated BOP/RO Announces Adverse Containment Criteria met.
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Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _LO61C-BU__ Scenario No.: __BU__ Event No.: _6& 7_ Page _6_ of _7_
Event
Description:
__ Phase A components and and FCV-42 fails to close automatically ____________________
Time Position Applicants Actions or Behavior Implement Appendix E, ESF Auto Actions, Secondary And Auxiliaries Status RO
- VERIFY Phase A, Cont. Vent Isol., SI actuated properly - ****must manually align phase A Train A components
- VERIFY MFW Isol,
- Verify Containment Spray,
- MSL Isol response correct
- Must manually close FCV-42 (S/G 12 MSIV)
- CHECK ECCS flow and VERIFY pump operation
- Isolates Excess letdown (8166 & 8167)
- VERIFY two trains CCW
- Dentotes critical task L061C Scenario BU.doc Rev. 0
Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: _LO61C-BU__ Scenario No.: __BU__ Event No.: __ Page _7_ of _7_
Event
Description:
__Steam line break isolation and S.I. termination_____________________________
Time Position Applicants Actions or Behavior SCO Transitions to E-2 SCO Implements F-0; monitors CSFSTs BOP Isolates S/G 1-4
- Verify Faulted S/Gs Mn Fdwtr Isol Vlvs - CLOSED
- Verify Faulted S/Gs Blowdown Isol Vlvs - CLOSED
- Verify Faulted S/Gs 10% Steam Dump Vlv - CLOSED
- **** Verify Faulted S/Gs AFW System Control Vlvs - CLOSED
- **** Verify Steam Supply Valves from Faulted S/Gs to TD AFW Pp -
CLOSED ( Close FCV-37 )
- Verify AFW flow available to at least one intact S/G BOP REMOVE Subcooled Margin Monitor Input From S/G 1-2 SRO Checks for a ruptured S/G SRO Checks if ECCS flow should be reduced.
SCO Transitions to E-1.1 RO Resets SI RO stops all but one CCP BOP isolates charging injection RO Establishes normal charging flow Terminate scenario after normal charging established.
- Dentotes critical task L061C Scenario BU.doc Rev. 0
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES A. Crew increases power to 8% using control rods.
B. CCW pump 12 trips on overcurrent at 6.5% power. They will respond per AR PK01-09, resolving the problem by placing CCW pump 13 in service.
C. 8149C ground causes a letdown isolation. Crew responds per AR PK04-21 and places excess letdown in service.
D. Pzr Spray controller for PCV-455B fails high in auto. RO takes manual control of PCV-455B and restores pressure control..
E. A Steam line break occurs on S/G 12 inside containment. This will require a reactor trip. A safety injection will occur due to low steamline pressure.
F. On the Safety Injection, FCV-42 doesnt automatically close, and must be isolated by the operator.
G. On the Safety Injection, train A of Phase A does not actuate. The operator must align Phase A components manually.
H. The crew will transition from E-0 to E-2, and to E-1.1 to terminate S.I.
I. The scenario is terminated after normal charging is established in E-1.1.
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ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Init 599 4% power, MOL, MFW in service, CB = 1202 per Checklist
- Integrators: BA - 0 and PW -100
- Tags: None Setup Drill 81 Reset normal engineering values CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary.
Primary integrator = 100 gal, Boron = 0 gal.
Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 1202 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.
o PEN running.
o R2B blowdown flows at 90 gpm.
o Reactor trip status correct 1 (Pg 2 of Group display Mode-1).
o Operational mode correct for current conditions. 2 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
Communications systems are turned on and functional 1
If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.
2 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.
Follow menu to manually override to correct mode.
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TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6610 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min mal ppl1a act,2,0,0,d,0 Phase A train A fails to actuate on SI 0 min vlv mss8 1,0,0,0,d,XV3I184C FCV-42 doesnt close automatically, will close by VB3 control switch
>6.5% power Pmp ccw2 6,7.02,5,0, CCW pump 12 trips on overcurrent C,fnispr.gt.6.5 X When requested CCW pp 12 motor hot to touch, B phase overcurrent flag dropped at breaker 30 min after CCW ser 1147 Ground alarm on Batt 11, clears after 3 pp 12 trips act,1,0,1798,c,XV1O245B,3 seconds ovr xv2i214c 8149C closes act,1,0,1800,c,XV1O245B,0 X Maintenance Notify control room that 8149c Solenoid has short causing ground, valve has failed closed and will not operate until repaired.
30min after HCV- cnh pzr2 6,1,5,1800, PCV-455b goes high in auto 123 open c,rcvh123.gt.0.1 30 min after PCV- mal mss2b act steam line break on S/G 12 Inside cnm 455B fails high 9e+06,120,1800,c,xcnh455f.gt.0.7 After RX trip PA Drill 32 NO Action on reactor trip L061C Scenario BU.doc Rev. 0
Drl_6610.txt
- NRC L082 Scenario 1
- glh1,8/14/08
- use 30 min time delays to allow nrc to direct events
- use snap 599 4% mol with mfw in service.
- at op l-3 6.26, pull rods to go to 8% power
- CCW 12 oc trip at 6.5%
pmp ccw2 6,7.02,5,0,c,fnispr.gt.6.5 #occp11
- 8149C ground after ccw pp 13 started
- causes ground alarm on dc bus 11 until fuse blows ser 1147 act,1,0,1798,c,XV1O245B,3 ovr xv2i214c act,1,0,1800,c,XV1O245B,0
- pcv-455b goes high in auto after hcv-123 open cnh pzr2 6,1,5,1800,c, rcvh123.gt.0.1, #xcnh455f
- FCV-42 S/G 12 MSIV must be closed manually vlv mss8 1,0,0,0,d,XV3I184C #rmsf042
- steam line break on S/G 12 Inside cnm after pcv-455b fails high mal mss2b act 9e+06,120,1800,c,xcnh455f.gt.0.7,
DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 4 %
GROSS GENERATION: 0 MWe NET GENERATION 0 MWe DAYS AT POWER: 120 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: Green PROTECTED EQUIPMENT: Train A/B, Bus F,G,&H, Prot. Sets I, II,III,IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:
- None ACTIVE SHUTDOWN TECH SPECS / ECGS:
- None TURNOVER ITEMS:
- Plant Startup in progress after going to mode 3 to replace Governor Valve 4 valve plug. Plant was in mode 3 for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Power ascension to 8% was stopped at 4% due to a CFCU 14 hi vibration.
Investigation showed dirty alarm contacts, which have been cleaned and CFCU 1-4 has been restarted.
Continue plant startup per OP L-3 6.26, pull rods to go to 8% power.
OPERABILITY ITEMS:
- None PRIORITY ITEMS FOR NEXT SHIFT:
- Continue with plant startup per L-3.
ANNUNCIATORS IN ALARM
- Numerous L061C Scenario BU.doc Rev. 0
SHIFT FOREMAN TURNOVER COMMENTS:
- 1. Reactivity management:
- a. Time in core life: MOL
- b. Power History: At 4%
- c. Boron concentration is 1202 ppm from a sample taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.
- d. Use rods to continue power ascension to 8% per OP L-3 6.26.
- 2. No one is in Containment, no entries are expected
- 3. U-2 is operating at 100% power COMPENSATORY MEASURES:
None CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.
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