ML13066A318
| ML13066A318 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/27/2013 |
| From: | D'Antonio J NRC Region 1 |
| To: | Entergy Nuclear Indian Point 3 |
| Jackson D | |
| References | |
| TAC U01866 | |
| Download: ML13066A318 (350) | |
Text
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 2000060131 Task
Title:
Perform a Quadrant Power Tilt Calculation by Hand 1940012125 KIA
Reference:
-RO - - -- -3.9
Job Performance Measure No: RO Admin 1 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator Plant - - - - - - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- Plant is at 100% power BOL.
- The Control Room personal computer is unavailable.
Task Standard: QPTR properly calculated.
Required Materials: Calculator, GRAPH-NI-2 General
References:
3-S0P-RPC005A, GRAPH-NI-2 Initiating Cue: You are the BOP and You are directed to perform a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC-005A Time Critical Task: No Validation Time: 45 minutes 1 of 10
Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-RCP-005A Comment:
- 2. Performance Step: Review Note before Step 1 Standard: Reviews Note Comment:
- 3. Performance Step: ENSURE appropriate meter range for detectors A and B, for each operable NIS Power Range Channel Standard: Ensures range meter indication between 1/3 and 2/3 of full scale Comment: Attachment Step 1.0 2 of 10
Performance Information (Denote critical steps with a check mark -/)
- 4. Performance Step: Record the following current information:
Standard: Records the following on Attachment 1
- Date T odays Date
- Time Current Time
- % Power Indicated Power Comment: Attachment Step 2.0
...J 5. Performance Step: RECORD UPPER and LOWER detector currents on operable NIS Power Range drawers Standard: Candidate demonstrates the ability to obtain readings from the correct meters and records them appropriately in the attachment Cue: Question the Candidate on how to obtain the detector currents.
Comment: Provide the Candidate with detector currents for use in the remainder of the JPM Attachment Step 3.0
- 6. Performance Step: If power range current amp is unavailable Standard: This step is Not Applicable Comment: Attachment Step 3.1 3 of 10
Performance Information (Denote critical steps with a check mark ...J)
...J 7. Performance Step: CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps by full power zero axial offset detector current from 3 GRAPH-NI-2 Standard: Enter data and calculate corrected detector current ratios 41 Upper 799/790=1.011 41 Lower 843/850=0.991 42 Upper 818/825=0.991 42 Lower 823/822=1.001 43 Upper 875/890=0.983 43 Lower 873/875=0.998 44 Upper 832/830=1.002 44 Lower 896/910=0.985 Comment: Attachment Step 4
..J 8. Performance Step: DETERMINE both upper and lower Average Normalized Ratios Standard: CALCULATE average normalized ratios for Upper detectors:
= 41U + 42U + 43U + 44U = 1.011+0.991+0.983+1.003 4 4
= 0.995 CALCULATE average normalized ratios for Lower detectors:
= 41L + 42L + 43L + 44L = 0.991+1.001+0.998+0.985 4 4
= 0.994 Comment: Attachment Step 5 4 of 10
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
'" 9. Performance Step: DETERMINE both upper and lower Quadrant Power Tilt as follows Standard:
= Highest Ratio of 41 U + 42U + 43U + 44U = 1.011 Average Ratio 0.997
=1.014
= Highest Ratio of 41 L + 42L + 43L + 44L = 1.001 Average Ratio (Step 6.2) 0.994
= 1.007 Comment: Values obtained by the candidate may vary depending on how decimal places they carry.
Attachment Step 6.0
- 10. Performance Step: Record Highest Quadrant Power Tilt calculated Standard: Records 1.014 Comment: Attachment Step 7.0 5 of 10
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- 11. Performance Step: If Quadrant Power Tilt exceeds 1.02 in either top or bottom of core ...
Standard: Determines QPTR does not exceed 1.02 Comment: Attachment Step 8.0 Terminating Cue: JPM Complete 6 of 10
Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __
7 of 10
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- Plant is at 100% power BOL.
- The Control Room personal computer is unavailable.
Initiating Cue:
You are the BOP and You are directed to perform a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC-005A
Appendix C Initial Conditions Form Actual Detector Currents I Channel Top Bottom I 41 799 843 42 818 823 i 43 875 873 I 44 832 896 I
Appendix C Initial Conditions Form ES-C-1 3-GRAPH-NI-2 Rev. 19X NIS FULL POWER DETECTOR CURRENTS (pA)
Cycle 17 (Values updated based on 17C20 flux map at 99.9% RTP)
FACE PLATE CURRENT Channel TOP OTTOM N41 790 850 N42 825 822 N43 890 875 N44 830 910 IR DETECTOR CURRENT LIMITS FOR USE IN 3-POP-1.3 N35 Current limit (Amps) N36 Current limit CAmps) 4%RTP 0.85 E-05 1.72 E-05 8%RTP 1.70 E-05 3.44 E-05 Written By:
Reviewed By: Signature Approved By Signature Effective Date: Today' s Date
~Entergy Nuclear Northeast Procedure Use Is:
if Continuous o Reference Control Copy: _ _ __
Effective Date: _ __
o Information Page 1 of 13 3-S0P-RPC-OOSA, Revision: S QUADRANT POWER TILT CALCULATIONS Approved By:
Team 3D Procedure Owner EDITORIAL REVISION
No: 3-S0P-RPC-00SA Rev:S QUADRANT POWER TILT CALCULATIONS Page 2 of 13 REVISION
SUMMARY
(Page 1 of 2) 1.0 REASON FOR REVISION 1.1 Updated to eliminate poor practices and ensure procedure contains proper level of detail.
2.0
SUMMARY
OF CHANGES 2.1 Moved and revised former Step 1.2, of Purpose, to Step 2.2.1 of P&Ls, General Information (Editorial 4.6.13).
2.2 Moved and revised former Step 1.3, of Purpose, to Step 2.2.2 of P&Ls, General Information (Editorial 4.6.13).
2.3 Deleted former P&L 2.1 regarding RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12).
2.4 Split Section 2, Precautions and Limitations, into 2 parts: 2.1, Precautions and Limitations and 2.2, General Information (Editorial 4.6.10).
2.S Added P&L 2.1.1 regarding use of uncorrected detector outputs to be consistent with Unit 2 procedure (Editorial 4.6.11).
2.6 Added P&L 2.2.3 regarding short term Tilt spikes with alarm actuation following ReS boron changes to be consistent with Unit 2 procedure (Editorial 4.6.11).
2.7 Added "IF Reactor Power is less than or equal to 7S%, THEN" to Step 3.1 to clarify SR 3.2.4.1 (Editorial 4.6.13).
2.8 Deleted former Step 3.2 regarding reactor power being greater than SO%. Per Reactor Engineering, QPTR can be performed at lower power, but becomes less accurate (Editorial 4.6.12).
2.9 Added Step 3.2 "IF Reactor Power is greater than 7S%,
THEN VERIFY all four NIS channel upper and lower detectors are in service" to clarify SR 3.2.4.1 (Editorial 4.6.11) 2.10 Added Note prior to Step 4.1 regarding normalization factors not being available following refueling or detector maintenance (Editorial 4.6.11).
2.11 Split Section 4.1 into two parts: 4.1, Manual Quadrant Power Tilt Calculation and 4.2, Computer Network Program Quadrant Power Tilt Calculation (Editorial 4.6.14).
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 3 of 13 (Page 2 of 2) 2.12 Changed Step 4.2.8 from "SELECT" to "ENTER" and deleted bullet regarding clicking "OK" and appropriate option button as there are no 'select' options (Editorial 4.6.13).
2.13 Added 2 bullets to Note prior to Step 4.2.8 to clarify when 3 or 4 operable NIS Power Range channels are used (Editorial 4.6.11).
2.14 Deleted former Step 4.1.13 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12).
2.15 Deleted former Steps 4.1.14.2,4.1.14.3 and 4.1.14.4 as these are all included in Tech Spec 3.2.4 (Editorial 4.6.12).
2.16 Added bullet to Step 4.2.13 to enter calculated Quadrant Power Tilt in the Narrative Log (Editorial 4.6.11).
2.17 Added Reference 5.2.2, SR 3.2.4.1 (Editorial 4.6.4).
2.18 Deleted former Reference 5.3.1, RA-11.1, as it is no longer mentioned in procedure (Editorial 4.6.12).
2.19 Added Reference 5.6.1, 0-NF-303, Core Quadrant Power Balance as an Interface Document (Editorial 4.6.11).
2.20 Added Reference 5.7.1 UFSAR Section 7.6.2 (Editorial 4.6.11 ).
2.21 Deleted former Step 4.0 of Attachment 1 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12).
2.22 Added "when Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used" to Note in Step 5 of Attachment 1 to clarify when 3 operable NIS Power Range channels can be used (Editorial 4.6.13).
2.23 Added bullets to Step 8.0 of Attachment 1 to verify requirements of LCO 3.2.4 are met, notify CRS and SM and to enter QPTR in the Narrative log (Editorial 4.6.11).
2.24 Changed Step 10.0 of Attachment 1 to forward Attachment 1 to Operations Staff to simplify the action. Placing in Operations Log binder has the same result of forwarding to Operations Staff (Editorial 4.6.13).
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 4 of 13 TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ......................................................................................................................... 5 2.0 PRECAUTIONS AND LIMITATIONS ................................................................................. 5 3.0 PREREQUiSiTES .............................................................................................................. 5 4.0 PROCEDURE .................................................................................................................... 6 4.1 Manual Quadrant Power Tilt Calculation .................................................................... 6 4.2 Computer Network Program Quadrant Power Tilt Calculation ................................... 6
5.0 REFERENCES
.................................................................................................................. 9 6.0 RECORDS AND DOCUMENTATION ................................................................................ 9 Attachments ATTACHMENT 1 MANUAL QUADRANT POWER TILT CALCULATION ................................ 10
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS i I Page 5 of 13 1.0 PURPOSE 1.1 This procedure provides guidance for the preparation of quadrant power tilt calculations in accordance with Technical Specification surveillance requirement SR 3.2.4.1.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions and Limitations 2.1.1 Uncorrected detector outputs SHALL NOT be used to calculate quadrant power tilt because they do NOT represent relative core power in their associated quadrant.
2.2 General Information 2.2.1 WHEN in MODE 1 with greater than 50 percent of rated thermal power AND quadrant power tilt exceeds 1.02. THEN VERIFY QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (Reference 5.2.1}
2.2.2 WHEN in MODE 1 with greater than 50 percent of rated thermal power AND either one upper OR lower quadrant power tilt alarm monitors are inoperable. THEN verify QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND after load change greater than 10 percent of rated power.
(Reference 5.2.3}
2.2.3 Short term Quadrant Power Tilt calculation spiking with possible Plant Computer System alarm actuation can occur immediately following Reactor Coolant System (RCS) boron changes. These short term spikes, (approximately five minutes duration), should not be considered significant. as they are transitory in nature.
3.0 PREREQUISITES 3.1 IF Reactor Power is less than or equal to 75%,
THEN VERIFY a Minimum of three NIS channel upper and lower detectors are in service. (Reference 5.2.2) 3.2 IF Reactor Power is greater than 75%,
THEN VERIFY all four NIS channel upper and lower detectors are in service.
! No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 6 of 13 4.0 PROCEDURE NOTE Following refueling or detector maintenance, prior to performance of initial at-power incore flux mapping operations, NIS detector current output normalization factors will not be available. During this period, NIS detector current outputs must be logged as required below, but quadrant tilt calculations cannot be performed.
4.1 Manual Quadrant Power Tilt Calculation 4.1.1 IF desired to perform a manual calculation, THEN GO TO ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION.
4.2 Computer Network Program Quadrant Power Tilt Calculation NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 offull scale.
4.2.1 VERIFY appropriate meter range is selected for detectors A and B for each operable NIS channel.
4.2.2 RECORD the individual upper and lower power range detector currents indicated on each operable NIS Power Range drawer in the following table:
TABLE
~=~~~~ANGECHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 42 43 44
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER rllT CALCULATIONS Page 7 of 13 WARNING Electrical shock hazard inside drawer.
4.2.2.1 IF a power range detector current amp reading is unavailable, THEN:
a) CONTACT I&C to obtain a DVM current reading for the appropriate drawer.
b) RECORD DVM reading(s) in the Table provided in Step 4.2.2.
4.2.3 ACCESS the QPTR Program (\\ipcfsetsp002\OPERATIONS\OPS General\! P3\Software\Unit 3\QPTR\QPTR.exe).
4.2.4 IF the network is unavailable AND CCR computer is operational, THEN:
4.2.4.1 OBTAIN the QPTR Program CD from Shift Manager's office.
4.2.4.2 INSERT CD in a CCR computer AND OPEN QPTR Program.
4.2.5 CLICK the "Click Here to Start" button to retrieve 100% NIS currents from 3-Graph-NI-2.
4.2.6 COMPARE the latest NIS currents against the 3-Graph-NI-2 values.
4.2.6.1 IF the 100% NIS currents do not match 3-Graph-NI-2.
THEN CLICK the "No" button AND ENTER 100% currents and 3-Graph-NI-2 revision number in the text boxes when prompted.
4.2.6.2 IF the 100% NIS currents match the latest revision of 3-Graph-NI-2, THEN click the "Yes" button.
4.2.7 WHEN prompted, THEN ENTER today's date, the current time and the current % power.
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 8 of 13 NOTE This program can be used for either 3 or 4 operable NIS Power Range channels.
- Three operable NIS Power Range channels can be used when Reactor Power is less than or equal to 75%. (Reference 5.2.2)
- All four operable NIS Power Range channels are required when Reactor Power is greater than 75%
4.2.8 ENTER the correct number of operable NIS Power Range channels.
4.2.9 ENTER appropriate NIS information from Table of Step 4.2.2 in the white text boxes.
4.2.10 IE a power range channel that is out of service, THEN ENTER "0" for the applicable channel in the white text boxes.
4.2.11 CLICK on the CALCULATE QPTR button to show the current QPTR.
4.2.12 CLICK on the PRINT RESULTS button to obtain computer printout of the quadrant power tilt calculation.
4.2.13 IE Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY requirements of LCO 3.2.4 are met.
- ENTER calculated Quadrant Power Tilt in the Narrative Log.
4.2.14 WHEN QPTR calculation program is no longer required, THEN CLICK "Quit Program".
4.2.15 OBTAIN CRS and SM signatures for the completed QPTR printout.
4.2.16 PLACE completed QPTR computer printout in Operations Log binder.
I I No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 9 of 13
5.0 REFERENCES
5.1 Commitment Documents 5.1.1 None 5.2 Technical Specifications:
5.2.1 LCO 3.2.4 Action Statement 5.2.2 SR 3,2.4,1 5.2.3 TRO 3.2.A Action Statement 5.3 Development Documents 5.3.1 None 5.4 Historical Development Documents 5.4.1 3PT-W022 , Quadrant Power Tilt Calculation 5.5 Drawings 5.5.1 None 5.6 Interface Documents 5.6.1 O-NF-303, Core Quadrant Power Balance 5.6.2 3-Graph-NI-2, NIS Full Power Detector Currents 5,7 UFSAR reference 5,7.1 Section 7.6.2 6.0 RECORDS AND DOCUMENTATION 6.1 Records 6.1.1 The following required records resulting from this procedure are controlled and maintained in accordance with the IP3 Records Retention Schedule.
- Attachment 1, Manual Quadrant Power Tilt Calculation Sheet
- Computer-generated printout of Quadrant Power Tilt Calculation 6,2 Documentation 6.2.1 The following documentation is required to be controlled or maintained in accordance with the IPEC Records Retention Schedule:
- None
No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT CALCULATIONS Page 10 of 13 ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 1 of 4)
NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 of full scale.
1.0 ENSURE appropriate meter range is selected for detectors A and B, for each operable NIS Power Range channel.
2.0 RECORD the following current information:
Datec_ _ _ __ Time_ _ _ _ _ _ __ % Power- - - - - -
3.0 RECORD individual upper and lower Power Range detector currents indicated on each operable NIS Power Range drawer in the following Table 1:
NOTE Enter "0", if one power range channel is out of service.
TABLE 1 POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 42 43 44
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 11 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 2 of 4)
WARNING Electrical shock hazard inside drawer.
3.1 IF power range current amp is unavailable, THEN:
3.1.1 CONTACT I&C to obtain a DVM current reading for the appropriate drawer.
3.1.2 RECORD DVM reading(s) in Table 1 of Step 3.0.
4.0 CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2, NIS Full Power Detector Currents):
Indicated 3-Graph-NI-2 Normalized Detector Indicated 3-Graph-NI-2 Normalized Detector Current Current Ratio Current Current Ratio 41 Upper T
41 Lower
42 Upper + = 42 Lower + =
43 Upper T
43 Lower +
44 Upper + = 44 Lower + =
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 12 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 3 of 4) 5.0 DETERMINE both upper and lower Average Normalized Ratios as follows:
NOTE When Reactor Power is less than or equal to 75%. then 3 NIS power range channels can be used. (Reference 5.2.2) If ONLY 3 NIS power range channels are in service, then "0" is entered for the inoperable channel, AND the sum of the currents is divided by 3.
5.1 CALCULATE average normalized ratio for Upper detectors:
41U + 42U + 43U + 44U
=
3* or 4*
- See note above 5.2 CALCULATE average normalized ratio for Lower detectors:
41L + 42L + 43L + 44L
=
3* or 4*
- See note above previous sub-step NOTE
- Upper Quadrant = Highest Normalized Ratio for Upper Detector (Step 4.0)
Power Tilt Average Normalized Ratio for Upper Detector (Step 5.1)
- Lower Quadrant = Highest Normalized Ratio for Lower Detector (Step 4.0)
Power Tilt Average Normalized Ratio for Lower Detector (Step 5.2) 6.0 DETERMINE both upper and lower Quadrant Power Tilt as follows:
6.1 CALCULATE Quadrant Power Tilt for Upper detectors:
Highest Ratio of 41 U, 42U, 43U, or 44U = ___
Average Ratio (Step 5.1) 6.2 CALCULATE Quadrant Power Tilt for Lower detectors:
Highest Ratio of 41 L, 42L, 43L, or 44L =___
Average Ratio (Step 5.2)
No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT CALCULATIONS Page 13 of 13 ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 4 of 4) 7.0 RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2:
Highest Quadrant Power Tilt_ _ _ _ _ _ _ _ _ _ _ __
8.0 IF Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY requirements of LCO 3.2.4 are met
- ENTER calculated Quadrant Power Tilt in the Narrative Log 9.0 REVIEW Attachment 1 for satisfactory completion:
I Control Room Supervisor Date I Time I
Shift Manager Date I Time 10.0 WHEN complete, THEN FORWARD this Quality Record to the Operations Department Records Custodian.
Signature Date
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Task No: 0040270131 Task
Title:
Perform Deborating Demineralizer In-Service Time Calculation 2.1.25 Job Performance Measure KIA
Reference:
RO - 3.9 No: ROAdmin 2
~~~~--------
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator - - - - - - - Plant - - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmrF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
Task Standard: In-Service Time properly calculated.
Required Materials: Calculator Procedure 1 of 6
Appendix C Job Performance Measure Form ES-C-1 General
References:
3-S0P-CVCS-004 Initiating Cue: You are the spare RO and the CRS has directed you to determine the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4.
Time Critical Task: No Validation Time: 45 minutes 20f6
Appendix C Page 3 Form ES~C~1 Performance Information (Denote critical steps with a check mark -.J)
- 1. Performance Step: Determine RCS has not been borated to cold shutdown
+100 ppm and Rx Trip Breakers are Open Standard: Given in Initial Conditions Comment: Procedure Step 4.3.4.1
Standard: Given in Initial Conditions Comment Procedure Step 4.3.4.2 "3. Performance Step: Calculate the change in Tavg on Attachment 1 Standard: A Tavg = TF - TI A Tavg = 569°F - 568°F Comment: Procedure Step 4.3.4.3 "4. Performance Step: Calculate the change in RCS Boron Concentration for the change in Tavg on Attachment 1 Standard: A B = A Tavg
- IBW A B = 1°F * -33.4 pcm/oF*-O.1074 ppm/pcm A B =22.1 ppm Comment: Procedure Step 4.3.4.4 30f6
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)
"5. Performance Step: Calculate Boron Efficiency for selected deborating demineralizer Standard: BE :: 1 - (BO/BI)
=
BE 1 - (14/98)
BE = .86 Comment: Procedure Step 4.3.1.1
" 6. Performance Step: Calculate G - gallons of water using Graph CVCS-3 Standard: From Nomograph - 13,500 +/- 500 gallons Comment: Procedure Step 4.3.4.5
" 7. Performance Step: Calculate the Deborating Demineralizer in-service time Standard: T =G I (LF .. BE)
T :: 13500 gallons I (84 gallons/min" 0.86)
T = 186.8 minutes (179 to 193 minutes)
Comment: Procedure Step 4.3.4.5 Terminating Cue: JPM Complete 4of6
Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
50f6
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmfOF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
Initiating Cue:
You are the spare RO and the CRS has directed you to determine the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4.
PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 19 of 37 CAUTION When more than one unsaturated demineralizer is placed in service at the same time, then the margin to cold shutdown boron must be evaluated by chemistry.
4.3.4 Determining Deborating Demineralizer In-Service Time 4.3.4.1 IF RCS has been borated to cold shutdown +100 ppm boron concentration AND the Reactor Trip Breakers are OPEN, THEN GO TO Step 4.3.5 to place Deborating Demineralizer(s) in service as required (assist in crud burst cleanup).
4.3.4.2 IF RCS Boron Concentration is less that 3 PPM AND Reactor Power is less than 99%,
THEN GO TO Step 4.3.5 to place Deborating Demineralizer in service as required.
NOTE This method is intended for use at approximately 100% power due to the basis for Attachment 2, Inverse Boron Worth vs Boron Concentration.
4.3.4.3 CALCULATE the change in Tavg required on Attachment 1 as follows:
A Tavg = TF - TI, where A Tavg = Required change in Tavg (OF)
TF= Final Tavg(OF)
TI = Initial Tavg(OF)
PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 20 of 37 4.3.4.4 CALCULATE the change in RCS Boron concentration for the change in Tavg on Attachment 1 as follows:
~ B =~ Tavg
~ Tavg =Required change in Tavg (OF)
ITC = At Power Isothermal Temperature Coefficient for the initial Tavg(pcm/oF), from Graph RV-5B IBW = Inverse Boron Worth (ppm/pcm) for the initial RCS Boron concentration, from Attachment 2, Inverse Boron Worth VS Boron Concentration 4.3.4.5 CALCULATE the Deborating Demineralizer in-service time on Attachment 1 as follows:
T =G / (LF
- BE), where T =required Deborating Demineralizer in-service time (Min)
G =Amount of dilution water required for the change in boron concentration (gals),from Graph CVCS-3, (Dilution Nomograph for Hot ReS 580°F) or CCR computer.
LF =Letdown Flow (gpm), from FI-134
=
BE Boron Efficiency for the selected Deborating Demineralizer 4.3.4.6 PLACE completed Attachment 1, Deborating Demineralizer In-service Time Calculations, in Daily Log Binder for Operations Staff to review and file.
PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 36 of 37 ATTACHMENT 1 DEBORATING DEMINERALIZER IN-SERVICE TIME CALCULATIONS (Page 1 of 1) 4.3.4.3 Required change in Tavg:
=
4.3.4.4 Change in RCS Boron concentration:
= *
- A B (ppm) IBW (ppm/pcm) 4.3.1.1 Boron Efficiency for Deborating Demineralizer:
Bed No. Sample Time Sample Date
________ =1-(~______________________ , _________________________~)
BE BO (ppm) BI (ppm) 4.3.4.5 Deborating Demineralizer in-service time:
= - - - - - , ('----------------- * ------------')
T (min) G (gal) LF (gpm) BE
No: 3-S0P-CVCS-004 Rev: 25 PLACING THE CVCS DEMINERALIZERS IN OR OUT OF SERVICE Page: 37 of 37 ATIACHMENT2 INVERSE BORON WORTH VS BORON CONCENTRATION (Page 1 of 1)
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10 20 30 40 50 60 70 80 90 100 Boron Concentration (PPM)
Unit 3 Rev. 0 DILUTION NOMOGRAPH
- 10 20 HOT FO R ReS 580° 10 20 30 itO 50 60 70 50 ....... -._- 100 200 100 500 200 800 .,.
1000 300 10 *2000 500 5000 100 10,000 1000 20,000 2000 1000 50,000 2000 100,000 3000 3000 PPM BOROH PPM BORON DILUTION It( COOLANT DILUTION WATER GAL Reviewed By: K. ~ _
. Approved By :~, J_
cvcs- 3 It.!..
page 3 of 9
-.A;t:/
.. -----~.-- Section 4
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 2000390131 Task
Title:
Prepare a Tagout 1940012213 Job Performance Measure RO - 4.1 KIA
Reference:
~~~~----- No: ROAdmin 3 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator - - - - - - - - - - Plant - - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tagout boundary
- The shift manager has waived the requirement for double valve protection.
- Single Valve protection is adequate for this tagout.
Task Standard: Manual Tagout Complete and ready for review Required Materials: None General
References:
EN-OP-102, Protective and Caution Tagging 3-COL-CVCS-001 Chemical and Volume Control System EN-OP-102-1, Protective and Caution Tagging Forms & Checklists 9321-F-27363 Flow Diagram Chemical and volume Control System Sheet 1 1 of 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are a spare reactor operator and the SM has directed you to prepare a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP 102-01.
Time Critical Task: No Validation Time: 45 minutes 20f9
Performance Information (Denote critical steps with a check mark ~)
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains EN-OP-102 and EN-OP-102-01 Comment:
- 2. Performance Step: Ensure requirement of Attachments 9.1 and 9.2 of EN OP-102 are followed Standard: Review Attachment 9.1 and 9.2 CommentStep Procedure Step 5.3 [1]
- 3. Performance Step: Review Scope of Work Standard: Tagout Required for emergent work.
Given in Initial Conditions Comment: Procedure Step 5.3 [2]
- 4. Performance Step: Determine Safe Work Boundary for 33 Charging Pump Seal Replacement Standard: Review Plant Prints 9321-F-27363 Comment: Procedure Step 5.3 [2] (g) 3 of 9
Appendix9 _ _ _ _ _ _ _ _ _ _P_a-"'9!-e_4_ _ _ _ _ _ _ _ _ _ Fo_r_m_E_S-_C_-_1 Performance Information (Denote critical steps with a check mark ...J)
- 5. Performance Step: Boundary Valves should be reviewed for outstanding deficiencies Standard: No deficiencies exist on valves identified in tagout boundary - Given in Initial Contitions CUE: No deficiencies exist on valves identified in tagout boundary Comment: Procedure Step 5.3 [3]
- 6. Performance Step: Utilizing the Isolation Boundaries, Prepare the tagout For each tag include:
- Tag Type
- Component/Equipment Number
- Component/Equipment Name
- Component/Equipment Location
- Component Hang and Restoration Position
- Tagout Hang Sequence Standard: See Attached Answer Key Comment:
4of9
Appendix C PageS Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)
Key Elements From Attachment 9.2 Tagging Sequence
- All Tagouts require tags to be hung and cleared in the order specified on the Tag Hang sheet or Tags To Be Removed sheet. When no definitive order is required for certain components of a Tagout, the Operations Supervisor may specify a given order number for multiple components (e.g., multiple components listed on the Tagout may be given order number "5" when their sequence relative to each other is not important).
- Recommended tagging order for pumps A. Control switch B. Breaker for main power C. Breakers for auxiliary power (motor heater, oil pumps, etc.)
D. Discharge valve E. Suction valve F. Other components within scope of Tagout Terminating Cue: JPM Complete S of 9
ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE: 3C20 MANUAL CH-038 TAGOUT: _ _ _ _ _ __
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placementl Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Equipment Location Seq. Configuration Da!efT~ __ DatefTime Seq. Configuration DatefTime DatefTime TaflNotes 133 Charging Pump Pullout 1 Danger ~ontrol Switch 1 Or CRITICAL Auto Pull to Lock
~CR ------ ---
133 Charging Pump 2 Danger ~reaker Control Fuses 2 Removed/Off Installed/On r---- ~80V Room Bus 5A -----
133 Charging Pump 3 Danger ~reaker 3 Racked Out CRITICAL Racked In
~80V Room Bus 5A -------- ------- 1--- ------
~H-236 33 Charging Pump Outlet solation 4 Danger 4 Closed CRITICAL Open
- 33 Charging Pump Cell pH-238 33 Charging Pump Outlet solation to Seal Injection 5 Danger 5 Closed CRITICAL Open 33 Charging Pump Cell r--- ----- I vH-409 33 Charging Pump Recirculation Isolation 6 Danger 6 Closed CRITICAL Open 33 Charging Pump Cell -------
CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation 7 Danger 7 Closed Open 33 Charging Pump Cell CH-284 33 Charging Pump Inlet solation 8 Danger 8 Closed CRITICAL Open 33 Charging Pump Cell ----- 1---- -- ---- ---
CH-418 33 Charging Pump Suction Stabilizer Drain 9 Danger 9 Open Closed P3 Charging Pump Cell ------- ---- ----------
~H-1175D 33 Charging Pump Suction ine Drain 10 Danger 10 Open Closed P3 Charging Pump Cell ------- - - - - ------- -------
PH-419 33 Charging Pump Suction Stabilizer Vent Cap 11 Danger 11 Cap Removed CRITICAL Cap Installed
- 33Charging Pump Cell -
6of9
ATTACHMENT 9.3 TAGOUT TAGS SHEET CH-419 33 Charging Pump Suction Stabilizer Vent 12 Danger 12 Open Closed 33 Char~in~ Pump Cell CH-103 33 Charging Pump Outlet Vent Cap 13 Danger 13 Cap Removed CRITICAL Cap Installed 33 Charging Pump Cell
...H-103 33 Charging Pump Outlet Vent 14 Danger 14 Open Closed 133~ Char~ing Pump Cell I I
7 of 9
Appendix C Initial Conditions Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tag out boundary
- The shift manager has waived the requirement for double valve protection.
- Single Valve protection is adequate for this tagout.
Initiating Cue:
You are a spare reactor operator and the SM has directed you to prepare a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.
~:3-COL.CVCS-001 Rev: 27]
r CHEMICAL AND VOLUME CONTROL SYSTEM i Page 27 of 41 Des.
Oper Actual Pos. Pos. Initial IV 2.12 Charging Pumps 55' Elev. - PAS 2.12.1 Charging Pumps Local Control Station 31 Charging Pump Control Switch Remote 32 Charging Pump Control Switch Remote 33 Charging Pump Control Switch Remote - ..*-
CH-AOV-200A 45 GPM Letdown Orifice Control Switch Auto AR CH-AOV-200B 75 GPM Letdown Orifice Control Switch Auto AR CH-AOV-200C 75 GPM Letdown Orifice Control Switch Auto -_.
AR 0 PI-142 Vent (next to charging pumps stabilizer heater panel) Shut _._
2.12.2 31 Charging Pump Cell CH-1175B 31 Charging Pump Suction Line Drain Shut CH-278 31 Charging Pump Inlet Isolation Open CH-273 31 Charging Pump Relief and Recirculation Line Outlet Isolation LO CH-230 31 Charging Pump Outlet Isolation Open CH-232 31 Charging Pump Outlet Isolation to Seal Injection Open NED-275 31 Charging Pump Seal Tank Overflow Isolation Open CH-407 31 Charging Pump Recirculation Isolation Shut CH-1 31 Charging Pump Strainer DIP Hi Side Isolation Shut Capped CH-2 31 Charging Pump Strainer DIP Low Side Isolation Shut Capped
ICHEMICAL AND VOLUME CONTROL ' No:3-COL-CVCS-001 Rev: 27 I SYSTEM I Page 28 of 41 L - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ _ _ __ _
.~
Des.
Oper Actual Pos. Pos. Initial IV 2.12 (CONTINUED)
CH-101 31 Charging Pump Outlet Vent Shut Capped _ __
CH-412 31 Charging Pump Suction Stabilizer Drain Shut CH-413 31 Charging Pump Suction Stabilizer Vent Shut Capped ____
CH-414 31 Charging Pump Suction Stabilizer Drain Line Vent Shut Capped ____
31 Charging Pump Transfer Switch Normal Locked 31 & 32 Charging Pumps Disconnect Switch Locked Off - -
2.12.3 32 Charging Pump Cell CH-288 RWST to Charging Pumps Suction Isolation Shut CH-289 Charging Pump Suction Header Isolation Open CH-1175C 32 Charging Pump Suction Line Drain Shut CH-283 32 Charging Pump Inlet Isolation Open CH-276 32 Charging Pump Relief and Recirculation Line Outlet Isolation LO CH-235 32 Charging Pump Outlet Isolation Open CH-233 32 Charging Pump Outlet Isolation to Seal Injection Open NED-279 32 Charging Pump Seal Tank Overflow Isolation Open CH-408 32 Charging Pump Recirculation Isolation Shut CH-3 32 Charging Pump Strainer DIP Hi Side Isolation Shut Capped CH-4 32 Charging Pump Strainer DIP Low Side Isolation Shut Capped
No:3-COL-CVCS-001 Rev: 27 CHEMICAL AND VOLUME CONTROL SYSTEM Page 29 of 41 Des.
Oper Actual Pos. Pos. Initial IV 2.12 (CONTINUED)
CH-102 32 Charging Pump Outlet Vent Shut Capped CH-415 32 Charging Pump Suction Stabilizer Drain Shut CH416 32 Charging Pump Suction Stabilizer Vent Shut Capped CH-417 32 Charging Pump Suction Stabilizer Drain Line Vent Shut Capped 32 Charging Pump Transfer Switch Normal Locked 2.12.4 33 Charging Pump Cell CH-113 Charging Pumps Discharge Header Vent Shut Capped CH-1175D 33 Charging Pump Suction Line Drain Shut CH-284 33 Charging Pump Inlet Isolation Open CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation LO CH-236 33 Charging Pump Outlet Isolation Open CH-238 33 Charging Pump Outlet Isolation to Seal Injection Open NED-280 33 Charging Pump Seal Tank Overflow Isolation Open CH-409 33 Charging Pump Recirculation Isolation Shut CH-5 33 Charging Pump Strainer DIP Hi Side Isolation Shut Capped CH-6 33 Charging Pump Strainer DIP Low Side Isolation Shut Capped CH-103 33 Charging Pump Outlet Vent Shut Capped
No: 3-COL-CVCS-001 Rev: 27 CHEMICAL AND VOLUME CONTROL SYSTEM Page 30 of 41 Des.
Oper Actual Pos. Pos. Initial IV 2.12 (CONTINUED)
CH-418 33 Charging Pump Suction Stabilizer Drain Shut CH-419 33 Charging Pump Suction Stabilizer Vent Shut Capped CH-420 33 Charging Pump Suction Stabilizer Drain Line Vent Shut Capped CH-199 Emergency Boration Line Drain (in overhead) Shut Capped 2.12.5 Charging Pump Cells Passage Way CH-229 PT-142 & PI-142 Root Isolation Open 0 PT-142 & PI-142 Isolation Open 2.13 Boric Acid Transfer Pum~s 55' Elev. - PAB 2.13.1 31 Boric Acid Transfer Pump CH-376 Boric Acid Batch Tank Outlet Isolation Shut CH-363 31 Boric Acid Transfer Pump Primary Water Supply Isolation Shut CH-367A 31 Boric Acid Transfer Pump Batching Tank Supply Isolation Shut CH-364 31 Boric Acid Transfer Pump Suction Isolation Open CH-360 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Filter AR CH-361 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Storage Tank AR CH-355A PI-190A Isolation Open
ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE: _MANUAL,_ _ _ __ TAGOUT: __________
~Tag...
Tag Equipment Place. Place. Rest. 1st Rest. 2nd PlacemenU Serial Type Equipment Description Place. Placement 1st Verif 2nd Venf Rest. Restoration Verif Verif Removal
'-. No. . \-
Equip!T1ent Location Seq. Configuration Dateffime Dateffime Seq. Configuration _~fIime Dateffime Tag Notes p3 Charging Pump Pullout 1 Danger pontrol Switch 1 Or CRITICAL Auto Pull to Lock
~CR i,
r---- .. ~
I- ~.-
I p3 Charging Pump 2 Danger ~reaker Control Fuses Removed/Off Installed/On
_ ~80V Room Bus 5A . .
p3 Charging Pump 3 Danger ~reaker 3 Racked Out CRITICAL Racked In
!480V Room Bus 5A _.,... *... .. r - - - - . _. ..
,",H-236 33 Charging Pump Outlet solation 4 Danger 4 Closed CRITICAL Open
~3 ChlilrgingPump Cell _. ..
r .
r---H-238 33 Charging Pump Outlet solation to Seal Injection 5 Danger 5 Closed CRITICAL Open
~3 Charging Pump Cell _. -
~H-409 33 Charging Pump
~ecirculation Isolation Open 6 Danger 6 Closed CRITICAL P3 Charging Pump Cell .c _. ._. ....
",H-281 33 Charging Pump Relief and
~ecirculation Une Outlet Isolation 7 Danger 7 Closed Open
~3 Charging Pump Cell
- ~H-284 33 Charging Pump Inlet solation 8 Danger 8 Closed CRITICAL Open P3 Charging Pump C e l l _ c - - _. - _.
~H-418 33 Charging Pump Suction
~tabilizer Drain 9 Danger 9 Open Closed P3 Charging Pump Cell ..
[10
- ~
~H-1175D 33 Charging Pump Suction ine Drain Danger 10 Open Closed p3 CharginQ Pump Cell r---H-419 33 Charging Pump Suction Stabilizer Vent Cap 11 Danger 11 Cap Removed CRITICAL Cap Installed P3 Charging Pump Cell - _. . .. ~
ATTACHMENT 9.3 TAGOUT TAGS SHEET
",H-419 33 Charging Pump Suction Stabilizer Vent 12 Danger 12 Open Closed P3 Charging Pump Cell ------------ ------------
~H-1 03 33 Charging Pump Outlet Vent 13 Danger ~ap 13 Cap Removed CRITICAL Cap Installed p3 Charging Pump Cell ------------
~H-103 33 Charging PumpOlitletVEmt 14 Danger 14 Open Closed tn Charaina Puma Cell
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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Task No: 2000130131 Task
Title:
Prepare a VC Pressure Relief Release Permit 1940012311 Job Performance Measure ROAdmin 4 KIA
Reference:
- 3.8
--~~~--------
No:
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator ----------
Plant - - - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable.
- 3. VC Pressure is 1.5 psig
- Permit Number 120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7 I-ICi/cc o R-12 Current Alarm 1.5 E-6 I-ICi/cc o R-14 Current Reading 9.948E-7I-1Ci/cc o R-14 Current Alarm 1.5E-5I-1Ci/cc o R-15 Current Reading 1.32 E-6 I-ICi/cc o R-27 Current Reading 10.0I-lCi/sec o R-27 Current Alarm 3.25 E+3 I-ICi/sec o Plant Vent Sample 1.85 E-5 I-ICi/cc Plant Vent Flow 3.21 E+4 scfm Condenser Air In leakage 5.8 scfm 1 of 10
Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: . A VC Pressure Relief Gaseous Release Permit (3-S0P-WDS 013 Attachment 1) is correctly filled out.
Required Materials: Calculator General
References:
3-S0P-WDS-013.
Initiating Cue: You are the BOP operator and the CRS has directed you to perform a manual VC Pressure Relief Gaseous Release Permit in accordance with 3-S0P-WDS-013.
Time Critical Task: No Validation Time: 25 Min 2 of 10
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-WDS-013 Review Precautions and Limitations CUE: All pal are satisfactory to continue.
Comment:
- 2. Performance Step: Review NOTES before Step 4.1.1 Standard: Reviews Notes Comment:
- 3. Performance Step: Record VC Pressure Relief as system to be released on Attachment 1 Standard: Enters "VC Pressure Relief' on Attachment 1 Comment: Procedure Step 4.1.1
- 4. Performance Step: Record current date/time on Attachment 1 Standard: Enters current date/time on Attachment 1 Comment: Procedure Step 4.1.2 3 of 10
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark...J)
- 5. Performance Step: ASSIGN permit number and RECORD on Attachment 1.
Standard: Records Permit Number. Given in Initial Conditions Comment: Procedure Step 4.1.3
- 6. Performance Step: Record current VC pressure on Attachment 1 Standard: Records 1.5 psig on Attachment 1. Given in Initial Conditions Comment: Procedure Step 4.1.4
- 7. Performance Step: VERIFY one of the following conditions satisfied:
- R-12 operable.
Standard: R-12 is operable. Given in Initial Conditions Comment: Procedure Step 4.1.5
- 8. Performance Step: Determine VC Noble Gas concentration using one of the following methods
- R-12 reading (~Ci/cc)
Standard: Determines R-12 reading is available Comment: Procedure Step 4.1.6 4 of 10
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,J)
- 9. Performance Step: If using R-12, THEN circle "R-12 Monitor" and Enter the following on Attachment 1
- R-12 reading for Concentration of Nobel Gas (I-lCi/cc)
- NA for Sample #, Date, and Time for Grab Sample Standard: Circle R-12 Monitor; Enter 7.170 E-7lJCi/cc and enter NA for Sample #, Date and Time Comment: Procedure Step 4.1.8
'" 1O. Performance Step: Determine calculated release rate ( R ) IJCi/sec and record on Attachment 1 Standard: R = (2.83E+OS cc/sec)
- 7.170 E-7lJCi/cc R= 2.02E-1 Comment: Procedure Step 4.1.9
'" 11. Performance Step: Determine available release rate D in I-ICi/sec with R-27 In Service (given in Initial Conditions)
Standard: 3.2SE+3 IJCi/sec -10 I-ICi/sec
= 3.24E+3 I-ICi/sec Comment: Procedure Step 4.1.10.1
- 12. Performance Step: Record Discharge Monitor on Attachment 1 Standard: Record R-27 on Attachment 1 Comment: Procedure Step 4.1.11 5 of 10
Performance Information (Denote critical steps with a check mark ...J)
- 13. Performance Step: Record Actual Alarm Setpoint on Attachment 1 Standard: Records 3.25E+3 !-ICi/sec Comment: Procedure Step 4.1.12
- 14. Performance Step: R is less than D THEN record NA calculated alarm setpoint on Attachment 1 Standard: Records NA on Attachment 1 Comment: Procedure Step 4.1.13
- 15. Performance Step: If calculated release rate R is greater than available release rate D THEN obtain authorization for higher release rate.
Standard: Determines R is less than 0 and authorization is not required Comment: Procedure Step 4.1.14
- 16. Performance Step: If R-27 is operable THEN enter an alert setpoint at a value below current alarm setpoint at CRS discretion and record on Attachment 1.
Standard: Records any value less than 3.25E+3 I-lei/sec Comment: Procedure Step 4.1.15 6 of 10
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,j)
..J 17. Performance Step: If R-12 is operable THEN determine R-12 calculated auto closure setpoint and record on Attachment 1 Standard: R-12 Setpoint ::::: 7.0E4
- 3.53E-6
- 2.471 E-1 Comment: Procedure Step 4.1.16.1
- 18. Performance Step: IF necessary THEN adjust R-12 auto closure setpoint to less than or equal to calculated value Standard: Determines setpoint adjustment is NOT necessary Comment: Procedure Step 4.1.16.2
- 19. Performance Step: When permit is complete. THEN record NA for the following:
- Release path valve alignment verification
- Volume
- Activity
- Iodine 131 Activity
- Calculated Alarm Setpoint
- Emax
- E
- RCV-014 setting Standard: Records NA on Attachment 1 Comment: Procedure Step 4.1.17 Terminating Cue: JPM Complete 7 of 10
Appendix C Page 8 Form ES-C-1 AlTACHMENT1, ;
GASEOUS WA$:r~.ftELEASE PI;RMIT FORM (Pag.1 of 1) ,
'i;~(~T~i:
~
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'NjI,;,,*;**
.' ..... **~1*.')7.e"Jl. AcWaf:~ Setpolntl~i.'~i.~sa¥ '. J.1Cifsee
\ ..~~~~~~3!.. :. ~:~,.~.~~vsec . AIert;~n~(14) tl.ft):~~~;
R,.12AUtoC~~(~; ~ (1~~".,..:~:i~q~1;..:*";..."4,'_:.::.:-....l-'"'~,
. J1cvsec
~'j;~,.f,j.;i.;i'~ ~.i$~a~:'IHgN C~PLEre . ~~~~:.
Resu..119l;tgr ~lIoo
.\.~;{~Gs$l tJ A, . p.efl~
ANSWER KEY 8 of 10
Appendix C Page 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
9 of 10
- -........ -~------------------------
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable.
- 3. VC Pressure is 1.5 psig
- Permit Number 120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7 lJCi/cc o R-12 Current Alarm 1.5 E-6 !-ICi/cc o R-14 Current Reading 9.948E-7 !-ICi/cc o R-14 Current Alarm 1.5E-5 !-ICi/cc o R-15 Current Reading 1.32 E-6 !-ICi/cc o R-27 Current Reading 10.0 lJCi/sec o R-27 Current Alarm 3.25 E+3 !-ICi/sec o Plant Vent Sample 1.85 E-5 !-ICi/cc Plant Vent Flow 3.21 E+4 scfm Condenser Air In leakage 5.8 scfm Initiating Cue:
You are the BOP operator and the CRS has directed you to perform a manual VC Pressure Relief Gaseous Release Permit in accordance with 3-S0P-WDS 013.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 2000070132 Task
Title:
Review a Quadrant Power Tilt Calculation by Hand 1940012125 KIA
Reference:
SRO - 4.2 Job Performance Measure No: SRO Admin 1 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- Plant is at 100% power BOL.
- The Control Room personal computer is unavailable.
- A Reactor Operator performed an Manual Quadrant Power Tilt Ratio Calculation
- The Reactor Operator recommended a 9% power reduction.
Task Standard: QPTR properly calculated.
Required Materials: Calculator, GRAPH-NI-2 General
References:
3-S0P-RPC005A, GRAPH-NI-2 Initiating Cue: You are Spare SRO and The SM directed you to REVIEW a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC OOSA. Determine if RO recommendation is accurate.
Time Critical Task: No 1 of 13
Appendix C Job Performance Measure Form ES-C-1 Validation Time: 45 minutes 2 of 13
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ",j)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-RCP-005A Comment:
- 2. Performance Step: Review Note before Step 1 Standard: Reviews Note Comment:
- 3. Performance Step: ENSURE appropriate meter range for detectors A and B, for each operable NIS Power Range Channel Standard: Ensures range meter indication between 1/3 and 2/3 of full scale Comment: Attachment Step 1.0 3 of 13
Form Performance Information (Denote critical steps with a check mark v)
- 4. Performance Step: Record the following current information:
Standard: Records the following on Attachment 1
- Date T odays Date
- Time Current Time
- % Power Indicated Power Comment: Attachment Step 2.0
- 5. Performance Step: RECORD UPPER and LOWER detector currents on operable NIS Power Range drawers Standard: Reviews Table 1 Entries - All Correct Comment: Provide the Candidate with detector currents for use in the remainder of the JPM Attachment Step 3.0
- 6. Performance Step: If power range current amp is unavailable Standard: This step is Not Applicable Comment: Attachment Step 3.1 4 of 13
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
..J 7. Performance Step: CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps by full power zero axial offset detector current from 3 GRAPH-NI-2 Standard: Reviews entered data and calculate corrected detector current ratios 41 Upper 799/790=1.011 41 Lower 823/850=0.968 42 Upper 818/825=0.991 42 Lower 843/822=1.026 43 Upper 875/890=0.983 43 Lower 873/875=0.998 44 Upper 832/830=1.002 44 Lower 896/910=0.985 Identify incorrect values used for 41 and 42 lower detector actual currents (Channel 41 current was entered in Channel 42 location and vice versa)
Comment: Attachment Step 4 5 of 13
Performance Information (Denote critical steps with a check mark -V)
- 8. Performance Step: DETERMINE both upper and lower Average Normalized Ratios Standard: CALCULATE average normalized ratios for Upper detectors:
= 41U + 42U + 43U + 44U = 1.011+0.991+0.983+1.003 4 4
= 0.995 CALCULATE average normalized ratios for Lower detectors:
= 41L+42L+43L+44L = 0.968+1.026+0.998+0.985 4 4
= 0.994 The actual calculated value for the lower average normalized ratio is the same as the correctly calculated value. This is coincidence.
Comment: Attachment Step 5 6 of 13
Appendix C Page 7 Performance Information (Denote critical steps with a check mark ..J)
"9. Performance Step: DETERMINE both upper and lower Quadrant Power Tilt as follows Standard:
= Highest Ratio of 41 U + 42U + 43U + 44U = 1.011 Average Ratio 0.997
=1.014
= Highest Ratio of 41 L + 42L + 43L + 44L = 1.026 Average Ratio (Step 6.2) 0.994
= 1.032 Identifies that based on earlier mistake QPTR is incorrectly calculated. Actual QPTR is 1.014.
Comment: Values obtained by the candidate may vary depending on how decimal places they carry.
Attachment Step 6.0
- 10. Performance Step: Record Highest Quadrant Power Tilt calculated Standard: Observes 1.032 on attachment 1 is incorrect value Comment: Attachment Step 7.0 7 of 13
Form Performance Information (Denote critical steps with a check mark -I)
V11. Performance Step: If Quadrant Power Tilt exceeds 1.02 in either top or bottom of core ...
Standard: Determines actual QPTR does not exceed 1.02 Determine RO power reduction recommendation is NOT correct. No reduction in power is necessary.
Comment: Attachment Step 8.0 Terminating Cue: JPM Complete 8 of 13
Appendix C Page 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
9 of 13
Appendix C Simulator Setup Form ES-C-1 Set Simulator to any At Power IC.
10 of 13
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- Plant is at 100% power BOL.
- The Control Room personal computer is unavailable.
- A Reactor Operator performed an Manual Quadrant Power Tilt Ratio Calculation
- The Reactor Operator recommended a 9% power reduction.
Initiating Cue:
You are Spare SRO and The 8M directed you to REVIEW a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of 80P-RPC-OOSA. Determine if RO recommendation is accurate.
_p.ppendix C Initial Conditions Form ES-C-1 Actual Detector Currents Channel Top Bottom 41 799 843 42 818 823 43 875 873 44 832 896
Appendix C Initial Conditions Form ES-C-1 3-GRAPH-NI-2 Rev. 19X NIS FULL POWER DETECTOR CURRENTS (pA)
Cycle 17 (Values updated based on 17C20 flux map at 99.9% RTP)
FACE PLATE CURRENT Channel TOP BOTTOM N41 790 850 N42 825 822 N43 890 875 N44 830 910 IR DETECTOR CURRENT LIMITS FOR USE IN 3-POP-1.3 N35 Current limit (Amps) N36 Current limit (Amps) 4%RTP 0.85 E-05 1.72 E-05 8%RTP 1.70 E-05 3.44 E-05 Written By: Signature Reviewed By: Signature Approved By Signature Effective Date: Today's Date
No: 3-S0P-RPC-OOSA Rev: S QUADRANT POWER TILT CALCULATIONS Page 10 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 1 of 4)
NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 of full scale.
1.0 ENSURE appropriate meter range is selected for detectors A and B, for each operable NIS Power Range channel.
2.0 RECORD the following current information:
Date -rOOM{ Time JJDlJ % Power l oll7o 3.0 RECORD individual upper and lower Power Range detector currents indicated on each operable NIS Power Range drawer in the following Table 1:
NOTE Enter "0", if one power range channel is out of service.
TABLE 1 I POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 1'1'1 g4~
42 iif gj.~
43
~1S" t13 44 g~:1. tttc,
No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT CALCULATIONS Page 11 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 2 of 4)
WARNING Electrical shock hazard inside drawer.
3.1 !E power range current amp is unavailable, THEN:
3.1.1 CONTACT I&C to obtain a DVM current reading for the appropriate drawer.
3.1.2 RECORD DVM reading(s) in Table 1 of Step 3.0.
4.0 CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2, NIS Full Power Detector Currents):
Indicated 3-Graph-NI-2 Normalized Detector Indicated 3-Graph-NI-2 Normalized Detector Current Current Ratio Current Current Ratio 41 Upper 74~ + Jqo = 41 Lower ~~~ + fj5Q = D.*Q'8 42 Upper 81~ + aZI) = 42 Lower 8~~ + ~.:l :J. = II ~ . :1I.
43 Upper i1~ + i~Q = 43 Lower ~1~ + a1{" = ~I~~
44 Upper tl3~ + ~~ = 44 Lower M~ + ~l~ = D. !~~
i No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 1 2 of 13 ATTACHMENT 1 ,
MANUAL QUADRANT POWER TILT CALCULATION (Page 3 of 4) 5.0 DETERMINE both upper and lower Average Normalized Ratios as follows:
NOTE When Reactor Power is less than or equal to 75%, then 3 NIS power ranqe channels can be used. (Reference 5.2.2) If ONLY 3 NIS power range channels are in service, then "0" is entered for the inoperable channel, AND the sum of the currents is divided by 3.
5.1 CALCULATE average normalized ratio for Upper detectors:
41U + 42U + 43U + 44U
=
- See note above 3* or 4* 4-5.2 CALCULATE average normalized ratio for Lower detectors:
41L + 42L + 43L + 44L
=
3* or 4* 4
- See note above previous sub-step NOTE
- Upper Quadrant = Highest Normalized Ratio for Upper Detector (Step 4.0)
Power Tilt Average Normalized Ratio for Upper Detector (Step 5.1)
- Lower Quadrant = Highest Normalized Ratio for Lower Detector (Step 4.0)
Power Tilt Average Normalized Ratio for Lower Detector (Step 5.2) 6.0 DETERMINE both upper and lower Quadrant Power Tilt as follows:
6.1 CALCULATE Quadrant Power Tilt for Upper detectors:
HighestRatioof41U,42U,43U,or44U = '.011
Average Ratio (Step 5.1) 6. c¥i1 6.2 CALCULATE Quadrant Power Tilt for Lower detectors:
Highest Ratio of 41 L, 42L, 43L, or 44L
= Average Ratio (Step 5.2)
=
No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT CALCULATIONS Page 13 of 13 ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 4 of 4) 7.0 RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2:
Highest Quadrant Power Tilt: _ _...:....r,_()--'1L-~
8.0 !E Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY requirements of LCO 3.2.4 are met
- ENTER calculated Quadrant Power Tilt in the Narrative Log 9.0 REVIEW Attachment 1 for satisfactory completion:
I Control Room Supervisor Date I Time I
Shift Manager Date I Time 10.0 WHEN complete, THEN FORWARD this Quality Record to the Operations Department Records Custodian.
Signature Date
~Entergy Nuclear Northeast Procedure Use Is:
Ii'J Continuous o Reference Control Copy: _ _ __
Effective Date: - - -
o Information Page 1 of 15 3-S0P-RPC-OOSA, Revision: S QUADRANT POWER TILT CALCULATIONS Approved By:
I Procedure Sponsor, RPOI Desi nee Date Team 3D Procedure Owner EDITORIAL REVISION
No: 3-S0P-RPC-005A Rev:5 I QUADRANT POWER TILT CALCULATIONS L ____________________..l...--Pa_g_e_2_0_f_1_3_ _ _ _ __
REVISION
SUMMARY
(Page 1 of 2) 1.0 REASON FOR REVISION 1.1 Updated to eliminate poor practices and ensure procedure contains proper level of detail.
2.0
SUMMARY
OF CHANGES 2.1 Moved and revised former Step 1.2, of Purpose, to Step 2.2.1 of P&Ls, General Information (Editorial 4.6.13).
2.2 Moved and revised former Step 1.3, of Purpose, to Step 2.2.2 of P&Ls, General Information (Editorial 4.6.13).
2.3 Deleted former P&L 2.1 regarding RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12).
2.4 Split Section 2, Precautions and Limitations, into 2 parts: 2.1, Precautions and Limitations and 2.2, General Information (Editorial 4.6.10).
2.5 Added P&L 2.1.1 regarding use of uncorrected detector outputs to be consistent with Unit 2 procedure (Editorial 4.6.11).
2.6 Added P&L 2.2.3 regarding short term Tilt spikes with alarm actuation fol/owing RCS boron changes to be consistent with Unit 2 procedure (Editorial 4.6.11).
2.7 Added "IF Reactor Power is less than or equal to 75%, THEN" to Step 3.1 to clarify SR 3.2.4.1 (Editorial 4.6.13).
2.8 Deleted former Step 3.2 regarding reactor power being greater than 50%. Per Reactor Engineering, QPTR can be performed at lower power, but becomes less accurate (Editorial 4.6.12).
2.9 Added Step 3.2 "IF Reactor Power is greater than 75%,
THEN VERIFY aI/ four NIS channel upper and lower detectors are in service" to clarify SR 3.2.4.1 (Editorial 4.6.11) 2.10 Added Note prior to Step 4.1 regarding normalization factors not being available fol/owing refueling or detector maintenance (Editorial 4.6.11).
2.11 Split Section 4.1 into two parts: 4.1, Manual Quadrant Power Tilt Calculation and 4.2, Computer Network Program Quadrant Power Tilt Calculation (Editorial 4.6.14).
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 3 of 13 (Page 2 of 2) 2.12 Changed Step 4.2.8 from "SELECT" to "ENTER" and deleted bullet regarding clicking "OK" and appropriate option button as there are no 'select' options (Editorial 4.6.13).
2.13 Added 2 bullets to Note prior to Step 4.2.8 to clarify when 3 or 4 operable NIS Power Range channels are used (EditoriaI4.6.11).
2.14 Deleted former Step 4.1.13 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12).
2.15 Deleted former Steps 4.1.14.2,4.1.14.3 and 4.1.14.4 as these are all included in Tech Spec 3.2.4 (EditoriaI4.6.12).
2.16 Added bullet to Step 4.2.13 to enter calculated Quadrant Power Tilt in the Narrative Log (Editorial 4.6.11).
2.17 Added Reference 5.2.2, SR 3.2.4.1 (Editorial 4.6.4).
2.18 Deleted former Reference 5.3.1, RA-11.1, as it is no longer mentioned in procedure (Editorial 4.6.12).
2.19 Added Reference 5.6.1, 0-NF-303, Core Quadrant Power Balance as an Interface Document (Editorial 4.6.11).
2.20 Added Reference 5.7.1 UFSAR Section 7.6.2 (Editorial 4.6.11).
2.21 Deleted former Step 4.0 of Attachment 1 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met {Editorial 4.6.12).
2.22 Added "when Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used" to Note in Step 5 of Attachment 1 to clarify when 3 operable NIS Power Range channels can be used (Editorial 4.6.13).
2.23 Added bullets to Step 8.0 of Attachment 1 to verify requirements of LCO 3.2.4 are met, notify CRS and SM and to enter QPTR in the Narrative log (Editorial 4.6.11).
2.24 Changed Step 10.0 of Attachment 1 to forward Attachment 1 to Operations Staff to simplify the action. Placing in Operations Log binder has the same result of forwarding to Operations Staff (Editorial 4.6.13).
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 4 of 13 TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ................................, ........................................................................................ 6 2.0 PRECAUTIONS AND LIMITATIONS ................................................................................. 6 3.0 PREREQUISITES .............................................................................................................. 6 4.0 PROCEDURE .................................................................................................................... 7 4.1 Manual Quadrant Power Tilt Calculation .................................................................... 7 4.2 Computer Network Program Quadrant Power Tilt Calculation ................................... 7
5.0 REFERENCES
................................................................................................................ 10 6.0 RECORDS AND DOCUMENTATION .............................................................................. 10 Attachments ATIACHMENT 1 MANUAL QUADRANT POWER TILT CALCULATION ................................ 12
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 5 of 13 1.0 PURPOSE 1.1 This procedure provides guidance for the preparation of quadrant power tilt calculations in accordance with Technical Specification surveillance requirement SR 3.2.4.1.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions and Limitations 2.1.1 Uncorrected detector outputs SHALL NOT be used to calculate quadrant power tilt because they do NOT represent relative core power in their associated quadrant.
2.2 General Information 2.2.1 WHEN in MODE 1 with greater than 50 percent of rated thermal power AND quadrant power tilt exceeds 1.02, THEN VERIFY QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (Reference 5.2.11 2.2.2 WHEN in MODE 1 with greater than 50 percent of rated thermal power AND either one upper OR lower quadrant power tilt alarm monitors are inoperable, THEN verify QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND after load change greater than 10 percent of rated power.
(Reference 5.2.31 2.2.3 Short term Quadrant Power Tilt calculation spiking with possible Plant Computer System alarm actuation can occur immediately following Reactor Coolant System (RCS) boron changes. These short term spikes, (approximately five minutes duration), should not be considered significant, as they are transitory in nature.
3.0 PREREQUISITES 3.1 IF Reactor Power is less than or equal to 75%,
THEN VERIFY a Minimum of three NIS channel upper and lower detectors are in service. (Reference 5.2.2) 3.2 IF Reactor Power is greater than 75%,
THEN VERIFY all four NIS channel upper and lower detectors are in service.
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 6 of 13 4.0 PROCEDURE NOTE Following refueling or detector maintenance, prior to performance of initial at-power incore flux mapping operations. NIS detector current output normalization factors will not be available. During this period. NIS detector current outputs must be logged as required below. but quadrant tilt calculations cannot be performed.
4.1 Manual Quadrant Power Tilt Calculation 4.1.1 IF desired to perform a manual calculation, THEN GO TO AnACHMENT 1. MANUAL QUADRANT POWER TILT CALCULATION.
4.2 Computer Network Program Quadrant Power Tilt Calculation NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 of full scale.
4.2.1 VERIFY appropriate meter range is selected for detectors A and B for each operable NIS channel.
4.2.2 RECORD the individual upper and lower power range detector currents indicated on each operable NIS Power Range drawer in the following table:
TABLE POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 42 43 44
No: 3-S0P-RPC-00SA Rev:sl QUADRANT POWER TILT CALCULATIONS Page 7 of 13 I
~.--------------------------------------~------------------~
WARNING Electrical shock hazard inside drawer.
4.2.2.1 IF a power range detector current amp reading is unavailable, THEN:
a) CONTACT I&C to obtain a DVM current reading for the appropriate drawer.
b) RECORD DVM reading(s) in the Table provided in Step 4.2.2.
4.2.3 ACCESS the QPTR Program (\\ipcfsetsp002\OPERATIONS\OPS General\IP3\Software\Unit 3\QPTR\QPTR.exe).
4.2.4 IF the network is unavailable AND CCR computer is operational, THEN:
4.2.4.1 OBTAIN the QPTR Program CD from Shift Manager's office.
4.2.4.2 INSERT CD in a CCR computer AND OPEN QPTR Program.
4.2.S CLICK the "Click Here to Start" button to retrieve 100% NIS currents from 3-Graph-N 1-2.
4.2.6 COMPARE the latest NIS currents against the 3-Graph-NI-2 values.
4.2.6.1 IF the 100% NIS currents do not match 3-Graph-NI-2, THEN CLICK the "No" button AND ENTER 100% currents and 3-Graph-NI-2 revision number in the text boxes when prompted.
4.2.6.2 IF the 100% NIS currents match the latest revision of 3-Graph-NI-2, THEN click the "Yes" button.
4.2.7 WHEN prompted, THEN ENTER today's date, the current time and the current % power.
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 8 of 13 NOTE This program can be used for either 3 or 4 operable NIS Power Range channels.
- Three operable NIS Power Range channels can be used when Reactor Power is less than or equal to 75%. (Reference 5.2.2)
- All four operable NIS Power Range channels are required when Reactor Power is greater than 75%
4.2.8 ENTER the correct number of operable NIS Power Range channels.
4.2.9 ENTER appropriate NIS information from Table of Step 4.2.2 in the white text boxes.
4.2.10 !E a power range channel that is out of service, THEN ENTER "0" for the applicable channel in the white text boxes.
4.2.11 CLICK on the CALCULATE QPTR button to show the current QPTR.
4.2.12 CLICK on the PRINT RESULTS button to obtain computer printout of the quadrant power tilt calculation.
4.2.13 IF Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY requirements of LCO 3.2.4 are met.
- ENTER calculated Quadrant Power Tilt in the Narrative Log.
4.2.14 WHEN QPTR calculation program is no longer required, THEN CLICK "Quit Program".
4.2.15 OBTAIN CRS and SM signatures for the completed QPTR printout.
4.2.16 PLACE completed QPTR computer printout in Operations Log binder.
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 9 of 13
5.0 REFERENCES
5.1 Commitment Documents 5.1.1 None 5.2 Technical Specifications:
5.2.1 LCO 3.2.4 Action Statement 5.2.2 SR 3.2.4.1 5.2.3 TRO 3.2.A Action Statement 5.3 Development Documents 5.3.1 None 5.4 Historical Development Documents 5.4.1 3PT-W022 , Quadrant Power Tilt Calculation 5.5 Drawings 5.5.1 None 5.6 Interface Documents 5.6.1 O-NF-303, Core Quadrant Power Balance 5.6.2 3-Graph-NI-2, NIS Full Power Detector Currents 5.7 UFSAR reference 5.7.1 Section 7.6.2 6.0 RECORDS AND DOCUMENTATION 6.1 Records 6.1.1 The following required records resulting from this procedure are controlled and maintained in accordance with the IP3 Records Retention Schedule.
- Attachment 1, Manual Quadrant Power Tilt Calculation Sheet
- Computer-generated printout of Quadrant Power Tilt Calculation 6.2 Documentation 6.2.1 The following documentation is required to be controlled or maintained in accordance with the IPEC Records Retention Schedule:
- None
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 10 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 1 of 4)
NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 offull scale.
1.0 ENSURE appropriate meter range is selected for detectors A and B, for each operable NIS Power Range channel.
2.0 RECORD the following current information:
Date_ _ _ __ Time,_ _ _ _ _ __ % Power_ _ _ _ __
3.0 RECORD individual upper and lower Power Range detector currents indicated on each operable NIS Power Range drawer in the following Table 1:
NOTE Enter "0", if one power range channel is out of service.
TABLE 1 POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CUR 41 42 43 44
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 11 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 2 of 4)
WARNING Electrical shock hazard inside drawer.
3.1 IF power range current amp is unavailable, THEN:
3.1.1 CONTACT I&C to obtain a DVM current reading for the appropriate drawer.
3.1.2 RECORD DVM reading(s) in Table 1 of Step 3.0.
4.0 CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2, NIS Full Power Detector Currents):
Indicated 3-Graph-NI-2 Normalized Detector Indicated 3-Graph-NI-2 Normalized Detector Current Current Ratio Current Current Ratio 41 Upper + = 41 Lower + =
42 Upper + = 42 Lower + =
43 Upper + = 43 Lower 'T'
=
44 Upper 'T'
44 Lower +
No: 3-S0P-RPC-005A Rev:sl QUADRANT POWER TILT CALCULATIONS
, Page 12 of 13 AnACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 3 of 4) 5.0 DETERMINE both upper and lower Average Normalized Ratios as follows:
NOTE When Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used. (Reference 5.2.2) If ONLY 3 NIS power range channels are in service, then "0" is entered for the inoperable channel, AND the sum of the currents is divided by 3.
5.1 CALCULATE average normalized ratio for Upper detectors:
41U + 42U + 43U + 44U
=
3* or 4*
- See note above 5.2 CALCULATE average normalized ratio for Lower detectors:
41L + 42L + 43L + 44L
= 3* or 4*
- See note above previous sub-step NOTE
- Upper Quadrant = Highest Normalized Ratio for Upper Detector (Step 4.0)
Power Tilt Average Normalized Ratio for Upper Detector (Step 5.1)
- Lower Quadrant = Highest Normalized Ratio for Lower Detector (Step 4.0)
Power Tilt Average Normalized Ratio for Lower Detector (Step 5.2) 6.0 DETERMINE both upper and lower Quadrant Power Tilt as follows:
6.1 CALCULATE Quadrant Power Tilt for Upper detectors:
Highest Ratio of 41U, 42U, 43U, or44U = ___
Average Ratio (Step 5.1) 6.2 CALCULATE Quadrant Power Tilt for Lower detectors:
=
Highest Ratio of 41 L, 42L, 43L, or 44L = ___ =
Average Ratio (Step 5.2)
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 13 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 4 of 4) 7.0 RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2:
Highest Quadrant Power Tilt_ _ _ _ _ _ _ _ _ _ _ __
8.0 !E Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY requirements of LCO 3.2.4 are met
- ENTER calculated Quadrant Power Tilt in the Narrative Log 9.0 REVIEW Attachment 1 for satisfactory completion:
I Control Room Supervisor Date I Time I
Shift Manager Date I Time 10.0 WHEN complete, THEN FORWARD this Quality Record to the Operations Department Records Custodian.
Signature Date
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Task No: 2000100132 Task
Title:
Review Deborating Demineralizer In-Service Time Calculation 2.1.25 Job Performance Measure KIA
Reference:
SRO -- 4.2 No: SROAdmin2 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- A Deborating Demineralizer In-Service Time Calculation was prepared by the Spare RO
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmrF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
Task Standard: In-Service Time properly calculated.
10f6
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials: Calculator Procedure General
References:
3-S0P-CVCS-004 Initiating Cue: You are a spare SRO and the SM has directed you to review the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4.
Time Critical Task: No Validation Time: 45 min 20f6
_A-Jp'-'p_e_n_di_x_c_ _ _ _ _ _ _ _ _.. . .. .: . .P. : : a""g-=-e..: : 3_ _ _ _ _ _ _ _ _::-Fo:::..;.r.:..;;.m::-E=-S-=--~C:_-.::._1 Performance Information (Denote critical steps with a check mark ;/)
- 1. Performance Step: Calculate the change in Tavg on Attachment 1 Standard: Ll Tavg =TF - TI L'1 Tavg =569°F - 568°F
~ Tavg =1°F Calculation is correct Comment: Procedure Step 4.3.4.3
- 2. Performance Step: Calculate the change in RCS Boron Concentration for the change in Tavg on Attachment 1 Standard: L'1 B =Ll Tavg
- IBW L'1 B =1°F * -33.4 pcmrF*-O.1074 ppmlpcm
~ B = 22.1 ppm Calculation is correct Comment: Procedure Step 4.3.4.4
- 3. Performance Step: Calculate Boron Efficiency for selected deborating demineralizer Standard: BE =1 - (BO/BI)
BE =1 - (14/98)
BE =.86 Clculation is correct Comment: Procedure Step 4.3.1.1 30f6
Performance Information (Denote critical steps with a check mark ...J)
-v 6. Performance Step: Calculate G - gallons of water using Graph CVCS-3 Standard: From Nomograph - 20,000galions This is NOT the correct value Comment: Procedure Step 4.3.4.5. This value can be obtained if candidate uses 30 ppm for boron concentration change
-v 7. Performance Step: Calculate the Deborating Demineralizer in-service time Standard: =
T G / (LF
- BE)
T = 20,00gallons / (84 gallons/min
- 0.86)
T =276.8 minutes This is NOT the correct value due to incorrect G from previous step.
Comment: Procedure Step 4.3.4.5 Terminating Cue: "IPM Complete 4 of6
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __
50f6
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- A Deborating Demineralizer In-Service Time Calculation was prepared by the Spare RO
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmrF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
Initiating Cue:
You are a spare SRO and the SM has directed you to review the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4.
PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 19 of 37 CAUTION When more than one unsaturated demineralizer is placed in service at the same time.
then the margin to cold shutdown boron must be evaluated by chemistry.
4.3.4 Determining Deborating Demineralizer In-Service Time 4.3.4.1 IF RCS has been borated to cold shutdown +100 ppm boron concentration AND the Reactor Trip Breakers are OPEN, THEN GO TO Step 4.3.5 to place Deborating Demineralizer(s} in service as required (aSSist in crud burst cleanup).
4.3.4.2 IF RCS Boron Concentration is less that 3 PPM AND Reactor Power is less than 99%,
THEN GO TO Step 4.3.5 to place Deborating Demineralizer in service as required.
NOTE This method is intended for use at approximately 100% power due to the basis for Attachment 2, Inverse Boron Worth vs Boron Concentration.
4.3.4.3 CALCULATE the change in Tavg required on Attachment 1 as follows:
6 Tavg = TF - TI. where 6 T avg = Required change in T avg (OF)
TF= Final Tavg(OF)
TI = Initial Tavg(OF)
PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 20 of 37 4.3.4.4 CALCULATE the change in RCS Boron concentration for the change in Tavg on Attachment 1 as follows:
dB = d Tavg It ITC
=
ITC At Power Isothermal Temperature Coefficient for the initial Tavg{pcmJoF), from Graph RV-5B
=
IBW Inverse Boron Worth (ppmJpcm) for the initial ReS Boron concentration, from Attachment 2, Inverse Boron Worth VS Boron Concentration 4.3.4.5 CALCULATE the Deborating Demineralizer in-service time on Attachment 1 as follows:
T =G I (LF
- BE), where T = required Deborating Demineralizer in-service time (Min)
=
G Amount of dilution water required for the change in boron concentration (gals),from Graph CVCS-3, (Dilution Nomograph for Hot ReS 580°F) or CCR computer.
LF = Letdown Flow (gpm), from FI-134 BE = Boron Efficiency for the selected Deborating Demineralizer 4.3.4.6 PLACE completed Attachment 1, Deborating Demineralizer In-service Time Calculations, in Daily Log Binder for Operations Staff to review and file.
PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 36 of 37 ATTACHMENT 1 DEBORATING DEMINERALIZER IN-SERVICE TIME CALCULATIONS (Page 1 of 1) 4.3.4.3 Required change in Tavg:
4.3.4.4 Change in RCS Boron concentration:
-....;;...~:..=~.;.....:..,_ =_ _,_ _ _ .. _"._3 .....3"""-'..--.:.~_ _ 11 - 0.'/) 1t./
6 B (ppm) 6 T avg (OF) ITe (pcm/OF) IBW (ppm/pcm) 4.3.1.1 Boron Efficiency for Deborating Demineralizer:
3l OIOQ 'TODAy Bed No. Sample Time Sample Date
_.8"--(,,,=--_ = 1 - (14 I ~f! )
BE BO (ppm) BI (ppm) 4.3.4.5 Deborating Demineralizer in-service time:
= ~q DOO I( ~ c.f 11 0
- S, )
G (gal) LF (gpm) BE
25 I
No: 3-S0P-CVCS-004
- _JV:
PLACING THE CVCS DEMINERALIZERS IN OR OUT OF SERVICE Page: 37 of 37 ATTACHMENT 2 INVERSE BORON WORTH VS BORON CONCENTRATION (Page 1 of 1)
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..().10a 0 10 20 30 40 50 60 70 80 90 100 Boron Concentration (PPM)
Unit 3 Rev. 0 DILUTION NOMOGRAPH 10 FOR 10 t'tOT ReS 580 0 20 20 30 40 50 60 70 50
-"~'--- 100 200 100 500 200 800 1000 ".
300 10 . 2000 500 5000 100 10,000 1000 20,000 2000 1000 50,000 2000 100,000 3000 3000 PPM BORON PPM BORON DILUTION 1M COOLANT DILUTION WATER GAL.
Reviewed By' K ~~ _
cvcs- 3
. Approved By :~~\\-~~"'f'f paqe 3 of 9 J Section 4
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 2000390131 Task
Title:
Review a Tagout 1940012213 Job .....""'.,.,.....,n"I Measure KIA
Reference:
SRO - 4.3
~~----~---------
No: SROAdmin 3 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator - - - - - - - Plant ------
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tagout boundary
- An RO prepared a manual tagout for 33 Charging Pump Task Standard: Manual Tagout Reviewed and errors located Required Materials: None General
References:
EN-OP-102, Protective and Caution Tagging 3-COL-CVCS-001 Chemical and Volume Control System EN-OP-102-1, Protective and Caution Tagging Forms & Checklists 9321-F-27363 Flow Diagram Chemical and volume Control System Sheet 1 1 of 11
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are a spare 8RO and the 8M has directed you to review a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.
Time Critical Task: No Validation Time: 45 minutes 2 of 11
Initial Conditions Performance Information (Denote critical steps with a check mark >/)
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains EN-OP-102 and EN-OP-102-01 Comment:
- 2. Performance Step: Ensure requirement of Attachments 9.1 and 9.2 of EN OP-102 are followed Standard: Review Attachment 9.1 and 9.2 Comment: Procedure Step 5.3 [1]
- 3. Performance Step: Review Scope of Work Standard: Tagout Required for emergent work.
Given in Initial Conditions Comment: Procedure Step 5.3 [2]
- 4. Performance Step: Determine Safe Work Boundary for 33 Charging Pump Seal Replacement Standard: Review Plant Prints 9321-F-27363 Comment: Procedure Step 5.3 [2] (g)
Appendix C Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark "'./)
- 5. Performance Step: Boundary Valves should be reviewed outstanding deficiencies Standard: No deficiencies exist on valves identified in tagout boundary - Given in Initial Conditions CUE: No deficiencies exist on valves identified in tagout boundary Comment: Procedure Step 5.3 [3]
-:r6.Performance Step: Utilizing the Isolation Boundaries, Review the tagout and identify the following errors:
- Valve CH-409 Charging Pump Recirc Valve was NOT included on Tagout
- Valve CH-284 Charging Pump Inlet Isolation Restoration Configuration is CLOSED
- CH-1175D Charging Pumps Suction Line Drain Placement Configuration should be OPEN
- CH*1175D Charging Pumps Suction Line Drain Restoration Configuration should be CLOSED Standard: See Attached Answer Key Comment:
Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
Key Elements From Attachment 9.2 Tagging Sequence
- All Tagouts require tags to be hung and cleared in the order specified on the Tag Hang sheet or Tags To Be Removed sheet. When no definitive order is required for certain components of a T agout, the Operations Supervisor may specify a given order number for multiple components (e.g., multiple components listed on the Tagout may be given order number "5" when their sequence relative to each other is not important).
- Recommended tagging order for pumps A. Control switch B. Breaker for main power C. Breakers for auxiliary power (motor heater, oil pumps, etc.)
D. Discharge valve E. Suction valve F. Other components within scope of Tagout Terminating Cue: JPM Complete
ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE: 3C20 MANUAL,_ _ __ TAGOUT: SI-038 Tag Tag Equipment Place, Place. Rest. 1st Rest. 2nd Placement!
Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Equipment Location Seq. ConfiQuration [)atem~ ~CltefTime _~E:'L COQfiguration DatefTime ...-RClteJIiI"l'lE:
~~ --------
Tao Notes 33 Charging Pump Pullout I
1 Danger Control Switch 1 Or CRITICAL Auto I I
Pull to Lock rCR , , - , , " - ------
33 Charging Pump 2 Danger Breaker Control Fuses 2 Removed/Off Installed/On 480V Room Bus 5A ,,-- --------
33 Charging Pump I Racked In 3 Danger Breaker 3 Racked Out 1480V Room Bus 5A ,,--"',
\-'---"
~H-236 33 Charging Pump Outlet solation Open 4 Danger 4 Closed
~3 Charaina Pump Cell -------- "
~H-238 33 Charging Pump Outlet solation to Seal Injection Open 5 Danger 5 Closed 33 Charaina Pump Cell -------- -" ,,---,
~H_409 33 Charging Pump Dange Recirculation Isolation Open 6 6 Closed CRITICAL r
33 Charging Pump Cell -----
CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation Open 7 Danger 7 Closed 33 Charging Pump Cell ------- ---" "-,,
,,----, "" -" "----,, ~" "----,,
CH-284 33 Charging Pump Inlet solation Open 8 Danger 8 Closed CRITICAL 33 Charaina Pump Cell --------
CH_418 33 Charging Pump Suction Stabilizer Drain Closed 9 Danger 9 Open 33 Charaina Pump Cell -------- ,,- "---"',.- -" ,,---, ------ '" ,--" "-,,
~H-1175D 33 Charging Pump Suction ine Drain Closed 10 Danger 10 Open CRITICAL 33 Charaina Pump Cell -----
~H-419 33 Charging Pump Suction Stabilizer Vent Cap Cap Installed 11 Danger 11 Cap Removed
~<::har~P~ Cell ------ ----- . ",L__" . . . , , _ ' --------- L". -------
ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: 3C20 MANUAL,_ _ __ TAGOUT: 81-038
-PH419 33 Charging Pump Suction Stabilizer Vent 12 Danger 12 Open Closed b3 Charging Pump Cell
~H-103 33 Charging Pump Outlet Vent 13 Danger ~ap 13 Cap Removed Cap Installed i-----~ .. b3 Charaina Pump Cell -------
~H-103 33 Charging Pump Outlet Vent 14 Danger 14 Open Closed (33 Charging Pump Cell ----- 1----....._...
- -I--
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tagout boundary
- An RO prepared a manual tagout for 33 Charging Pump Initiating Cue:
You are a spare SRO and the SM has directed you to review a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.
ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: 3C20 MANUAL CH-038 TAGOUT: _ _ _ _ _ __
...... ~
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement!
Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Equioment Location SeQ. Configuration DatefTime DatefTime S~CL ConfiQuration DatefTime DatefTime Tag Notes
~3 Charging Pump Pullout 1 Danger ~ontrol Switch 1 Or Auto Pull to Lock k:;CR --.---- ......* ..._
~3 Charging Pump 2 Danger Breaker Control Fuses 2 Removed/Off Installed/On 480V Room Bus 5A _._
33 Charging Pump 3 Danger Breaker 3 Racked Out Racked In 1480V Room Bus 5A --------
f.-H-236 33 Charging Pump Outlet solation Open 4 Danger 4 Closed 133 Charaino Pump Cell ---------
",H-238 33 Charging Pump Outlet solation to Seal Injection 5 Danger 5 Closed Open 133 Charaino Pump Cell ------
~H-281 33 Charging Pump Relief and
~ecirculation Line Outlet Isolation Open 6 Danger 6 Closed 133 Charging Pump Cell --.--- .... f---..--- -------
~H-284 33 Charging Pump Inlet Isolation I 7 Danger 7 Closed Closed 133 Charaino Pump Cell --------- ......- --------- ...... _._- --------
",H-418 33 Charging Pump Suction Stabilizer Drain Closed 8 Danger 8 Open 33 Chargina Pump Cell l;H-1175D 33 Charging Pump Suction ine Drain 9 Danger 9 Closed Open 33 Charging Pump Cell ------
CH-419 33 Charging Pump Suction Stabilizer Vent Cap Cap Installed 10 Danger 10 Cap Removed 133 Charaina Pump Cell --------
f.-H-419 33 Charging Pump Suction Stabilizer Vent 11 Danger 11 Open Closed 133 Chanling Pump Cell -------- ...- ------ ..._L.__
ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: 3C20 MANUAL CH-038 TAGOUT: _ _ _ _ _ __
~~~~~- ~~~~~-
""H::103 33 Charging Pump Outlet Vent 12 Danger ~ap 12 Cap Removed Cap Installed
~3 Charging Pump Cell ------ ~~~- ~~~-
~H-103 33 Charging Pump Outlet Vent 13 Danger 13 Open Closed 33 Charging Pump Cell
---~------~--~-
~MICAL AND VOLUME CONTROL No:3-COL-CVCS-001 r--
Rev: 27 SYSTEM Page 27 of 41 Des.
Oper Actual Pos. Pos. Initial IV 2.12 Charging Pumgs 55' Elev. - PAS 2.12.1 Charging Pumps Local Control Station 31 Charging Pump Control Switch Remote 32 Charging Pump Control Switch Remote 33 Charging Pump Control Switch Remote -~--
CH-AOV-200A 45 GPM Letdown Orifice Control Switch Auto AR ~-
CH-AOV-200B 75 GPM Letdown Orifice Control Switch Auto ---
AR CH-AOV-200C 75 GPM Letdown Orifice Control Switch Auto AR a PI-142 Vent (next to charging pumps stabilizer heater panel) Shut -~-
2.12.2 31 Charging Pump Cell CH-1175B 31 Charging Pump Suction Line Drain Shut CH-278 31 Charging Pump Inlet Isolation Open CH-273 31 Charging Pump Relief and Recirculation Line Outlet Isolation LO --~~~--
CH-230 31 Charging Pump Outlet Isolation Open CH-232 31 Charging Pump Outlet Isolation to Seal Injection Open --~---
NED-275 31 Charging Pump Seal Tank Overflow Isolation Open ----.~
CH-407 31 Charging Pump Recirculation Isolation Shut --~- ---
CH-1 31 Charging Pump Strainer DIP Hi Side Isolation Shut Capped _ _~_
CH-2 31 Charging Pump Strainer DIP Low Side Isolation Shut Capped
---~.
No:3-COL-CVCS-001 Rev: 27 CHEMICAL AND VOLUME CONTROL SYSTEM Page 29 of 41 Des.
Oper Actual Pos. Pos. Initial IV 2.12 (CONTINUED)
CH-102 32 Charging Pump Outlet Vent Shut Capped CH-415 32 Charging Pump Suction Stabilizer Drain Shut CH-416 32 Charging Pump Suction Stabilizer Vent Shut Capped CH-417 32 Charging Pump Suction Stabilizer Drain Line Vent Shut Capped 32 Charging Pump Transfer Switch Normal Locked 2.12.4 33 Charging Pump Cell CH-113 Charging Pumps Discharge Header Vent Shut Capped CH-1175D 33 Charging Pump Suction Line Drain Shut CH-284 33 Charging Pump Inlet Isolation Open CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation LO CH-236 33 Charging Pump Outlet Isolation Open CH-238 33 Charging Pump Outlet Isolation to Seal Injection Open NED-280 33 Charging Pump Seal Tank Overflow Isolation Open CH-409 33 Charging Pump Recirculation Isolation Shut CH-5 33 Charging Pump Strainer DIP Hi Side Isolation Shut Capped CH-6 33 Charging Pump Strainer DIP Low Side Isolation Shut Capped CH-103 33 Charging Pump Outlet Vent Shut Capped
[ CHEMICAL AND VOLUME CONTROL SYSTEM
! No:3-COL-CVCS-001
- Page
.~I _ _ _ _30
___of_41 Rev: 27
____________ ~
Des.
Oper Actual Pos. Pos. Initial IV 2.12 (CONTINUED)
CH-418 33 Charging Pump Suction Stabilizer Drain Shut CH-419 33 Charging Pump Suction Stabilizer Vent Shut Capped ____
CH-420 33 Charging Pump Suction Stabilizer Drain Line Vent Shut Capped _~_
CH-199 Emergency Boration Line Drain (in overhead) Shut Capped 2.12.5 Charging Pump Cells Passage Way CH-229 PT-142 & PI-142 Root Isolation Open o PT-142 & PI-142 Isolation Open 2.13 Boric Acid Transfer Pumps 55' Elev. - PAB 2.13.1 31 Boric Acid Transfer Pump CH-376 Boric Acid Batch Tank Outlet Isolation Shut CH-363 31 Boric Acid Transfer Pump Primary Water Supply Isolation Shut CH-367A 31 Boric Acid Transfer Pump Batching Tank Supply Isolation Shut CH-364 31 Boric Acid Transfer Pump Suction Isolation Open CH-360 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Filter AR CH-361 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Storage Tank AR CH-355A PI*190A Isolation Open
ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE: MANUAL,_ _ _ __ TAGOUT: ______________
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement!
Serial Type Equipment Description Place. Placement 1st Verit 2nd Verif Rest. Restoration Verif Verif Removal No. Equipment Location Seq. Configuration Datefrime Datefrime Seq Configuration Datefrime Datefrime Tag Notes
+-.1 33 Charging Pump Pullout
! I I
1 I
Danger ,-,ontrol Switch CCR 1 Or Pull to Lock CRITICAL Auto I
-~
33 Charging Pump 2 Danger Breaker Control Fuses 2 Removed/Off Installed/On
~OV ~oom Bus 5A 33 Charging Pump I 3 I Danger Breaker 3 Racked Out CRITICAL Racked In I
I 480V Room Bus 5A CH*236 33 Charging Pump Outlet I
I 4
I I Danger solation 4 Closed CRITICAL Open 33 Charging Pump Cell Is l.H*238 33 Charging Pump Outlet solation to Seal Injection Danger 5 Closed CRITICAL Open 33 Charging Pump Cell l.H-409 33 Charging Pump I 6 I Danger Recirculation Isolation 33 Charging Pump Cell 6 Closed CRITICAL Open i
I ,-,H*281 33 Charging Pump Relief and Recirculation Line Outlet Isolation
~.
Danger 7 Closed Open 33 Cha~ing Pum~ Cell CH*284 33 Charging Pump Inlet solation I 8 Danger 8 Closed CRITICAL Open
~-, 33 Charging Pump Cell CH-418 33 Charging Pump Suction
~
Stabilizer Drain Closed Danger 9 Open 33 Charging Pump Cell CH-1175D 33 Charging Pump Suction I ine Drain
~~-.
Danger 10 Open Closed 33 Charging Pump Cell CH-419 33 Charging Pump Suction Stabilizer Vent Cap Cap Removed CRITICAL Cap Installed 11 Danger 11 I 33 Charging Pum~ Cell 1 ~~ ~
ATTACHMENT 9.3 TAGOUT TAGS SHEET
! CH-419 33 Charging Pump Suction Stabilizer Vent 12 Danger 12 Open Closed 33 Charging Pump Cell . .
CH-103 33 Charging Pump Outlet Vent Cap 13 Danger 13 Cap Removed CRITICAL Cap Installed
~ *...
33 Charging Pump Cell - - ... ~
--~.---~
CH-103 33 Charging Pump Outlet Vent 14 Danger 14 Open Closed 33 Charging Pump Cell
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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 2000180132 Task
Title:
Review a VC Pressure Relief Release Permit 1940012311 Job Performance Measure KIA
Reference:
SRO - 4.3
--=-=-'-=-_......."-_-- No: SROAdmin4 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom x Simulator - - - - - - Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully. the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable except R-27
- 3. VC Pressure is 1.5 psig
- Permit Number 120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7 j..ICi/cc o R-12 Current Alarm 1.5 E-6 j..ICi/cc o R-14 Current Reading 9.948E-7 j..ICi/cc o R-14 Current Alarm 1.5E-5 j..ICi/cc o R-15 Current Reading 1.32 E-6 j..ICi/cc o R-27 Current Reading OOS o R-27 Current Alarm OOS o Plant Vent Sample 1.85 E-5 j..ICi/cc Plant Vent Flow 3.21 E+4 scfm Condenser Air In leakage 5.8 scfm 1 of 12
Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: . A VC Pressure Relief Gaseous Release Permit (3-S0P-WDS 013 Attachment 1) is correctly filled out.
Required Materials: Calculator General
References:
3-S0P-WDS-013.
Initiating Cue: You are the FSS and the SM has directed you to review a manual VC Pressure Relief Gaseous Release Permit in accordance with 3 SOP-WDS-013.
Time Critical Task: No Validation Time: 25 Min 2 of 12
_A_p~p_e_n_d_ix_C
__________.___________P_age3 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-WDS-013 Review Precautions and Limitations CUE: All P&L are satisfactory to continue.
Comment:
- 2. Performance Step: Review NOTES before Step 4.1.1 Standard: Reviews Notes Comment:
- 3. Performance Step: Record VC Pressure Relief as system to be released on Attachment 1 Standard: Checks "VC Pressure Relief' entered on Attachment 1 Correct Comment: Procedure Step 4.1.1
- 4. Performance Step: Record current date/time on Attachment 1 Standard: Checks current date/time on Attachment 1 Correct Comment: Procedure Step 4.1.2 3 of 12
Performance Information (Denote critical steps with a check mark "'-1)
- 5. Performance Step: ASSIGN permit number and RECORD on Attachment 1.
Standard: Checks Permit Number entered on Attachment 1. Given in Initial Conditions Correct Comment: Procedure Step 4.1.3
- 6. Performance Step: Record current VC pressure on Attachment 1 Standard: Checks 1.5 psig on Attachment 1. Given in Initial Conditions Correct Comment: Procedure Step 4.1.4
- 7. Performance Step: VERIFY one of the following conditions satisfied:
- R-12 operable.
Standard: R-12 is operable. Given in Initial Conditions Comment: Procedure Step 4.1.5
- 8. Performance Step: Determine VC Noble Gas concentration using one of the following methods
- R-12 reading (J.l.Ci/cc)
Standard: Determines R-12 reading is available Comment: Procedure Step 4.1.6 4 of 12
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,f)
'" 9. Performance Step: If using R-12, THEN circle "R-12 Monitor" and Enter the following on Attachment 1
- R-12 reading for Concentration of Nobel Gas
(~Ci/cc)
- NA for Sample #, Date, and Time for Grab Sample Standard: Checks "R-12 Monitor" Circled Correct Observes incorrect data entered for Concentration of Noble Gas 9.948E-7 ~Ci/cc entered CRITICAL Should have entered 7.170 E-7 jJCilcc Observes "NA" for Sample #, Date and Time NOT CRITICAL Comment: Procedure Step 4.1.8
'" 10. Performance Step: Determine calculated release rate ( R) jJCi/sec and record on Attachment 1 Standard: Observes Calculation performed correctly using incorrect numbers R = (2.83E+05 cc/sec)
- 9.948E-7 fJCi/cc R= 2.81 E-1 CRITICAL Correct Calculation should be 2.02E-1 Comment: Procedure Step 4.1.9 5 of 12
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)
- 11. Performance Step: Determine available release rate 0 in !-lCi/sec with R-27 OOS and R-14 In Service (given in Initial Conditions)
Standard: Checks calculation correct (1.5E 9.948E-7)
- 3.21 E+4
- 472
= 2.12E+2 !-lCi/sec Comment: Procedure Step 4.1.10.2
'\J 12. Performance Step: Record Discharge Monitor on Attachment 1 Standard: Checks R-14 on Attachment 1 Observes R-27 entered on Attachment 1 INCORRECT Comment: Procedure Step 4.1.11
- 13. Performance Step: Record Actual Alarm Setpoint on Attachment 1 Standard: Checks 1.5E-5 !-lCi/sec Correct Comment: Procedure Step 4.1.12
- 14. Performance Step: If R is less than D THEN record NA for calculated alarm setpoint on Attachment 1 Standard: Checks NA on Attachment 1 Correct Comment: Procedure Step 4.1.13 6 of 12
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ."J)
- 15. Performance Step: If calculated release rate R is greater than available release rate D THEN obtain authorization for higher release rate.
Standard: Determines R is less than D and authorization is not required Comment: Procedure Step 4.1.14
- 16. Performance Step: If R-27 is operable THEN enter an alert setpoint at a value below current alarm setpoint at CRS discretion and record on Attachment 1.
Standard: R-27 is not operable (Given in Initial Conditions)
Comment: Procedure Step 4.1.15
- 17. Performance Step: If R-12 is operable THEN determine R-12 calculated auto closure setpoint and record on Attachment 1 Standard: Checks R-12 Setpoint = 7.0E4
- 3.53E-6
=2.471E-1 Correct Comment: Procedure Step 4.1.16.1
- 18. Performance Step: IF necessary THEN adjust R-12 auto closure setpoint to less than or equal to calculated value Standard: Checks setpoint adjustment is NOT necessary Comment: Procedure Step 4.1.16.2 7 of 12
Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- 19. Performance Step: When permit is complete, THEN record NA for the following:
- Release path valve alignment verification
- Volume
- Activity
- Iodine 131 Activity
- Calculated Alarm Setpoint
- Emax
- E
- RCV-014 setting Standard: Checks NA on Attachment 1 Comment: Procedure Step 4.1.17 Terminating Cue: ~IPM Complete 8 of 12
Appendix C Page 9 Form ES-C-1 GASEOUS WASTE RELEASES ~o 3-S0P-Woo-013 Reyo 28 L--____ ..._ _",__ _ _ _ _ _ _-'- __ P~~~~3~7~~f~5~6 . _ _____ .=J AlTACHMENT 1, GASEOUS WASTE RELEASE PERMIT FORM (Page 1 of 1)
Tank! Vi,.: I'/l",...... ,t- Current _ ,
System (1) ik I,,' f DatelTime (2) \ (/ (j ,')tfa te Concentration of Volume (4) /J /!. fe Initial Pressure (5) \. "l psig Noble Gas (C)(6)!~~~~-::::'7r1:-_!lCi/CC Grab Sample:(7) Sample # ,,J ~ Date_J./J~A,,--__ Time tJ k.
Activity (A)(a)_~w::::....:6.~_ _ _ _ _!lCi Noble Gas Iodine 131 Activity (8a) N A. ~ICi/cc
,___::r,N'e.-+ ",.1"", ,L~ VC Purge Only
~ it Wfl!~ _~'" \),,)1A.ot Calculated Release Rate (R)(9 :),!:II t- - I ",Ci/sec Available Release Rate (D)(10)J.I*'c t .1.",Ci/sec DiSChargeMonitor(11)~ ~ I'<V>ni~ Actual Alarm Selpoln! (12)1.) E" - t.::) ~ICifsec Calculated alarm setpoin! (13) ...J b. !lei/sec Alert selpolnt (14) t-J P.. jlCi/sec R-12 Auto Closure/Alarm Setpoints: Calculated (15) ;).Ll 1 C - \ llCi/cc Actual (16) 1.5E - (, llCi/cc
!E discharge monitor is OOS, THEN COMPLETE the following:
- Monitor (17) N A.. _._ placed out service @ __-""N,-,I\~__ _ __--"""-'--'--_ _
Date Time
- Vent Sample:( 15) Sample # W p". Date,_-"yt...:.:."'--_ _ Time ,J A. Results (1g) !J Is ~ICi/CC (Noble Gas)
- Vent flow rate (20) tJ '" cfm Continuous Release Rate (CR)(21),_-"t.J:..;":....:..._ _ _-lUCilsec Release Calculations verified by \""I_~~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Release Path Valve Alignment Verified (23)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
CRS/SM Discharge AuthOrized (24)_~ _ .:-:-_ _ __ Release Start \~C'I _ _~_ _
eRS/SM Time Final Pressure (26) _ _ _ _,_ _psig Release Stop (27),_ _ _- - _ _ _ __
Date Time Calculations Results: S (28) _ _ _ _ __ Emax\~~I ____________"
RCV"014 Setting (31),_ _ _ _ _ _% open Comments (32) _ __
ANSWER KEY 9 of 12
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
10 of 12
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable except R-27
- 3. VC Pressure is 1.5 psig
- Permit Number 120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7 ~Ci/cc o R-12 Current Alarm 1.5 E-6 ~Ci/cc o R-14 Current Reading 9.948E-7 ~Ci/cc o R-14 Current Alarm 1.5E-5 ~Ci/cc o R-15 Current Reading 1.32 E-6 ~Ci/cc o R-27 Current Reading OOS o R-27 Current Alarm OOS o Plant Vent Sample 1.85 E-5 ~Ci/cc Plant Vent Flow 3.21 E+4 scfm Condenser Air In leakage 5.8 scfm Initiating Cue:
You are the FSS and the SM has directed you to review a manual VC Pressure Relief Gaseous Release Permit in accordance with 3-S0P-WDS-013.
Appendix C Initial Conditions Form ES-C-1
"---.....,.~i-N-O-:-3--S0-P--W--O"-S---O-13---R-ev-:-2-a-l l " GASEOUS WASTE RE_L_E_A_S_E_S_ _..L-_ _
ATTACHMENT 1, Page 37 of 56 GASEOUS WASTE RELEASE PERMIT FORM (Page 1 of 1)
Tankl \.Ie p((,r..,..,.t' Current _
System (1) '" I,,*' Date/Time (2) \&'d(?o[J C!),V'f evil 'Ti~ Permit No" (3) FlO;) () 'f ate Time Concentration of Volume (4) fJ A. ft3 Initial Pressure (5) I* s- psig Noble Gas (C)(6) q.ti..Jf;f- 7 ~Cl/cc Grab Sample:(7) Sample 1'..1 t.. Date_~r-J==--A,::.!.--_ _ Time tJA.. ~2~
Activity (A)(8),_~W...:-/l._ _ _ _ _ _ ~lCi Noble Gas Iodine 131 Activity (8a) tJ A. )J.Ci/cc VC Purge Only Calculated Release Rate (R)(9) ).l! I £- -I IlCi/sec Available Release Rate (D)(10)J.I*lct,l.~lCi/sec Discharge Monitor (11)_--'-"2:..-.... J'>-1-'--____ Actual Alarm Setpoint (12) !. 5 E" - i.=) pCI/sec Calculated alarm setpoint (13)_...:-N~'_t:._ _ _ ~Ci/sec _ _ _ ~Cilsec Alert setpoint (14) _ _---:..r-J-=--f\
R-12 Auto Closure/Alarm Setpoints: Calculated (15}~1~'~.Lj~l~E.~'--__~Ci/cc Actual (16) 1.5 £ -l., ~tCi/cc 1.E discharge monitor is OOS. THEN COMPLETE the following:
- Monitor (17) !-..l A. placed out service @ _--:.;~:.w.::f\,,--_ _
Date Time
- Vent Sample:(18) Sample # t.J " Date_~tJ,,-".:-;A.'--_ _ Time tJ A.. Results (19) tJ "- ~Ci/cc (Noble Gas)
- Vent flow rate (20) tJ A. cfm Continuous Release Rate (CR)(21 ),_...-:;:tJ~A.:2.__ _ _ ~Cj/sec Release Calculations verified by (22),_-.:N;.;:!..:..~2.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Release Path Valve Alignment Verified \4'"'1_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
CRS/SM Discharge Authorized (24),_ _-=-=-::::-:-:-_ _ _ __ Release Start (25)
CRS/8M Date Time Final Pressure (26) psig Release Stop (27)
Date Time Calculations Results: S (28) _ _ _ _ __ Emax (29) fe/min E(30),_ _ _ _ __ ft3!min RCV-014 Setting % open
No: 3-S0P-WDS-013 Rev:
GASEOUS WASTE RELEASES 37 of 56 I
ATTACHMENT 1, GASEOUS WASTE RELEASE PERMIT FORM (Page 1 of 1)
Current Date/Time (2) ~ld;\d CU.V'ft"ill\ 'Ti~ Permit No. (3) I (}OJoll ate Time Concentration of Volume (4) tJ /1. fe Initial Pressure (5) , * '5 psig Noble Gas (C)(6) q. q&.(t)£- 7 /lCilcc Grab Sample:(7) Sample # tJ A... Date_..o.;:tY:::-~-,--_ _ Time ,J A. 0~2~
Activity (A}(8)._-'-t..l_A_ _ _ _ _ _,/lci Noble Gas Iodine 131 Activity (8a) N A. /lCi/cc VC Purge Only Calculated Release Rate (R)(9) ::>. ~ I G-I }.lCi/sec Available Release Rate (D)(10)J.t*lc t .J..}.lCi/sec J>-J-l.--____
Discharge Monitor (11 )_........"i2=--..... Actual Alarm Setpoint (12) Vi t;; - t:) /lCi/sec Calculated alarm setpoint (13)__N_'_b._ _ _ ~lCi/sec Alert setpoint (14 )_ _ _ r-..l_"'___ /lCi/SeC R-12 Auto Closure/Alarm Setpoints: Calculated (15) :; .Ll16 -\ /lCi/cc Actual (16) 1.5'£ - (, ~LCi/cc IF discharge monitor is OOS. THEN COMPLETE the following:
- Monitor (17) t-J , placed out service @ _--=-N~~~__
Date Time
- Vent Sample:(18) Sample # U f:... Date_ _tJ~"'-,--_ _ Time tV ~ Results (19) , tJ As- ~lCi/cc (Noble Gas)
- Vent flow rate (20) tJ A.. cfm Continuous Release Rate (CR)(21 )_.....;...:tJ:...!\.....;..____ /lCi/seC Release Calculations verified by (22)_~tJ-=--:-~..:..-._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Release Path Valve Alignment Verified (23) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
CRS/SM Discharge Authorized (24) _ _ ==-:-::-_____ Release Start (25)_--::,---_
CRS/SM Date Time Final Pressure (26)_ _ _ _ _ _ _psig Release Stop (27)_--:::--_
Date Time Calculations Results: S (28) _ _ _ _ __ Emax (29)_ _ _ _ _ _ _ ft3/min E(30)_ _ _ _ _ _fe/min RCV-014 Setting (31 )_ _ _ _ _ _% open Comments:(32)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
. No: 3-S0P-WDS-013 Rev: 28 GASEOUS WASTE RELEASES Page 37 of 56 ATTACHMENT 1, GASEOUS WASTE RELEASE PERMIT FORM (Page 1 of 1)
Current _
Tank! \Ie Pil"%lt't' System (1) f<< I,,' .f DatelTime (2) \Od~da te Volume (4) ~~ ff Initial Pressure (5) ,. ~ psig Grab Sample:(7) Sample # tJ l. ~ A..
Date._...£:......:--
Activity (A)(8)r_-:u::...:...;A~_ _ _ _-Jf.lCi Noble Gas Iodine 131 Activity (8a) NA. f.lCi/ee
__-_:rW'Dme-f. (J.'~ VC P O I
. c:ku.fo Wi' ~'t'~U~ urge ny Calculated Release Rate (R)(9) ~.~. c:: -I Ci/sec Available Release Rate (D){10)J.l l c t .l.J,.I.Cilsec Discharge Monitor (11) @ Wt'b!4 M.Dni.4trf Actual Alarm Setpoint (12) 1.5" £" - S" ).lCi/sec Calculated alarm setpoint (13) ,J b. !-lCi/sec Alert setpoint (14) ...., f\ !-lCi/sec R*12 Auto Closure/Alarm Setpoints: Calculated (15) a.~ 1 E. -\ ).lCilee Actual (16) (. c; ~ - (, ).lCi/cc IF discharge monitor is OOS, THEN COMPLETE the following:
- Monitor (17) ....J l.. placed out service@_--:.N;:...o.;;I'l>.."--____ _..:.::Io.J:....:...;A.:......-_ _
Date Time
- Vent Sample:(18) Sample # t.J f1... Date tJ " Time ~ A Results (19) tJ I\c. ).lCi/cc (Noble Gas)
- Vent flow rate (20) tJ ~ cfm Continuous Release Rate (CR)(21 ),_......:.;::tJ~A:...::.--_ _ _ f.lCilsec Release Calculations verified by (22),_~tJ.:::...:....~.:...-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Release Path Valve Alignment Verified (23),_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
CRS/SM Discharge Authorized (24),_ _ ==-=-=-____ Release Start (25),_----,,..---_ _---==--_
CRS/SM Date Time Final Pressure (26),_ _ _ _ _ _psig Release Stop (27),_ _ __
Date Time Calculations Results: S (28),_ _ _ __ Emax (29),_ _ _ _ _ _ _ fefmin E(30),_ _ _ _ _ _fe/min RCV-014 Setting (31),_ _ _ _ _ _% open Comments:(32),_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 1500010532 Task
Title:
Classify Emergency Events requiring Emergency Plan Implementation 1940012438 Job Performance Measure SRO KIA
Reference:
SRO-4.4 No: Admin-5
~~-------------
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance x Actual Performance Classroom x Simulator - - - - - - Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
1 of 8
Appendix C Job Performance Measure Form ES-C-1 Initial Conditions:
A reactor trip occurred approximately 18 minutes ago after 108 days @ 100% reactor power. The trip was automatic due to a loss of 31 Instrument Bus while N41 was OOS for repair. 33 EDG is tagged out for air-start motor replacement following a failed surveillance. A loss of offsite power occurred during the auxiliary power transfer. 32 EDG has failed to start. The Control Room Supervisor has completed the immediate actions of ECA-O.O and the following conditions exist according to the brief:
- 31 EDG is operating. 2AT3A tie breaker will not close due to a tripped 3A normal supply breaker with its amber light illuminated.
- The Con Ed DO has reported a grid stability problem due to severe weather to our South and power should be restored to the region within the hour
- 33332L and 33332M are OOS and the Buchanan Ring Bus is de-energized
- 31 Instrument Bus has been reenergized on MCC-34
- 32 ABFP is feeding all SGs adequately
- RCS pressure is 2050 psig and increasing
- I&C is investigating the cause of the 3A Bus problem
- Natural Circulation flow has been verified in the RCS METEOROLOGICAL CONDITIONS:
Wind Speed: 2.8 meters/second Wind Direction: 110 degrees @ 10 meters Stability Class: D Task Standard: Event properly classified and Part 1 form correctly completed within the required time.
Required Materials:
General
References:
IP-EP-120, Emergency Classification IP-EP-210, Central control Room IP-EP-410, Protective Action Recommendation EAL Wall Chart EAL Technical Basis Document 2 of 8
Appendix C Job Performance Measure Form ES-C-1 Initiating Cue: The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement SM can arrive on site.
This is a Time Critical Job Performance Measure You must Classify the event and Complete the NYS Part 1 form.
Inform the examiner when you have classified the event.
Inform the examiner when you have completed the Part 1 form.
Time Critical Task: Yes Validation Time: 25 30f8
_A--'-"'-'ppc....;e;...:..n'-.:::dc:c..ix'--C"--_ _ _ _ _ _ _ _ _....::...PClge 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ")
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains IP-EP-120 Comment: CUE: Candidate will be given all necessary procedure before the JPM is started.
Record the time the ~IPM is started: _ _ _ _ _ _ _ __
"2. Performance Step: Evaluate Plant Status to determine if GE, SAE, Alert, or NUE applies. Determine the highest classification and make declaration.
Standard: Determines Event is SAE per EAL 6.1.4 TIME CRITICAL - Must complete this step within 15 minutes of start of JPM.
Comment: Record the Time Declaration Made: _ _ _ _ _ _ _ __
"3. Performance Step: Complete and approve "New York State Radiological Emergency Data Form", IP-EP-115 EP-1 Standard: Completes all necessary information on the form and signs the form TIME CRITICAL - Must complete this step within 15 minutes of Time of Declaration (JPM step 2)
Comment: Record the Time Form is complete: _ _ _ _ _ _ _ __
4 of 8
_Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)
- 4. Performance Step: Refer to procedure IP-EP-210, Attachment 9.1.
Standard: Refers to Attachment 9.1 Comment:
- 5. Performance Step: Initiate County, State and NRC Notification per IP-EP-115, Form EP-6.
Standard: Request a communicator Comment: CUE: Acknowledge the communicator is prepared to make notifications Terminating Cue: JPM Complete 5 of 8
New York State Indian Point Energy Center RADIOLOGICAL EMERGENCY DATA FORM* PART t Notification # --'
This is the Indian Point Energy Center with a Part 1 Notification Reactor Status: ~ ~
This Isan-:~- ACTUAL EMERGENCY at UNIT 2 ~. 3 BOTH UNITS Unit 2 ,.... _1"'"
(Date) T'tJd.2\.( (Time) L...U.rrerrri~(24 hr clock)
Shutdown
~ operational .....~
(Date) _-1....l~
_..",'l--_ _ _ (Time) i - Ie moults (24 hr clock)
- 2. The Emergency A Unusual Event B. Alert C. Site Area Emergenc Classilication is:
D. General Emergency E, Emergency Terminated This Emergency Classification declared on:1i-=~:lIo" ." "'I,-----:",-:at lime I =-==t (Data) (rima 24 hr clock) r--+----:.......... ~r---.---- ..---.--.-.-..-
3.
4.
B. Release BELOW Federal limits To Atmosphere To Water To Atmosphere To Water D, Unmoni\ored release requiMng evaluation
- 5. Meiers/Sec at elevation 10 meters 7.
8.
B EVACUATE and IMPLEMENT the KI PLAN for the following Sectors C, SHEL TER'IN,PLACE and .IMPLEMENT the KIPLAN for the following Sectors All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM 2 miles around 5*miies downwind 5 miles around 10-miles downwind Entire EE'Z In the following Sectors; 1 2 3 <I 5 6 7 6 9 10 11 12 13 14 15 Hi (Communicator's Name)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Dateffirne: _ _ _ _ _ _ _ _ __
(Director's Page 1 of 1 Form EP-1, Rev 3 6 of 8
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's Signature and date: _ _ _ _ _ _ _ _ _ __
7 of 8
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
A reactor trip occurred approximately 18 minutes ago after 108 days @ 100% reactor power. The trip was automatic due to a loss of 31 Instrument Bus while N41 was OOS for repair. 33 EDG is tagged out for air-start motor replacement following a failed surveillance. A loss of offsite power occurred during the auxiliary power transfer. 32 EDG has failed to start. The Control Room Supervisor has completed the immediate actions of ECA-O.O and the following conditions exist according to the brief:
- 31 EDG is operating. 2AT3A tie breaker will not close due to a tripped 3A normal supply breaker with its amber light illuminated.
- The Con Ed DO has reported a grid stability problem due to severe weather to our South and power should be restored to the region within the hour
- 33332L and 33332M are OOS and the Buchanan Ring Bus is de-energized
- 31 Instrument Bus has been reenergized on MCC-34
- 32 ABFP is feeding all SGs adequately
- RCS pressure is 2050 psig and increasing
- I&C is investigating the cause of the 3A Bus problem
- Natural Circulation flow has been verified in the RCS METEOROLOGICAL CONDITIONS:
Wind Speed: 2.8 meters/second Wind Direction: 110 degrees @ 10 meters Stability Class: D Initiating Cue:
The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement SM can arrive on site.
This is a Time Critical Job Performance Measure You must Classify the event and Complete the NYS Part 1 form.
Inform the examiner when you have classified the event.
Inform the examiner when you have completed the Part 1 form.
New York State Indian Point Energy RADIOLOGICAL EMERGENCY This is the Indian Point Energy Center with a Part 1 Notification on: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
1 Reactor Status:
This is an: EXERCISE ACTUAL EMERGENCY at: UN1T2 UNIT3 BOTH UNITS Unit 2 Operational (Date) (Time) (24 hr clock)
Shutdown Unit 3 Operational (Date) (Time) (24 hr clock)
Shutdown
- 2. The Emergenc:l A. Unusual Event B. Alert C. Site Area Emergency QI§ssification is:
D. General Emergency E. Emergency Terminated This Emergency Classification declared on: at (Date) (Time 24 hr clock)
- 3. EAL#:
- 4. Release of RadiQ~give Materials due to the Classified Event A. No Release B. Release BELOW Federal limits To Atmosphere To Water C. Release ABOVE Federal limits To Atmosphere To Water D. Unmonitored release requiring evaluation 5
- Wind 5geed: Meters/Sec at elevation 10 meters 1 .
~nd Di,.olio", <F'om) Degrees at elevation 10 meters
- 7. Stability Class: A B C D E F G 1 8.
The following Protective Actions are recommended to be implemented as soon as practicable:
A. NO NEED for PROTECTIVE ACTIONS outside the site boundary B. EVACUATE and IMPLEMENT the KI PLAN for the following Sectors C. SHELTER-IN-PLACE and IMPLEMENT the KI PLAN for the following Sectors All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM 2 miles around 5-miles downwind 5 miles around 10-miles downwind Entire EPZ In the follOwing Sectors; 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 NOTE: OFFSIT!; AUTHORITIES SHOULD CONSIDER SHELTER-IN-PLACE + TAKE KIIF EVACUATION IS NOT FEASIBLE
- 9. Reported by - Communicator: Telephone #
(Communicator's Name)
'10. I Emergency Director Approval: DatelTime:
I (Director's Name)
Page 1 of 1 Form EP-1, Rev 3
New York State Indian Point Energy Center RADIOLOGICAL EMERGENCY DATA FORM - PART 1 Notification # _,_
~---~~---------~-------------------------------------------------------------~
This is the Indian Point Energy Center with a Part 1 Notification on: __-n':":':::JDi!::.8Q.~{_______________
1.
Reactor Status: _ ~
This is an: ACTUAL EMERGENCY at: UNIT 2 ~ BOTH UNITS I
Unit 2 e n (Date) T Dda\.l (Time)
L....U. rre n+-r. Jlt-e(24 hr clock)
Shutdown
-r-.~ ...,.. 1tJ.Q rrvOU'lr!> ~ ,. I
~
Unit 3 Operational 1_
(0 t ) -LD:!!a..1 (Time) i - (24 hr clock) - 4ro-V'l11l".t\
(ShutdowCi) a e ......LII-r::%f-r- -
¥-- 2. The Emergency Classification is:
A. Unusual Event B. Alert CC. Site Area Emergen~ - tn -Irs I O. General Emergency E. Emergency Terminated This Emergency Classification declared on:~""'L.::Dd,",.,.au"'""'l-___-=_.at :TIme.
t (Date) (Time 24 hr clock)
- 3. EAL#: (..1...., L~') b.{ Q(( 'jQ~"LLavds 101).'" AC rD~'" > IS' fI'\\nL.t~ ~, C)f\cl \r'\bb"i~/-to pDWt'lf" C'lJfe CDb"~ ..,,-th'I>\ 1'5 MI "u-ks
- 4. Release of Radioactive Materials due to the Classified Event:
- 8. No Release:> B. Release BELOW Federal limits To Atmosphere To Water C. Release ABOVE Federal limits To Atmosphere To Water D. Un monitored release requiring evaluation
- 5. Wind Speed: Meters/Sec at elevation 10 meters
- 6. Wind Direction: (From) ___IL.,;\!...l)=--_____ Degrees at elevation 10 meters
- 7. Stability Class: A B C G) E F G 8.
The fnl/owino Protective Actions are ! to be . as soon as practiCable:
( A. NO NEED for PROTECTIVE ACTIONS outside the site boundau B. EVACUATE and IMPLEMENT the KI PLAN for the following Sectors C. SHELTER-IN-PLACE and IMPLEMENT the KI PLAN for the following Sectors All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM 2 milM around 5-miles downwind 5 miles around 1O-miles downwind Entire EPZ In the following Sectors: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 NOTE: OFFSITE AUTHORITIES SHOULD CONSIDER SHELTER-IN-PLACE of. TAKE KIIF EVACUATION IS NOT FEASIBLE
- 9. Reported by - Communicator: _N. . .I.a-=..;W\t'
. -"""______________ Telephone # _ _ _ _ _ _ _ _ _ __
(Communicators Name)
- 10. Emergency Director Approval: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Datemme: ____________
(Director's Name)
Page 1 of 1 Form EP-1, Rev 3
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0000420501 Task
Title:
Align Low-Head 51 Flow Path for Hot Leg Recirculation 000011A111 Job Performance Measure A KIA
Reference:
RO- 4.2 SRO- 4.2 No:
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom Simulator X Plant _ _ _ __
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- It is 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after a large break LOCA with loss of offsite power.
- Transfer to hot leg recirculation is desired.
Task Standard: The SI System in aligned for Hot Leg Recirculation with 32 and 33 HHSI Pumps Operating.
Required Materials:
General
References:
- -ES-1.4 Transfer to Hot Leg Recirculation Initiating Cue: You are the ATC and the CRS has directed you to transfer to Hot Leg Recirculation in accordance with ES-1.4 steps 1 through 11.
Time Critical Task: No Validation Time: 20 1 of 13
Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-ES-1.4 Comment:
- 2. Performance Step: Review Caution and Note before Step 1 Standard: Reviews Caution and Note Comment:
- 3. Performance Step: CHECK Low-Head Recirc flow Standard: Observe flow on FI-946A through 0 on Panel SBF-2 Comment: Procedure Step 1
- 4. Performance Step: Review Note before Step 2 Standard: Reviews Note Comment:
2 of 13
Performance Information (Denote critical steps with a check mark >/)
..J 5. Performance Step: Align Non-BIT Hot Leg Injection Valves:
- Close 856J and 856H
- Open 856B Standard: Rotate switches for 856 J and H to CLOSE Rotate switch for 856B to OPEN All above switches are on Panel SBF-2 Comment: Procedure Step 2 The sequence of operation of the above valves is important.
..J 6. Performance Step: Align Non-BIT Hot Leg Injection Valves:
- Close 856E and 856C
- Open 856G Standard: Rotate switches for 856 E and C to CLOSE Rotate switch for 856G to OPEN All above switches are on Panel SBF-2 Comment: Procedure Step 3 The sequence of operation of the above valves is important.
- 7. Performance Step: Check HHSI Hot Leg Injection valve status Standard: Verify 8568 or 856G OPEN Comment: Procedure Step 4 3 of 13
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- 8. Performance Step: Dispatch Nuclear NPO to deenergize the following valves
- 856G
- 856E
- 856C
- 856J
- 856H
- 856B Standard: Contact NPO using radio and direct deenergizing valves CLlE: Acknowledge as Nuclear NPO to Deenergize valves Comment: Procedure Step 5 NOTE: Booth Operator Deenergize valves listed above
- 9. Performance Step: Check Recirc Pumps only one running Standard: Observes only both Recirc Pumps Operating.
Places one Recirc Pump in Trip Pull Out Comment: Procedure Step 6.a 4 of 13
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- 10. Performance Step: Dispatch NPO to verify the following valves CLOSED
- IV-1403
- IV-1447
- IV-1448
- IV-1464
- IV-1465
- IV-1479 Standard: Contact NPO using radio and direct verifying valves CLOSED CUE: Acknowledge as Nuclear NPO. Report "All Valves are Closed".
Comment: Procedure Step 6.b.1
- 11. Performance Step: Dispatch NPO to verify the following valves OPENED
- SI-MOV-850A
- ISI-MOV-850C Standard: Contact NPO using radio and direct verifying valves OPENED Comment: Procedure Step 6.b.2 CUE: Acknowledge as Nuclear NPO 5 of 13
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ."J)
- 12. Performance Step: Ensure the following valves are OPEN
- 888A
- 888B
- 1869A
- 1869B
- 1835A
- 1835B
- 1852A
- 1852B Standard: Verify valves listed above are opened All of the valves listed above are located on Panel SBF-1 Comment: Procedure Step 6.c
- 13. Performance Step: Ensure the following valves are OPEN
- 888A
- 888B Standard: Rotate switches for above valves to OPEN position Both of the valves listed above are located on Panel SBF-1 Comment: Procedure Step S.c 6 of 13
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)
- 14. Performance Step: Ensure the following valves are OPEN
- 1869A
- 1869B
- 1835A
- 1835B
- 1852A
- 1852B Standard: Verify valves listed above are opened Rotate switch for 1869A to Open All of the valves listed above are located on Panel SBF-1 Comment: Procedure Step 6.c
- 15. Performance Step: Place SI Pump Suction Low Pressure Alarm Block switch to UNBLOCK Standard: Rotate Switch to UNBLOCK on Panel SBF-1 Comment: Procedure Step 6.d
- 16. Performance Step: Low Pressure Alarm on Standard: Observes alarm not illuminated Comment: Procedure Step 6.e 7 of 13
Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark -,J)
..J 17. Performance Step: Place Safety Injection Recirc Switch 6 to OFF position Standard: Rotate switch to OFF Comment: Procedure Step 6.f
- 18. Performance Step: Start High Head Safety Injection Pump 31 Standard: Observes that 31 HHSI Pump does not start, then places switch in TRIP PULLOUT Go to Step 8 Comment: Procedure Step 7.a
" 19. Performance Step: Start High Head Safety Injection Pump 33 Standard: Rotate switch for 33 HHSI pump to Start Comment: Procedure Step 8.a
- 20. Performance Step: Check BIT header loop injection flow Standard: Verify stable flow on Loop 2 Comment: Procedure Step 8.b
- 21. Performance Step: Check HHSI pump status Standard: Observes 33 HHSI pump running Comment: Procedure Step 9 8 of 13
Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)
- 22. Performance Step: Check status of 31 and 33 HHSI pumps Standard: Verify only 33 HHSI pump is running Comment: Procedure Step 9.b
- 23. Performance Step: Check HHSI pump 32 status Standard: Verify 32 HHSI pump SHUTDOWN Comment: Procedure Step RNO 9.b.1 9 of 13
Appendix C Page 10 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/)
- 29. Performance Step: Check control switches for non-running HHSI pumps in Trip Pullout Standard: Verifies 31 HHSI pump switch in Trip Pullout Comment: Procedure Step 9.d
- 30. Performance Step: high-head injection flows established in at least 1 header Standard: Observes flow in both loops on FI-925 and FI-982 Comment: Procedure Step 9.e
'\J 31. Performance Step: Terminate Low Head Recirculation Standard: Rotate switches for the following to CLOSE
- 746 (Not Critical already closed)
- 747
- 899A
- 899B The switches above are located on Panel SGF Comment: Procedure Step 10 Terminating Cue: JPM Complete 10 of 13
Appendix C Page 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
11 of 13
Appendix C Simulator Setup Form ES-C-1 12 of 13
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- It is 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after a large break LOCA with loss of offsite power.
- Transfer to hot leg recirculation is desired Initiating Cue:
You are the ATC and the CRS has directed you to transfer to Hot Leg Recirculation in accordance with ES-1.4 steps 1 through 11.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0100180431 Task
Title:
Respond to a Pressurizer Low Pressure Alarm 000027A101 Job Performance Measure Sim B KIA
Reference:
RO - 4.0 SRO-3.9 No:
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom Simulator ~-----
x Plant -~-~-
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully. the objective for this job performance measure will be satisfied.
Initial Conditions:
- The plant is operating at 100% power
- No Equipment is Out of Service Task Standard: Pressurizer pressure stable, reactor tripped with 33 and 34 RCPs tripped.
Required Materials: None General
References:
3-ARP-003 Initiating Cue:
You are the ATe Time Critical Task: No Validation Time:
1 of 7
Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
NOTE:
Candidate may diagnose failed open Spray Valve at any time during this JPM. The exact order of actions before the Reactor Trip is not important, and they may be performed in any order.
The reactor must be tripped before the Reactor Coolant Pumps are tripped.
- 1. Performance Step: Acknowledge Pressurizer Low Pressure Alarm and refer to ARP Standard: Observe alarm and retrieve ARP from holder Comment: Candidate may recognize pressure lowering before alarm annunciates.
- 2. Performance Step: Verify alarm by observing PRZR Pressure Standard: Observe pressure decreasing on all 4 channels Comment: ARP Step 3.1
- 3. Performance Step: Determine if Channel or Controller Failure has occurred Standard: Determine NOT instrument failure (All 4 channel indications decreasing)
Determine NOT a controller failure (Controller output calling for heaters. Pressurizer heaters will eventually energize).
Comment: ARP Step 3.2 20f7
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)
4, Performance Step: IF the Pressurizer heaters or sprays are NOT operating properly, THEN PLACE Pressurizer Pressure Master Controller in MANUAL and ATTEMPT to establish RCS pressure at 2235 psig, Standard: Transfer controller to Manual (T-bar up) and output adjusted to Heaters (Left of nUll)
Comment: ARP Step 3,3 5, Performance Step: If Pressure is low, then check:
- PORVs Closed
- PRZR Spray and Aux Spray Closed
- PRZR Heaters Energized Standard: Identifies Pressurizer Pressure is low and one Spray Valve is Open Comment: ARP Step 3.4 6, Performance Step: If PRZR PORV are NOT closed THEN close PORVs Standard: Observes PORVs are closed and no action is required Comment: ARP Step 3.4,2 7, Performance Step: If Spray Valve(s) are not closed Close Spray Valve in Manual Standard: Transfer controller to Manual (T-bar up) and output adjusted to Close (Left)
Comment: ARP Step 3.4.3,1 30f7
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J>
- 8. Performance Step: IF PRZR Spray Valve does NOT close, THEN CLOSE PRZR Spray Valve by removing power fuse from back of Foxboro controller for affected PRZR Spray Valve.
Standard: Observes Spray Valve NOT Closed and removes controller from Flight Panel. When controller is removed, then fuse is removed from back.
Comment: ARP Step 3.4.3.2
'\J 9. Performance Step: If Spray Valve(s) can NOT be closed, Then TRIP the Reactor Standard: Identifies spray valve will not close; depresses the Rx TRIP button on Panel FCF Comment: ARP Step 3.4.3.3.a
'\J 10. Performance Step: Trip 33 and 34 Reactor Coolant Pumps Standard: Verifies Reactor Tripped then rotates RCP switches to STOP position Comment: ARP Step 3.4.3.3.b
- 11. Performance Step: Go To E-O Reactor Trip or Safety Injection Standard: Observes conditions to verify reactor tripped Comment: ARP Step 3.4.3.3.c Terminating Cue: JPM Complete 40f7
Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
50f7
Appendix C Simulator Setup Form ES-C-1 Reset Simulator to any 100% Ie Need Malfunctions to prevent Spray Valve from Closing 6of7
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The plant is operating at 100% power
- No Equipment is Out of Service Initiating Cue:
You are the ATC
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 003*010*04*01 Task
Title:
RCP #1 Seal Failure Actions KIA
Reference:
003000A2.01 Job Performance Measure No: Sim-C RO - 3.5 SRO - 3.9 Examinee: NRC Examiner: - - -
Facility Evaluator: Date:
~--~--
Method of testing:
Simulated Performance Actual Performance x Classroom Simulator X Plant - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions: Plant is at indicated power level. A malfunction is in progress on 34 RCP. The CRS has directed you to perform the actions of AOP-RCP-1. Reactor Coolant Pump Malfunction.
Task Standard: AOP-RCP-1 actions completed.
Required Materials: 3-AOP-RCP-1 General
References:
Initiating Cue: You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1. Reactor Coolant Malfunction for the indicated malfunction on 34 RCP.
Time Critical Task: No Validation Time: 10 minutes SIM-D rev. 0 1 of 7
Appendix C 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark)
- 1. Performance Step: Determine if reactor trip is required:
- Checks motor winding temp> 250°F with Tave > 540°F
- Checks upper or lower motor bearing temp> 200°F
- Checks shaft vibration> 20 mils
- Checks shaft vibration> 15 mils and increasing
- Checks Frame vibration> 5 mils
- Checks Frame vibration> 3 mils and increasing
- Checks seal delta-p < 200 psid
- Checks seal inlet temp> 225°F
- Checks seal outlet temp> 235°F Standard: Determines reactor trip required goes to step 4.2 Comment: Procedure Step 4.1
- 2. Performance Step: Are Reactor Trip Breakers Closed Standard: Observes red lights illuminated - Reactor Trip Breakers are closed Comment: Procedure Step 4.2
" 3. Performance Step: Trip the reactor Standard: Reactor manually tripped CUE: CRS directs the rest of the crew to perform E-O immediate actions. You are to continue with the subsequent actions of AOP-RCP-1.
Comment: Procedure Step 4.3 "4. Performance Step: Stop 34 Reactor Coolant Pump Standard: Places 34 RCP Control Switch to stop.
Comment: Procedure Step 4.4 SIM-D rev. 0 2 of 7
Performance Information (Denote critical steps with a check mark)
- 5. Performance Step: Initiate E-O, Reactor Trip or Safety Injection Standard: E-O initiated CUE: CRS directs the rest of the crew to perform E-O immediate actions. You are to continue with the subsequent actions of AOP-RCP-1.
Comment: Procedure Step 4.5
- 6. Performance Step: IAAT RCP #1 seal inlet temperature is > 225°F the dispatch NPO to close CH-241 D 34 RCP Seal Injection Flow Control Valve Standard: Observes #1 seal inlet temperatures greater than 225 0 and dispatches NPO to close valve.
CUE: Acknowledge as NPO and report valve is closed Comment: Procedure Step 4.6 "7. Performance Step: If 33 or 34 RCP shutdown then close affected spray valve - Closes PC-455G Standard: Places controller PC-455G to manual and reduces output to 0 (closed).
Comment: Procedure Step 4.7
- 8. Performance Step Was RCP Shutdown due to #1 seal return flow> 6 gpm Standard: Determines RCP NOT secured due to High Seal Return Flow Comment: Procedure Step 4.8 SIM-D rev. 0 30f7
4 Form ES-C-1 Performance Information (Denote critical steps with a check mark)
- 9. Performance Step Was RCP Shutdown due to #1 seal return flow < 0.84 gpm and Seal Temperatures Increasing?
Standard: Determines RCP was secured due to Low flow and Increasing Seal Inlet temperature Comment: Procedure Step 4.10
'" 10. Performance Step: IAAT 34 RCP has stopped rotating then manually close the seal return valve 2610 Standard: Observes flow stable at 20 - 30% on loop 34.
2610 closed by placing control switch on panel SAF to close.
Comment: Procedure Step 4.23
- 11. Performance Step: Are EOPs in Use Standard: Determines EOP are in use Goes to step 4.29 Comments: Procedure Step 4.24 and 4.25
- 12. Performance Step: When directed by the SM Return to procedure and step in effect.
Standard:
Comments:
Terminating Cue: JPM is Complete SIM-D rev. 0 4 of 7
VERIFICATION OF COMPLETION Job Performance Measure No. Sim Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __
SIM-D rev. a 5 of 7
Simulator Setup Reset simulator to IC-11 The malfunctions below will simulate a failure closed of 34 RCP #1 Seal resulting in heating up of the water surrounding the pump bearing and out of the #1 Seal.
Insert Malfunction:
- MAL-RCS013D Final Value 20% Ramp 10 Seconds (#2 seal failure)
- ANN-SAF-1-1 OFF (Reactor Coolant Pump Standpipe High Level)
- IND-RCS024D OFF #34 RCP Standpipe Level Off Normal Indicator Light
- IND-CVC015 Final Value 235 Ramp 180 Seconds (Seal Inlet Temp Increasing)
- IND-CVC016 Final Value 252 Ramp 180 Seconds (Seal Outlet Temp Increasing)
Reset Simulator to IC-155 SIM-D rev. 0 6 of?
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
Plant is at indicated power level. A malfunction is in progress on 34 RCP. The CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Pump Malfunction.
Initiating Cue:
You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Malfunction for the indicated malfunction on 34 RCP.
SIM-D rev. 0 7 of 7
Appendix C Job Performance Measure Form ES-C-1 Worksheet Indian Point 3 Task No: 0590060301 Facility:
Place Main Feed Reg Valve Controllers in Automatic Task
Title:
059000A403 Job Performance Measure No: Sim D KIA
Reference:
RO-2.9 SRO-2.9 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The plant is at 25% power
- 32 Main Boiler Feed Pump is in service
- 31 Main Boiler Feed Pump is in Standby
- SG Levels are being controlled using the Low Flow Bypass Valves
- Pre Job Discussion for this evolution has been completed
- Venting of Steam Flow Transmitters is NOT occurring
- All required Precautions and Limitations and Prerequisites of 3-S0P-FW 001 are satisfied Task Standard: 31 Main Feed Reg Valve in Automatic control.
Required Materials:
General
References:
3-S0P-FW-001 Initiating Cue: You are the ATC and the CRS has directed you to transfer to the Main Feed Regulating Valves, starting with 31 SG, in accordance with 3-S0P-FW-001, Main Feedwater System Operation, section 4.10.2.
1 of 8
Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 15 Minutes 2 of 8
Performance Information (Denote critical steps with a check mark ,j)
- 1. Performance Step: Obtain correct procedure Standard: Obtains current revision of 3-S0P-FW-001 Comment:
- 2. Performance Step: Observe CAUTION and NOTE before step 4.10.2 Standard: Reviews Caution and Note Comment:
- 3. Performance Step: Verify venting of steam flow transmitters is NOT occurring.
Standard: Given in Initial Conditions Comment: Procedure Step 4.10.2.1
- 4. Performance Step: Verify SG Level is slightly higher than 45% with steam flow and feed flow signals approximately equal Standard: Identify 31 SG level slightly higher than 45% and increase feed flow to 32, 33, and 34 SG by opening Low Flow Bypass Valve (Panel FBF)
Comment: Procedure Step 4.10.2.2 3 of 8
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 5. Performance Step: Prepare MFRV for service by unseating the applicable MFRV using Manual Control Standard: Rotate large potentiometer on FCV 417 counterclockwise until an increase in feed flow is observed the rotate clockwise to close the valves. (Panel FBF)
Comment: Procedure Step 4.10.2.3
'\J 6. Performance Step: Place 31 MFRV in AUTO Standard: Move controller toggle switch on FCV 417 controllers to left postion Comment: Procedure Step 4.10.2.4
" 7. Performance Step: Adjustthe associated Low Flow Bypass Valve to lower feed flow to slightly less than steam flow Standard: Rotate large potentiometer on FCV 417L clockwise (Panel FBF)
Comment: Procedure Step 4.1 0.2.5.a 4 of 8
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
'" 8. Performance Step: When associated MFRV starts to OPEN then adjust the Low Flow Bypass Valve as needed to minimize overshoot Standard: Rotate large potentiometer on FCV 417L counterclockwise when associated MFRV starts to open, (Panel FBF)
Comment: Procedure Step 4.10.2.S.b
'" 9. Performance Step: Continue to adjust associated Low Flow Bypass Valve until it is fully closed Standard: Continue to Rotate large potentiometer on FCV 417L clockwise in small increments, (Panel FBF)
Comment: Procedure Step 4.10.2.S.c
'" 10. Performance Step: Repeat JPM Steps 6-9 as desired Standard: Repeat steps to place MFRVs in Auto for as many MFRVs as examiner desires Comment:
Terminating Cue: JPM Complete 5 of 8
VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
6 of 8
Appendix C Simulator Setup Form ES-C-1 Reset Simulator to IC-9 Ensure 31 and 32 SG levels are greater than 45%
Ensure 33 and 34 SG levels are less than 45%
Reset Simulator to IC-156 7 of 8
Appendix C Initial Conditions Form ES-C-1
~~~~~
Initial Conditions:
- The plant is at 25% power
- 32 Main Boiler Feed Pump is in service
- 31 Main Boiler Feed Pump is in Standby
- SG Levels are being controlled using the Low Flow Bypass Valves
- Pre Job Discussion for this evolution has been completed
- Venting of Steam Flow Transmitters is NOT occurring
- All required Precautions and Limitations and Prerequisites of 3-S0P-FW 001 are satisfied Initiating Cue:
You are the ATC and the CRS has directed you to transfer to the Main Feed Regulating Valves, starting with 31 SG, in accordance with 3...s0P-FW-001, Main Feedwater System Operation, section 4.10.2.
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 0220010131 Task
Title:
Start a Fan Cooler Unit 022000A401 KIA
Reference:
RO - 3.6 SRO - 3.6 Job Performance Measure No: SIM E
--=-:..:..::..:.-=--
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom Simulator - - -x- - - Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The plant is at indicated power
- 31 - 34 Containment Fan Cooler Units (FCU) are in operation
- Breaker Maintenance is scheduled for 32 Feu
- Containment Temperature is 87.5°
- Service Water is properly aligned to all FCUs
- All Precautions and Limitations have been satisfied
- 35 FCU was secured 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago for breaker maintenance
- Motor Starting Frequency requirement have been verified.
Task Standard: 35 Fan Cooler Unit is operating.
Required Materials: None General
References:
3-S0P-C8-010, Containment Recirculation Fan Cooler Unit Operations.
1 of 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are the BOP and the CRS has directed you to start 35 Fan Cooler Unit in accordance with 3-S0P-CB-01 O.
Time Critical Task: None Validation Time: 10 Minutes 20f9
Form Performance Information (Denote critical steps with a check mark ">
- 1. Performance Step: Obtain correct procedure Standard: Obtain 3-S0P-CB-010 Comment:
- 2. Performance Step: Review NOTES before step 4.2.1 Standard: Review Notes Comment:
- 3. Performance Step: Verify motor starting requirements of 3-S0P-0D4A will be met for 35 FCU.
Standard: Given in Initial Conditions Comment: Procedure Step 4.2.1
..J 4. Performance Step: Verify that the Fan Cooler Filter Unit Normal Inlet Dampers (A and 8) for 35 Fan Cooler Unit are OPEN.
Standard: Rotate CONT. RECIRC. UNIT NO. 35 FLOW VLV 1305 switch to OPEN. Observe Green Light OFF and red light ON.
PaneISBF-2 Comment: Procedure Step 4.2.2 30f9
Performance Information (Denote critical steps with a check mark ;J)
"5. Performance Step: Verify that the Fan Cooler Filter Unit Normal & Incident Damper (Bypass Damper C) for 35 Fan Cooler Unit is OPEN.
Standard: Rotate CONT. RECIRC. UNIT NO. 35 FLOW VLV 1306 switch to OPEN. Observe Green Light OFF and red light ON.
Observe Containment Control Recirc Air Unit Valve Tripped alarm clear PaneISBF-2 Comment: Procedure Step 4.2.3
- 6. Performance Step: Review NOTE before step 4.2.4 Standard: Reviews NOTE Comment:
- 7. Performance Step: Verify that the Fan Cooler Filter Unit Incident Damper (Damper D) for 35 FCU is CLOSED.
Standard: Observe CONT. RECIRC. UNIT NO. 35 FLOWVLV 1307 switch in CLOSE and Green Light is ON Panel SBF-2 Comment: Procedure Step 4.2.4 4of9
Performance Information (Denote critical steps with a check mark ;/)
- 8. Performance Step: Verify that the FCU starts by monitoring the current on the associated 480V bus.
Standard: Observe 480V bus amps for bus 6A Panel SHF CUE: A Spare RO will standby and observe bus 6A amps when the fan is started.
Comment: Procedure Step 4.2.5
..J 9. Performance Step: Review NOTE before step 4.2.5 Standard: Reviews NOTE Comment:
- 10. Performance Step: Start 35 Fan Cooler Unit Standard: Rotate Containment Recirc Fans Switch for 35 FCU to START. Observe green light OFF and Red Light ON Panel SBF-2 CUE: The spare RO reports and increase and then decrease in bus 6A amps.
Comment: Procedure Step 4.2.6 The CONTAINMENT RECIRC FAN MOTORS BEARING VIBRATIONS alarm on SBF-1 is expected to annunciate. Candidate should acknowledge this alarm 50f9
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 11. Performance Step: If CONTAINMENT RECIRC FAN MOTORS BEARING VIBRATIONS alarms, THEN RESET the alarm using the reset pushbutton on Panel SBF-1 Standard: Depresses pushbutton on Panel SBF-1 Observer the alarm resets.
Comment: Procedure Step 4.2.7 Terminating Cue: ~IPM Complete 6of9
Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
7of9
Appendix C Simulator Setup Form ES-C-1 This JPM can be run from virtually any simulator Initial Condition Ensure that 35 FCU is secured Ensure Dampers AlB and C are closed for 35 FCU 80f9
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The plant is at indicated power
- 31 - 34 Containment Fan Cooler Units (FCU) are in operation
- Breaker Maintenance is scheduled for 32 FCU 0
- Containment Temperature is 87.5
- Service Water is properly aligned to all FCUs
- All Precautions and Limitations have been satisfied
- 35 FCU was secured 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago for breaker maintenance
- Motor Starting Frequency requirement have been verified.
Initiating Cue:
You are the BOP and the CRS has directed you to start 35 Fan Cooler Unit in accordance with 3-S0P-CB-010.
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 0800060331 Task
Title:
Energize Buses 5 and 6 from 13.8 KV Power 062000A401 KiA
Reference:
RO - 3.3 SRO - 3.1 Job Performance Measure No: SIM F
-=-=-=-"---
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom Simulator X Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The plant is at approximately 45% power.
- The Station Service Transformer experienced a fault
- The operating crew entered of 3-AOP-138KV-1.
- 13.8KV power is available.
- 6.9 KV Bus 5 Lockout Relay 86ST5 is reset
- 6.9 KV Bus 6 Lockout Relay 86ST6 is reset Task Standard: 6.9 KV buses 5 and 6 are energized from 13.8KV source Required Materials: None General
References:
3-AOP-138KV-1 Attachment 1 Initiating Cue: You are the BOP and the CRS has directed you to re-energize Buses 5 and 6 from 13.8KV in accordance with steps 1.10 through 1.30 in 3-AOP-138KV-1, Attachment 1.
Time Critical Task: No 1 of 12
Appendix C Job Performance Measure Form ES-C-1 Validation Time: 15 Minutes 2 of 12
Form Performance Information (Denote critical steps with a check mark ...J)
'" 1. Performance Step: Place the 6900V bus tie breaker in PULL OUT.
Standard: Place the following in pullout:
o 6900V Bus No. 1-5 Tie in PULLOUT o 6900V Bus No. 2-5 Tie in PULLOUT o 6900V Bus No. 3-6 Tie in PULLOUT o 6900V Bus No. 4-6 Tie in PULLOUT Panel SHF Comment: Procedure Step 1.10
- 2. Performance Step: Will 6.9 KV Bus 5 be energized from 13.8KV source?
Standard: YES - Given in Initiating Cue Comment: Procedure Step 1.11
'" 3. Performance Step: Place 35 Circ Water Pump breaker in PULL OUT Standard: CCR control switch placed in PULL OUT for 35 Circ Water Pump PanelSJF Comment: Procedure Step 1.12 3 of 12
Performance Information (Denote critical steps with a check mark ;/)
'" 4. Performance Step: Is 6900KV bus No.5 Normal Feed breaker in Pullout?
Place 6900KV bus No.5 Normal Feed breaker in Pullout Standard: 6900V Bus No.5 Normal Feed breaker control switch placed to PU LL OUT PanelSHF Comment: Procedure Step 1.13
- 5. Performance Step: Is 6.9KV Bus 5 lockout relay 86ST5 reset?
Standard: YES. Given in Initial Conditions Candidate may contact the Nuclear Plant Operator to verify 86STS reset at the 6.9KV switchgear.
CUE: IF NPO contacted, report 86ST5 is reset Comment: Procedure Step 1.14
- 6. Performance Step: Is Station Service Transformer Supply Breaker 5 open and flag matched to green?
Standard: Observes green and amber lights ON and switch flag red.
Rotate switch to TRIP then back to AUTO Panel SHF Comment: Procedure Step 1.15 4 of 12
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/>
- 7. Performance Step: Is voltage zero on 6.9KV bus 5 Standard: YES. Places 6900V Bus Voltmeter switch to Bus 5 position and verifies 6900V Bus meter indicates zero.
Panel SHF Comment: Procedure Step 1. 16
'" 8. Performance Step: Close GT-35 6.9 KV Bus No.5 Feed Breaker Standard: Rotate Breaker Control Switch from Pullout to Close position. Observes Green Light OFF and Red Light ON PanelSHF Comment: Procedure Step 1.17
- 9. Performance Step: Is 6.9KV Bus 5 energized?
Standard: YES. Observes voltage indicated on 6900V Bus Voltmeter.
Panel SHF Comment: Procedure Step 1.18
- 10. Performance Step: Is Bus 5A Normal Feed breaker open?
Standard: YES. Observes Gree Light ON. The flag is still RED. The candidate may rotate the switch to TRIP to match the flag position with breaker position.
Panel SHF Comment: Procedure Step 1 . 19 5 of 12
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 11. Performance Step: Close Sta. Serv Trans. 5 Supply Breaker SS5 Standard: Rotate Switch to CLOSE position. Observe Green Light OFF and Red Light ON.
Comment: Procedure Step 1.20 This step in not critical because it is not necessary to energize bus 5. It is a step necessary to energize 480V bus 5A.
12.. Performance Step: Bus 6 be energized from 13.8KV source?
Standard: YES - Given in Initiating Cue Comment: Procedure Step 1.21 "13. Performance Step: Place 34 Circ Water Pump and Standby Circ Water Pump breakers in PULL OUT Standard: CCR control switch placed in PULL OUT for 34 and Standby Circ Water Pump PanelSJF Comment: Procedure Step 1.22 6 of 12
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ")
"14. Performance Step: Is 6900KV bus No.6 Normal Feed breaker in Pullout?
Place 6900KV bus No.6 Normal Feed breaker in Pullout Standard: 6900V Bus No.6 Normal Feed breaker control switch placed to PULL OUT Panel SHF Comment: Procedure Step 1.23
- 15. Performance Step: Is 6.9KV Bus 6tockout relay 86ST6 reset?
Standard: YES. Given in Initial Conditions Candidate may contact the Nuclear Plant Operator to verify 868T6 reset at the 6.9KV switchgear.
CUE: IF NPO contacted, report 86ST5 is reset Comment: Procedure Step 1.24
- 16. Performance Step: Is Station Service Transformer Supply Breaker 6 open and flag matched to green?
Standard: Observes green and amber lights ON and switch flag red.
Rotate switch to TRIP then back to AUTO Panel8HF Comment: Procedure Step 1.25 7 of 12
Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark -../)
- 17. Performance Step: Is voltage zero on 6.9KV bus 6 Standard: YES. Places 6900V Bus Voltmeter switch to Bus 6 position and verifies 6900V Bus meter indicates zero.
Panel SHF Comment: Procedure Step 1.26
-../ 18. Performance Step: Close GT-36 6.9 KV Bus No.6 Feed Breaker Standard: Rotate Breaker Control Switch from Pullout to Close position. Observes Green Light OFF and Red Light ON Panel SHF Comment: Procedure Step 1.27
- 19. Performance Step: Is 6.9KV Bus 6 energized?
Standard: YES. Observes voltage indicated on 6900V Bus Voltmeter.
Panel SHF Comment: Procedure Step 1.28
- 20. Performance Step: Is Bus 6A Normal Feed breaker open?
Standard: YES. Observes Green Light ON. The flag is still RED. The candidate may rotate the switch to TRIP to match the flag position with breaker position.
Panel SHF Comment: Procedure Step 1.29 8 of 12
Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/>
- 21. Performance Step: Close Sta. Serv Trans. 6 Supply Breaker SS6 Standard: Rotate Switch to CLOSE position. Observe Green Light OFF and Red Light ON.
Comment: Procedure Step 1.30 This step in not critical because it is not necessary to energize bus 6. It is a step necessary to energize 480V bus 6A.
Terminating Cue: JPM Complete 9 of 12
~--~---------------~~-----------------------=--~~~
Appendix C Page 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: ________________
10 of 12
Appendix C Simulator Setup Form Reset Simulator to IC24 Insert Malfunction MAL EPS006 Place Simulator in Run and let conditions stabilize.
Perform the first 17 steps of AOP-138KV-1 11 of 12
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The plant is at approximately 45% power.
- The Station Service Transformer experienced a fault
- The operating crew entered of 3-AOP-138KV-1.
- 13.8KV power is available.
- 6.9 KV Bus 5 Lockout Relay 86ST5 is reset
- 6.9 KV Bus 6 Lockout Relay 86ST6 is reset Initiating Cue:
You are the BOP and the CRS has directed you to re-energize Buses 5 and 6 from 13.8KV in accordance with steps 1.10 through 1.30 in 3-AOP-138KV-1, Attachment 1.
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian 3 Task No: 0390120431 Task
Title:
Respond to a Steam Flow Channel Failure 035000K401 KIA
Reference:
RO - 3.6 SRO - 3.8 Job Performance Measure No: SIM G Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance x Classroom Simulator ------
X Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The reactor is at indicated power
- Steady State, equilibrium Xenon conditions exist
- No equipment is out of service Task Standard: Stable plant conditions.
Required Materials: None General
References:
3-AOP-INST-1 Initiating Cue: You are the ATC. Take appropriate actions to stabilize plant.
Time Critical Task: No Validation Time:
10f9
_ _ _ _ _ _ _ _ _~ . . _P_ag""_e_2_ _ _.________F_o_rm_E_S_-C_-1_
_A-L.Jpp'-e_n_d_ix_C Performance Information (Denote critical steps with a check mark ;/)
- 2. Performance Step: Check All Control Systems
- Rod Control - Not Affected
- PRZR Pressure Control- Not Affected
- PRZR Level Control - Not Affected
- MBFP Speed Control - Not Affected
- SG Pressure Control - Not Affected
- SG Level Control - IS AFFECTED All above indications are located on the Flight Panel Standard: Check indications for all controls systems - Only Steam Flow is affected.
Comment: This is part of the immediate actions step 3.1 for 3-AOP-INST-1. The candidate should check all of these indication from memory. When conditions are stable the candidate should obtain the procedure and evaluate the control systems again.
20f9
Appendix~C,--_ _ _ _ __ Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 3. Performance Step: Has an instrument failure occurred?
Standard: YES Operator determines FT-449B has failed low.
Panel FBF Comment: Procedure Step 4.1
- 4. Performance Step: Got to the applicable step for the indicated failure. Step 4.70 for Steam Flow Failure Standard: Operator determines step 4.70 is the correct step from the table Comment: Procedure Step 4.2
- 5. Performance Step: Are both SG Transfer Switches selected to the NON affected channel.
Standard: YES. However, the Steam Flow Transfer Switch did not transfer control to the non-affected channel. Operator may attempt to transfer again.
Panel FBF Comment: Procedure Step 4.3 30f9
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 7. Performance Step: Return controls for unaffected equipment used to stabilize plant conditions to auto as desired.
Standard: No equipment can be returned to auto.
Comment: Procedure Step 4.72
- 8. Performance Step: Refer to the following TS tables for required actions
- 3.3.1-1
- 3.3.2-1 Standard: No Action Required Comment: Procedure Step 4.73 CUE: The STA will evaluate Tech Specs.
4 of 9
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ."f)
- 9. Performance Step: Observe CAUTION before Step 4.74 Standard: Reviews Caution Comment:
- 10. Performance Step: Are all redundant bistable status lights for failed instruments listed in Attachment 4 Table 1 extinguished Standard: Check each of the listed status lights OFF
- H-19 -- 8G 34 LO LEVEL LC447G
- 1-7 -- HI 8TM FLOW LP31 FC419A
- J-7 -- HI 8TM FLOW LP31 FC419B
- 1-8 -- HI 8TM FLOW LP32 FC429A
- J-8 -- HI 8TM FLOW LP32 FC429B
- 1-9 -- HI 8TM FLOW LP33 FC439A
- J-9 -- HI 8TM FLOW LP33 FC439B Comment: Procedure Step 4.74
- 11. Performance Step: Observe NOTE before step 4.75 Standard: Reviews Note Comment:
50f9
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
..J 12. Performance Step: Trip bistables for failed instrument listed in Attachment 4 Table 2 Standard: Locate rack White A-8 Place the switches listed below in the tripped (Up) postion
- Loop 48, High SF 51
- Loop 48, SF > FWF Comment: Procedure Step 4.75
- 13. Performance Step: Are all bistable status lights for failed instrument listed in Attachment 4 illuminated?
Standard: At panel SOF verify status lights are illuminated.
Comment: Procedure Step 4.76 Terminating Cue: JPM Complete 6of9
VERIFICATION OF COMPLETION Job Performance Measure No, Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
70f9
Appendix C Simulator Setup Form ES-C-1 Reset Simulator to any 100% Power IC Insert Malfunction MAL-MSS004H to 0% (NO Ramp time or Delay time)
Insert Switch Override SWI-PCS007 to ON (Prevents contacts from transferring) 8 of9
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The reactor is at indicated power
- Steady State, equilibrium Xenon conditions exist
- No equipment is out of service Initiating Cue:
You are the ATC. Take appropriate actions to stabilize plant.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0730150101 Task
Title:
Adjust R-27 Process Radiation Monitor Setpoints 073000A402 KIA
Reference:
RO - 3.7 SRO - 3.7 Job Performance Measure No: Sim H Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance X Actual Performance X Classroom Simulator X Plant -----
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
Plant startup is in progress. Post maintenance testing is complete on R-27. A new alert setpoint has been provided by chemistry. All requirements for setpoint control and log keeping have been met and are being performed by the CRS Task Standard: New alert setpoints entered into Bantam 11 and RM-23A for rad monitor R-27 Required Materials: None General
References:
3-S0P-RM-008, Radiation Monitoring Control Cabinet (BANTAM 11/RM23A Cabinet.
Initiating Cue: You are the BOP and the CRS has directed you to adjust the Bantam-11 to 3.5E+3 per 3-S0P-RM-008, Radiation Monitoring Control Cabinet steps 4.3.5.1 Time Critical Task: No 1 of 8
Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 10 minutes 2 of 8
Performance Information (Denote critical steps with a check mark ..J)
- 1. Performance Step: Refer to 3-S0P-RM-010 Radiation Monitor Setpoint Control Standard: 3-S0P-RM-010 requirements verified to be met Given in Initial Conditions CUE: All requirements for setpoint control and log keeping have been met and are being performed by the eRS.
Comment: Procedure Step 4.3.5.1
'\J 2. Performance Step: Select Bantam 11 RM-27 channel per section 4.3.1 Standard: This can be accomplished several ways.
From the Group Display enter 4027 then press SEL and verify RM-27 is backlit From the Group Menu press SEL button repeatedly until RM-27 is backlit From Grid Display select grid 1 and enter 4027 then press SEL and verify RM-27 and verify channel is backlit.
From the Grid Display press SEL repeated until RM-27 is backlit Comment: Procedure Step 4.3.5.2
'" 3. Performance Step: Select Channel Items display by depressing the Channel Items pushbutton.
Standard: Depresses Channel Items Pushbutton Comment: Procedure Step 4.3.5.2.a 3 of 8
Performance Information (Denote critical steps with a check mark -,J)
"4. Performance Step: Insert Key and turn Normal Supervisor Switch to Supervisor Standard: Insert and Rotate Key to Supervisor position Comment: Procedure Step 4.3.5.2.b "5. Performance Step: If changing Alert Set point Then enter 010 press SEL and verify channel item is backlit Standard: properly enters numbers and presses SEL, then verifies channel is backlit Comment: Procedure Step 4.3.5.2.d-e
" 6. Performance Step: Enter new set point Standard: Enter setpoint in the following format 35 + 0 3 Comment: Procedure Step 4.3.5.4 4 of 8
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
'" 7. Performance Step: Verify desired value is displayed If correct press Enter Standard: Observe display and depress Enter if correct. If not correct press Clear and repeat step 4.3.5.4 Comment: Procedure Step 4.3.5.5
'" 8. Performance Step: Turn Normal Supervisor keyswitch to NORMAL and REMOVE key.
Standard: Rotate switch to NORMAL and Remove Key Comment: Procedure Step 4.3.5.6
- 9. Performance Step: Restore normal All Monitors display Standard: Depresses Group Menu Pushbutton then 026 and SEL to restore normal display Comment: Procedure Step 4.3.5.7 Terminating Cue: JPM Complete 50f8
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
6of8
Appendix C Simulator Setup Form ES-C-1 No Simulator Setup is necessary for this JPM 7 of 8
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
Plant startup is in progress. Post maintenance testing is complete on R-27. A new alert setpoint has been provided by chemistry. All requirements for setpoint control and log keeping have been met and are being performed by the CRS Initiating Cue:
You are the BOP and the CRS has directed you to adjust the Bantam-11 to 3.5 E+3 per 3 SOP-RM-008, Radiation Monitoring Control Cabinet steps 4.3.5.1.
Appendix C Job Performance Measure Form ES-C-1
- - - - - - -Worksheet Facility: Indian Point Task No: 0040010504 Task
Title:
locally Emergency Borate 000024A104 Job Performance Measure KIA
Reference:
RO - 3.6 SRO - 3.7 No: In-Plant 1 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance x Actual Performance Classroom Simulator - - - - - - x Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The Control Room has been evacuated due to a fire
- Source Range N-38 is on scale but count rate has not been decreasing as expected
- MCC-36A is energized, MCC-36B is de-energized
- 31 BATP had been in-service
- Seal injection is in service to ALL RCPS Task Standard: Local Emergency Boration has been established for 35 minutes per 3 AOP-SSD-1, Attachment 8 Required Materials:
General
References:
2-AOP-SSD-1, Attachment 8, Emergency Boration - Local Initiating Cue: You are the ATC and the SM has directed you to Emergency Borate the RCS in accordance with 3-AOP-SSD-1! Attachment 8.
Time Critical Task: No Validation Time: 20 minutes 1 of 9
Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 1. Performance Step: Obtain correct procedure Standard: Obtains 3-AOP-SSD-1 Attachment 8 This procedure would have been picked up from the APP R cage outside the Unit 3 Control Room upon evacuation.
Comment:
- 2. Performance Step: Verify 31 BATP energized from MCC-36A Standard: Locate breaker for 31 BATP on MCC-36A and verify it is closed. (Can also be locally verified if pump liS)
Comment: Procedure Step 8.1 CUE: Breaker on MCC36A is CLOSED
- 3. Performance Step: Determine if 32 Boric Acid Transfer Pump energized at MCC-36B?
Standard: Determine 32 Boric Acid Transfer Pump cannot be energized.
MCC-36B is de-energized - Given in Initial Conditions.
Comment: Procedure Step 8.2
- 4. Performance Step: Determine that 31 Boric Acid Transfer Pump be used to supply blender?
Standard: Given in Initial Conditions Comment: Procedure Step 8.3 CUE: If requested the SM directs you to use 31 Boric Acid Transfer Pump.
20f9
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/>
- 5. Performance Step: Open CH-360 (31 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
Standard: Locate CH-360 and determines valve is open Comment: Procedure Step 8.4.
This step in NOT critical because if 31 BATP was in service, this valve would be opened. Depending on actual plant configuration this valve may be opened or closed.
CUE: Valve is Open
- 6. Performance Step: Close CH-370 (32 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
Standard: Locate CH-370 and determine valve is closed Comment: Procedure Step B.5.
This step in NOT critical because if 31 BATP was in service, this valve would be closed. Depending on actual plant configuration this valve may be opened or closed.
CUE: Valve is Closed
- 7. Performance Step: Close CH-267B (31 BORIC ACID FILTER BYPASS ISOLATION FROM 32 BORIC ACID TRANSFER PUMP)
Standard: Locate CH-267B and determine valve is closed Comment: Procedure Step 8.6.
This step in NOT critical because if 31 BATP was in service, this valve would be closed. Depending on actual plant configuration this valve may be opened or closed.
CUE: Valve is Closed 30f9
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- .J 8. Performance Step: Close CH-HCV*105 and CH-HCV-105 (Boric Acid Transfer Tank Recirculation Flow Controllers)
Standard: Locate valves. Isolate air supply to the valves and vent the air from the diaphragm.
Comment: Procedure Step 8.7 CUE: Valves are closed
- 9. Performance Step: Depress clutch lever for CH-MOV-333 (EMERGENCY BORATION VALVE). (PAB 73' el. Boric Acid Blender area)
Standard: Locate valve and depress clutch lever.
Comment: Procedure Step 8.8 CUE: Lever moves down freely
- 10. Performance Step: Engage clutch by moving handwheel as necessary and release clutch lever.
Standard: Rotate handwheel as necessary until clutch engages and then release lever Comment: Procedure Step 8.9 CUE: Handwheel rotates slightly and clutch is engaged
- 11. Performance Step: Open CH-MOV-333 by rotating handwheel counterclockwise.
Standard: Attempts to rotate handwheel counterclockwise.
Comment: Procedure Step 8.10 CUE: Handwheel will NOT rotate 40f9
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,j)
Transfer control of aligned Boric Acid Transfer Pump to LOCAL at the boric acid transfer pumps.
Standard: Place hand switch for 31 BATP in Local Comment: Procedure Step 8.11 CUE: Switch rotates to Local Position
'" 15. Performance Step: Place aligned Boric Acid Transfer Pump Speed Switch to FAST.
Standard: Locate switch and rotate to Fast Speed Comment: Procedure Step 8.12 CUE: Switch is in Fast Position 5 of9
Performance Information (Denote critical steps with a check mark >/>
- 16. Performance Step: Determine that Seal Injection flow to all RCPs was NOT isolated Standard: Given in Initial Conditions. Goes to Procedure Step 8.15 Comment: Procedure Step 8.13
- 17. Performance Step: Dispatch Nuclear NPO to monitor RCP Seal Injections Flows Standard: Directs Nuclear NPO to monitor Rep Seal Injection Flows Comment Procedure Step 8.15 CUE NPO Acknowledges direction.
- 18. Performance Step: Observe NOTE before Step 8.17 Standard: Reviews NOTE Comment:
CUE: 35 minutes has elapsed.
6of9
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,J)
<;J 19. Performance Step: Increase Charging Pump Speed until each RCP Seal Injection indicates 10 - 12 gpm Standard: Locate Charging Pump Controls Establish communication with the Nuclear NPO Rotate speed potentiometer for operating charging pump Stop adjustment when NPO reports Seal Injection flow is 10 -12 gpm on all pumps Comment: Procedure Step 8.16 Charging Pump Controls are located in a cabinet by the entrance to the charging pump cells.
CUE: NPO reports all RCP seal injection flows indicate 10 -12 gpm
- 20. Performance Step: WHEN boration has been ongoing for> 35 minutes, THEN stop Boric Acid Transfer Pump.
Standard: Rotate Boric Acid Transfer Pump switch to STOP Comment: Procedure Step 8.17 CUE: Pump is stopped Terminating Cue: ..IPM Complete 7of9
Appendix C Page 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
8of9
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The Control Room has been evacuated due to a fire
- Source Range N-38 is on scale but count rate has not been decreasing as expected
- MCC-36A is energized, MCC-36S is de-energized
- 31 SATP had been in-service
- Seal injection is in service to ALL RCPS Initiating Cue:
You are the ATC and the SM has directed you to Emergency Borate the RCS in accordance with 3-AOP-SSO-1, Attachment 8.
Control Room Inaccessibility Safe 3-AOP-SSD-1 Rev 14 Shutdown Control Page 113 of 195 Attachment 8 Emergency Boratlon - Local Page 1 of 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8.1 _Is 31 Boric Acid Transfer Pump _ Energize 31 Boric Acid Transfer Pump energized at MCC-36A (7RH)? at MCC-36A (7RH).
~ - -
8.2 _Is 32 Boric Acid Transfer Pump _ Energize 32 Boric Acid Transfer Pump energized at MCC-36B (7RH)? at MCC-36B (7RH).
8.3 _Will 31 Boric Acid Transfer Pump 1._ Open CH-370 (32 BORIC ACID be used to supply blender? TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
2._Close CH-360 (31 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
3._Close CH-267A (31 BORIC ACID FILTER BYPASS ISOLATION FROM 31 BORIC ACID TRANSFER PUMP) 4._GO TO Step 8.7.
8.4 _Open CH-360 (31 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
8.5 _Close CH-370 (32 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
8.6 _CloseCH-267B (31 BORIC ACID FILTER BYPASS ISOLATION FROM 32 BORIC ACID TRANSFER PUMP)
Control Room Inaccessibility Safe 3-AOP-SSD-l Rev 14 Shutdown Control Page 11 5 of 195 Attachment 8 Emergency Boratlon
- Local Page 3 of 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8.7 Close the following valves:
_CH-HCV-105 (31 BORIC ACID STORAGE TANK RECIRCULATION FLOW CONTROLLER SETTING)
_CH-HCV-104 (32 BORIC ACID STORAGE TANK RECIRCULATION FLOW CONTROLLER SETTING) 8.8 _Depress clutch lever for CH*MOV-333 (EMERGENCY BORATION VALVE). (PAB 73' el.
Boric Acid Blender area) 8.9 _ Engage clutch by moving handwheel as necessary and release clutch lever.
8.10 _Open CH*MOV-333 by rotating 1. _ Secure and bleed off both air supplies handwheel counterclockwise. to CH-FCV*110A (BORIC ACID BLENDER BORIC ACID FLOW CONTROL VALVE).
2._0pen CH*293 (BORIC ACID BLENDER BORIC ACID BYPASS ISOLATION).
8.11 _Transfer control of aligned Boric Acid Transfer Pump to LOCAL at the boric acid transfer pumps.
8.12 _ Place aligned Boric Acid Transfer Pump Speed Switch to FAST.
\
Control Room Inaccessibility Safe 3-AOP-SSD-l Rev 14 Shutdown Control Page 117 of 195 Attachment 8 Emergency Boratlon
- Local Page 5 of 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8.13 _Was Seal Injection to all RCPs _ GO TO Step 8.15 isolated due to no Charging and CCW Pumps running?
8.14 _GO TO Step 8.17.
8.15 Dispatch Nuclear NPO to monitor RCP Seal Injection Flows:
_FI-144 (RCP #31 SEAL WATER FLOW INDICATOR)
_FI-143 (RCP #32 SEAL WATER FLOW INDICATOR)
_FI-116 (RCP #33 SEAL WATER FLOW INDICATOR)
_FI-115 (RCP #34 SEAL WATER FLOW INDICATOR) m_____ .m_...
- 8.16 _'ncrease charging pump speed until each RCP Seal Injection indicates 10
- 12 gpm.
NOTE
- u> 35 minutes" is a minimum value and is not intended to specify the exact amount of boration.
- Clock starts after seal injection flow is established.
8.17 _WHEN boration has been ongoing for> 35 minutes, THEN stop Boric Acid Transfer Pump.
8.18 EXIT this attachment.
- END ....
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0840050432 Task
Title:
Perform Actions for RHR Pump Cooling using City Water 005000K101 KIA
Reference:
RO..,.. 3.2 SRO - 3.1 Job Performance Measure No: In Plant 2 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance x Actual Performance Classroom Simulator ------
x Plant - - - - -
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The unit is in Mode 5 with #31 RHR pump in service.
- City Water is available for 31 RHR Pump.
Task Standard: Backup City Water aligned to the 31 RHR Pump and draining to the floor Required Materials: None General
References:
3-S0P-ESP-001, Initiating Cue: You are the Spare RO and the CRS has directed you to align Normal Backup City Water to cool 31 RHR Pump per SOP-ESP-001, Section 4.12.
Time Critical Task: No Validation Time: 20 Minutes 1 of 7
Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains 3-S0P-ESP-001, Local Equipment Operation and Contingency Actions.
Comment:
- 2. Performance Step: Observe Cautions before Step 4.12.1 Standard: Reviews Cautions Comment:
..J 3. Performance Step: Close AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation Standard: Locates Valve, Simulates rotating in the clockwise direction CUE: The Valve is Closed Comment: Procedure Step 4.12.1.1 2 of 7
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)
..J 4. Performance Step: Close AC-737 A, CC Return from 31 RHR Pump Thermal Barrier Inlet Isolation Standard: Locates Valve, Simulates rotating in the clockwise direction CUE: The Valve is Closed Comment: Procedure Step 4.12.1.2
..J 5. Performance Step: Close AC*1871 D, CC Supply to 31 RHR Seal HX Inlet Isolation Standard: Locates Valve, Simulates rotating in the clockwise direction CUE: The Valve is Closed Comment: Procedure Step 4.12.1.2
'\I 6. Performance Step: INSTALL emergency city water supply jumper (e.g.,
hose) between MW*18*16, Hose Connection Isolation, (across from filter room on column) and one inch tee located immediately downstream of AC.736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation Standard: Jumper hose located in spare RHR pump cell, hose connection locations identified, and simulate connection actions.
CUE: Jumper Hose is connected.
Comment: Procedure Step 4.12.1.4 3 of 7
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;J)
- 7. Performance Step: INSTALL drain hose on % inch tee located immediately downstream of AC-1871D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation(31 RHR pump room)
Standard: % inch tee located and simulated hose connection actions CUE: Hose is connected Comment: Procedure Step 4.12.1.5
- 8. Performance Step: Route drain hose to suitable drain Standard: Drain hose routed CUE: Drain Hose is routed to drain Comment: Procedure Step 4.12.1.6
'" 9. Performance Step: OPEN AC-1871C, CC Return from 31 RHR Pump Seal Hx Outlet Isolation (31 RHR pump room).
Standard: Valve located, locking screws backed out or removed and valve simulated opened (counterclockwise)
CUE: Locking Screw is removed and valve is Open Comment: Procedure Step 4.12.1.7 40f7
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
..J 10. Performance Step: OPEN MW-18-16, Hose Connection Isolation (across from filter room on column)
Standard: locate valve and simulate rotate counterclockwise (Open)
CUE: Valve is Open Comment: Procedure Step 4.12.8 Terminating Cue: JPM Complete 50f7
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
60f7
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The unit is in Mode 5 with #31 RHR pump in service.
- City Water is available for 31 RHR Pump.
Initiating Cue:
You are the Spare RO and the CRS has directed you to align Normal Backup City Water to cool 31 RHR Pump per SOP-ESP-001, Section 4.12.
LOCAL EQUIPMENT OPERATION No: 3-S0P-ESP-001 Rev: 22 AND CONTINGENCY ACTIONS Page 38 of63 4.12 31 RHR Pump Cooling Using City Water CAUTION
- Without cooling water, two RHR pumps may be run for a maximum of 45 minutes followed by a single pump run for an additional maximum of 45 minutes (Ref. 5.2.6).
- Only 31 RHR pump can be supplied by City Water, as an emergency-cooling source.
4.12.1 IF CCW can NOT be established AND it is directed to operate 31 RHR pump, THEN PROVIDE backup City Water supply as follows:
4.12.1.1 CLOSE AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation.
4.12.1.2 CLOSE AC-737A, CC Return from 31 RHR Pump Thermal Barrier and Seal Hx Outlet Isolation.
4.12.1.3 CLOSE AC-1871 D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation.
4.12.1.4 INSTALL emergency city water supply jumper (e.g., hose) between MW-18-16, Hose Connection Isolation, (across from filter room on column) and one inch tee located immediately downstream of AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation.
4.12.1.5 INSTALL drain hose on % inch tee located immediately downstream of AC-1871 D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation{31 RHR pump room).
4.12.1.6 ROUTE drain hose to a suitable drain (e.g., 31 RHR Pump Room floor drain).
4.12.1.7 OPEN AC-1871C, CC Return from 31 RHR Pump Seal Hx Outlet Isolation (31 RHR pump room).
4.12.1.8 OPEN MW-18-16, Hose Connection Isolation (across from filter room on column).
4.12.2 WHEN city water cooling to 31 RHR pump is no longer required, THEN PERFORM the following:
4.12.2.1 CLOSE MW-18-16, Hose Connection Isolation (across from filter room on column).
LOCAL EQUIPMENT OPERATION No: 3~SOP-ESP-001 Rev: 22 AND CONTINGENCY ACTIONS Page 39 of 63 4.12.2.2 REMOVE jumper hose installed between MW-18-16, Hose Connection Isolation, and one inch tee downstream of AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation, and REPLACE cap on tee.
4.12.2.3 REMOVE jumper hose installed downstream of AC-1871D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation, and REPLACE cap on tee.
4.12.2.4 OPEN AC-1871D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation.
4.12.2.5 OPEN AC-737A, CC Return from 31 RHR Pump Thermal Barrier and Seal Hx Outlet.
4.12.2.6 THROTTLE AC-1871C to achieve 7.5 gpm as read on FIC-646.
4.12.2.7 THROTTLE AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation, to obtain 15 gpm total flow as read on FIC-646.
4.13 Emergency City Water Supply to the AFW Pumps 4.13.1 OPEN the applicable AFW Pump suction supply:
- CT-PCV-1187, 31 ABFP City Water Makeup Isolation
- CT-PCV-1188, 32 ABFP City Water Makeup Isolation
- CT-PCV-1189, 33 ABFP City Water Makeup Isolation 4.13.2 IF unable to open City Water suction supplies THEN have Maintenance open the valves using ELC-004- FIR (Appendix uRI! Repair).
4.14 Restore from Emergency City Water Supply to the AFW Pumps 4.14.1 IF ELC-004-FIR, (Appendix uRn Repair) was used to perform sect. 4.13, THEN COORDINATE with maintenance to restore condition to normal.
4.14.2 CLOSE the applicable AFW Pump suction supply:
- CT-PCV-1187, 31 ABFP City Water Makeup Isolation
- CT-PCV-1188, 32 ABFP City Water Makeup Isolation
- CT-PCV-1189, 33 ABFP City Water Makeup Isolation
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0710040134 Task
Title:
Release a Gas Decay Tank KiA
Reference:
RO - 2.6 SRO - 2.6 Job Performance Measure No: In Plant 3 Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance Actual Performance Classroom Simulator - - - - - - Plant - - - x --
READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- The release of 31 Small Gas Decay Tank is complete
- 32 Small Gas Decay Tank must be released.
- RCV-014 is closed
- An Independent Verifier (IV) is standing by Task Standard:
Required Materials: None General
References:
3-S0P-WDS-013, Gaseous Waste Releases Initiating Cue: You are the Nuclear NPO and the SM directs you to complete the restoration lineup for 31 Small Gas Decay Tank (SGDT) and perform the Release Alignment for 32 SGDT in accordance with 3-S0P-WDS-013 Attachment 9.
Time Critical Task: No 1 of 7
Appendix C Job Performance Measure Form ES-C-1 Validation Time:
2of7
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ")
'" 1. Performance Step: Perform restoration section of applicable Attachment 9 for 31 Small Gas Decay Tank Standard: Obtains Attachment 9 Locates and Simulates Closing WD-1652A (Rotate Clockwise)
CUE: Valve is Closed Comment:
'" 2. Performance Step: Perform valve alignment to isolate tank and prepare to sample per Attachment 9.
Standard: Locate each valve on list below and check or reposition valve Only WD-1652 is critical, the remaining valves are expected to be in the indicate position CUE: The valves are in the position indicated WD-1652B is OPEN Comment:
3 of?
Appendix C Pagel 4 Form ES-C-1 VALVE VALVE DESCRIPTION REQUIRED NUMBER POSITION N2 Supply to 32 SGDT Isolation WD-1641 B CLOSED 32 SGDT Drain (1)
WD-1642B CLOSED 32 SGDT Fill Isolation (1)
WD-1651B CLOSED PT-1053 Root Isolation WD-1676B OPEN r-----
32 SGDT to Release Header WD-1652B OPEN Isolation r-----
31 SGDT to Release Header WD-1652A CLOSED Isolation 33 SGDT to Releasl: Header WD-1652C CLOSED Isolation 34 SGDT to Release Header WD-1652D CLOSED Isolation 35 SGDT to Release Header WD-1652E CLOSED Isolation 36 SGDT to Release Header WD-1652F CLOSED Isolation 31 LGDT to Release Header WD-1617 CLOSED Isolation 32 LGDT to Release Header WD-1618 CLOSED
-- Isolation 33 LGDT to Release Header WD-1619 CLOSED r-Isolation 34 LGDT to Releasta Header WD-1620 CLOSED Isolation CUE: The valves are in the position indicated WD-1652B is OPEN 401'7
Appendix C Page 5 Form ES-C-1
- 3. Performance Step: Initiate Independent Verification (IV) of gas decay tank release path per Attachment 9 Standard: Contact another individual to peliorm independent verification. Independent Verifier is standing by on radio.
Given in Initial Conditions.
CUE: Acknowledge as Independent Verifier and report that IV is complete.
Comment:
Terminating Cue: JPM Complete 50f7
6 Form VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _.
6 of 7
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The release of 31 Small Gas Decay Tank is complete
- 32 Small Gas Decay Tank must be released.
- RCV-014 is closed
- An Independent Verifier (IV) is standing by Initiating Cue:
You are the Nuclear NPO and the SM directs you to complete the restoration lineup for 31 Small Gas Decay Tank (SGDn and perform the Release Alignment for 32 SGDT in accordance with 3-S0P-WDS-013 Attachment 9.
Appendix 0 Scenario Outline Facility: IPEG Unit 3 Scenario No . 1 Op-Test No.: 1 Examiners: Operators:
Initial Conditions: 100% power steady state. 32 AFW Pump is out of service for bearing repair.
Need to have 35 SWP in service.
Turnover:
32 AFW Pumps is expected back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Team has been asked to reduce power to 90% for a Turbine Stot;! and Control Valve Test.
Event Malt. Event Event No. No. I Type* Description 1 N/A R (ATC) Perform power reduction.
N (BOP, CRS) 2 MAL C (CRS) 33 MFRV fails open in auto - manual available.
CFW013 E C (ATC) 33 MFRV will be placed in manual to control 33 SG level.
3 MAL C (ALL) NRHX Tube Leak.
CFW011 4 MAL C (CRS, Loss of 480V Bus 3A.
EPS05B BOP) 34 or 36 SWP will be started.
TS (CRS)
5 N/A R (ATC) Perform power reduction with Feed Reg Valve in Manual N (BOP, CRS) 6 MAL- C (CRS) Inadvertent main generator trip. Reactor will not automatically trip.
GEN002 Manual trip will be required.
C (ATC) i7 MAL- M (ALL) 33 AFW pump will not start causing a loss of heat sink. Heat sink I
CFW001 will be restored using condensate.
C 8 MAL- TS (CRS) PORV 455C leaks by requiring isolation. CRS can be asked about PRS003 TS requirements at end of scenario.
D C (ATC)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor U3 NRC Scenario 1 Power ReductIon fro 100%,33 MFRV Falls Open - Manual Control AvaIl. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, paR v 455C Leaks requiring isolation.
Page 1 of20
Appendix 0 Scenario Outline Form ES-O-1 The evaluation begins with the plant at 100% power steady state operation.
- 32 ABFP has been out-of-service for bearing oil line repair for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. It is expected back within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (TS 3.7.5 - 72 hr AOT). 31 and 33 ABFPs are protected equipment.
- The team has been requested to reduce power to 90% in preparation for a turbine stop and control valve test.
After the team has begun reducing reactor power, 33 Main Feed Regulating valve (FCV-417) fails open. The team will take actions per AOP-FVIJ-1, "Loss of Feedwater" and place the MFRV in manual to control SG level.
During subsequent actions of AOP-FW-1, a leak develops in the Non-Regen heat exchanger.
The team will respond per AOP-CVCS-1 and isolate Letdown.
While putting in Excess Letdown, an electrical fault occurs on 480\1 Bus 3A. The team will have to start an essential service water pump per AOP-480V-1. The CRS will determine that two AFW Pumps are inoperable necessitating a shutdown per T.S. 3.7.5 or safety function determination per 3.0.6.
The team will commence a power reduction in accordance with POP-2.1 with 33 Main Feed Regulating Valve in Manual.
The MTG will then trip inadvertently. The reactor will not trip automatically and will require manual trip at the flight panel. After the trip, 33 AFW Pump will not start, and one of the PORVs begins to leak by creating an isolable SBLOCA. The team will respond to the PORV failure by closing its block valve. The team will initiate performance of E-O, "Reactor Trip or Safety Injection".
Since no motor-driven AFW pump is available, the team will transition to FR-H.1, "Loss of Secondary Heat Sink" due to inadequate AFW flow.
The scenario will terminate when Condensate flow is established to the SGs Procedure Flowpath: AOP-FW-1, AOP-CVCS-1, AOP-480V-1, E-O, FR-H.1 Critical Tasks are as follows:
E-O - A Manually trip reactor from the CCR before completing E-O, Step 1 E-O - M Close block MOV upstream of stuck-open Pzr PORV by completion of the first step in the ERG network that directs the crew to close the block MOV FR-H.1 - A Establish Condensate or Main Feed flow to at least one SG before 3 out 4 SG WR levels < 20%
U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip AvaiL, 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 2 of20
Appendix 0 Scenario Outline Form ES-O-1 Setup/Event Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES
~
IC Reset Reset Simulator to IC-11 I SES Setup Insert malfunction MAL- Auxiliary Feedwater Pump 31 Failures Schedule CFW001A to TRIP Insert malfunction MAL- Auxiliary Feedwater Pump 32 Trip CFW001B Insert override SWI-ATSOO2A Green Lamp Aux Feedwater Pump No. 32 to Off Control Switch Module Insert override SWI-ATS002B Red Lamp Aux Feedwater Pump No. 32 Control to Off Switch Module Insert override SWI-ATS002C Trip Pos Aux Feedwater Pump No. 32 Control to On Switch Module Insert override SWI-ATS002D On Pos Aux Feedwater Pump No. 32 Control Switch Module Insert remote LOA-MSS021 MS-41 S/G 32 To AFWP Iso to 0 Insert remote LOA-MSS022 MS-42 S/G 33 To AFWP Iso to 0 Insert malfunction MAL- Auxiliary Feedwater Pump 33 Failures CFW001 C to TRIP Insert override SWI- PCV-455C Red Lamp Pressurizer Relief Valve RCS021B to Off PCV-455C Control Switch Create event 30 JPPLP4(1)==1 -desc Set trigger 30 to actuate after reactor trip Insert malfunction MAL- FDW CNTRL FIC-437 Auto Mode Failure CFW013E to 100.00000 on (Manual Avail) event 1 Insert malfunction MAL- Non-Regenerative Letdown Heat Exchanger CFW013E to 50.00000 on Tube Leak event 2 Insert malfunction MAL- Main Generator Trip GEN002 on event 4 Insert malfunction MAL- Loss Of 480 V Bus 3A EPS005B on event 3 Insert malfunction MAL- Pressurizer Relief Valve 455C Valve Position PRS003C after 60 to Failure 10.00000 on event 30 Insert malfunction MAL- Reactor Trip Breakers Fail To Open (Auto RPS002A to ALL_FAIL Failure)
I U3 NRC Scenario I Power Reduction fro J00%, 33 MFRV Fails Open Manual Control A vail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 30[20
Appendix D Scenario Outline Form ES-D-1
- SES Setup Load Schedule and verify
. Schedule malfunctions and overrides have been entered Floor Setup Perform Setup Checklist Ensure 35 Service Water Pump Operating Update Protected Equipment Hang Danger T~gs on 32 AFW pump PC Risk is Yellow Hang Protected Equipment Tags For:
31 and 33 AFW pumps Event 1
- Respond as requested by Crew performs power reduction crew
. Event 2 Activate Trigger 1 when MAL-CFW013E 33 SG MFRV Fails Open directed Role Play Acknowledge requests for 18.C will develop a troubleshooting plan I&C to troubleshoot Event 3 Activate Trigger 2 MAL-CFW013E NRHX Tube Leak
- Role Play Respond as requested by the LOA-CVC031 Open/adjust CH-409, 33 charging crew pump recirc valve Event 4 Activate Trigger 3 MAL-EPS005B Fault on bus 3A Role Play I If asked to investigate bus 3A i Bus has smell of ozone and probably tripped on actual fault. More troubleshooting will be required Event 5 Respond as requested by Power reduction due to INOPERABILITY of 2 crew AFW pumps Event 6 Activate Trigger 4 MAL-GEN002 Inadvertent Generator Trip MAL-RPS002A Reactor fails to automatically trip manual trip is successful.
MAL-PRS003C PORV starts to leak by can be manuall:: isolated using block valve i lay Respond as requested by the I crew Event 7 Inserted at setup MAL-CFW001 B 33 AFW pump failure to start Role Play Respond as requested by the If asked to investigate 33 AFW pump report the crew pump is mechanically bound and will not rotate.
As Nuc NPO stand by MCC36A1B to open breakers for BFO-2s Insert LOA-CFW066 and LOA-CFW067 to DEENERGIZE when requested I Event 8 Inserted 30 seconds after MAL-PRS003D PORV 455C leak set to 10%
reactor trip U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 4 of20
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: _1_
Event
Description:
Power Escalation Time Position Applicant's Actions or Behavior Note:
The reactivity plan for the power reduction should be developed by the team in the briefing room prior to taking the watch. The plan could call for boration and/or rod insertion CRS Assigns roles for power reduction ATC Reviews reactivity plan ATC If rods are inserted:
- Places/verifies rods are in Manual
- Inserts rods specified number of steps
- Observes:
0 Proper rod motion 0 Tavg 0 Power BOP Peer ch~cks rod insertion ATC If boration is performed:
- USing SOP-CVCS-003
- Places RCS Makeup control to Stop
- Place RCS MakE~up Mode selector to borate
- Adjusts integrator to desired boration amount
- Places RCS Makeup control to Start
- Observes:
0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 5 of20
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _1_
Event
Description:
Power Escalation Time I Position Applicant's Actions or Behavior Lead Evaluator When the following has been demonstrated/observed:
- Sufficient load ascension,
- Sufficient normal plant operations by the BOP .
Then instruct Booth to insert Event 2.
U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open ~ Manual Control AvaiL NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 6 of20
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: l Event
Description:
I Time Position ! Examinee's Actions or Behavior ATC Diagnose 33 MFRV failing open
- Feed Flow to 33 SG increasing
- 33 SG Level Increasing I
- Steam Generator Level Control Deviation Alarm BOP I Refers to ARPs for alarms ATC ~Iaces 33 MFRV in Manual Control and adjusts manual setpoint to lower feed flow
. to lower level i CRS I Directs crew to perform immediate operator actions of 3-AOP-FW-1 ATC performs IOAs of AOP-FW-1
- Checks status of Main Boiler Feed Pumps (MBFP) i
- Announce IOAs complete CRS Announces Entering 3-AOP-FW-1 and begins reading individual steps.
CRS/ATC Identify both MBFPs operating CRS Determines transition to step 4.54 I
I I CRS I
May perform a Crew Brief at this time I Ma~ notif~ Shift Manager that failure has occurred.
CRS/ATC Determine Main Feed Regulating Valve (MFRV) has failed open.
ACT Reports MFRV is in manual and control is functioning. SG level is returning to program.
- CRS/ATC Check status of additional feed system valves - all normal I
CRS Notifies the System Engineer that MFRV needs to be inspected U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 7 of20
Appendix D Scenario Outline Form ES-D-1
. Op-Test No.: _1_ Scenario No.: Event No.: .L Event
Description:
Time I Position Examinee's Actions or Behavior I CRS Notifies 8M Lead Examiner Direct Booth to initiate Event 3 U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 8 of20
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: L Event
Description:
Time Position Examinee's Actions or Behavior I BOP Identify Loss of Letdown/Increase in CCW Surge Tank Level CRS Enter AOP-CVCS-1 Continue with Loss of Letdown I CRS/ATC
- Determine there is a bubble in the Pressurizer I
BOP I Close CH LCV 459 and CH-LCV-460 (Panel SF F)
CRS/ATC i Determines Seal Injection exist Transition to Ste~ 4.20 BOP/ATC Coordinate shutting CH-HCV-142 maintaining discharge header pressure < 2650 psig ATC Adjust charging pump speed to maintain seal injection approximately 6 gpm CRS i Direct NPO to throttle CH-409 (33 Charging Pump Recirculation Valve) as necessary.
I Booth Oe.e,.ator If directed to throttle 409 LOA-CVC031 CRS I Determines excess letdown is dl3sired directs BOP to perform Attachment 2 BOP I Notify HP that -excess letdown will be placed in service BOP Contact Nuc NPO to verify status of RCDT BOP Open the following valves
- AC-AOV-793 (Panel SNF)
I
- AC-AOV-796 (Panel SGF)
- AC-AOV-791 (Panel SNF) i I
- AC-AOV-798 {panel SNF} I BOP I Check CH-HCV-123 Closed (Panel SFF) i U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 9 of20
Appendix 0 Scenario Outline Form ES~D~1 Op-Test No.: _1_ Scenario No.: Event No.:
Event
Description:
Time Position Examinee's Actions or Behavior BOP i Verify CH-AOV-215 in Divert (Panel SFF)
BOP Open the following valves
- CH-AOV-213A (Panel SFF)
- CH-AOV-213B {panel SFF}
BOP Slowly Open CH-HCV-123 (Panel SFF) i BOP When sufficient warm-up (slow rise on TI-122)
- Close CH-HCV-123 (Panel SFF)
~
- Place CH-AOV-215 to NORMAL (Panel SFF) i .... ** Throttle 0een CH-HCV-123 {Panel SFF}
Lead Examiner . Direct Booth Operator to initiate Event 4 i
U3 NRC Scenario I Power Reduction fro 100%, 33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 10 of20
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~
Event
Description:
Time Position Examinee's Actions or Behavior
- --~
.----~-~--~-~--.----
CRS/BOP Multiple alarms - Diagnose Loss of Bus 3A
-~ -- --.-----~-
CRS Enter AOP-480V-1
- ~
~-~--
CRS/BOP Determine power is lost to Bus 3A and RHR was not in service
. ~-
CRS/ATC Determine 33 Charging Pump is running
~-
CRS/BOP Determine 2 CCW Pumps are running r .I *
--~----- -~.
CRS/BOP Determine Essential Service Water Header Pressure is < 60 psig and no SW pumps are operating on the Essential SW Header Start 34 or 36 SW Pump .-
CRSIATC Determine Turbine is on line I CRS/ATC Determine Power has not been lost to IRPI
~-~-~
r~-~--------- - -~-~-------~-~---
CRS/ATC Determine Vacuum NOT decreasing BOP CRS/BOP Determine ISO PHASE BUS RETURN AIR HIGH TEMP alarm is clear I
-~-*-*fc*-**-
~~
CRS/BOP Determine waste release is NOT in progress I
~-- . -- -------~-- ------_.
BOP Dispatch operator to monitor EDGs CRS/ATC Determine IRPI is operable
-~---
~----------
CRS Initiate Review of Tech Specs
ICRS Determine that 2 AFW pumps are inoperable necessitating a shutdown per T.S.
3.7.5
~ -- --........:
U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page II 01'20
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~
I Event D~scri~tion: I1 Time J Position Examinee's Actions or Behavior Booth Operator If necessary call as SM and direct the crew to initiate the shutdown immediately.
i The unit should be off the line in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
CRS I Obtain POP_2.1 and SM permission for power reduction CRS Use Attachment 3 from POP-2.1 for power reduction i I CRS I Record power reduction data and contact the SM to make required notifications l I I CRS , Direct ATC/BOP to perform a Reactivity Calculation for the power reduction ATC/BOP Prepare Reactivity Calculation using the Daily Reactivity Sheet, OPT -25 I
I CRS Assigns roles for power reduction ATC Reviews reactivity plan I
ATC If rods are inserted:
- Places/verifies rods are in Manual
- Inserts rods specified number of steps
- Observes:
0 Proper rod motion 0 Tavg 0 Power BOP ~111::~1\l:> 11l:>I::ILlUII U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 1201'20
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~
I~~~-r~~~--r-------~-----------~---------------------------------------~
Time Position Examinee's Actions or Behavior ATC If boration is performed:
- Energize All Pressurizer Heaters
- Places RCS Makeup control to Stop
- Place RCS Makeup Mode selector to borate
- Adjusts integrator to desired boration amount
- Places RCS Makeup control to Start
- Observes:
0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration ATCIBOP Initiate Turbine Load Reduction at desired rate
- Governor (Preferred)
I
- Load Limit 1
ATC Adjust Control Rod Position per TS and Graph-RPC-16 lead Evaluator When the following has been dEimonstrated/observed:
- Sufficient load reduction.
- Sufficient normal plant operations by the BOP.
il Then instruct Booth to insert Event 6.
U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 13 of20
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~
Event Descri 'on:
Time Position Examinee's Actions or Behavior CRS/ATC Diagnose Turbine Trip with failure of reactor to trip ATC Announce "Tripping the Reactor" then depress the' reactor trip button on the Flight Panel NOTE The CRS may direct tripping the reactor before the ATC makes the announcement.
CRS When Unit trips, direct team to p1arform immediate actions of E-O
- Verifies immediate actions using the procedure.
When the CRS directs "Perform the Immediate Operator Actions of E-O", the A TC and BOP will first perform the IOAs silently only announcing unexpected conditions. The crew will then re-perform the IOAs verbalizing each item.
ATC Verifies Reactor Trip: (Panel FCF)
- Reactor trip and bypass breakers open
- Rod bottom lights lit
- IRPls < 20 steps
- Nuclear flux d ATC Verifies Turbine Trip by observing stop valves closed (Panel FAF)
BOP Check status of 480V buses (Panel SHF)
Observe SA, 2A, and 6A busses energized from Offsite Power ATC Check SI status Determine SI is Actuated
- Any SI Annunciator - Lit (Panel FDF)
- SIPum Panel SBF-1 SBF-2 U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 14 of20
Appendix D Scenario Outline Form ES-D-1 ATC Determines SI NOT actuated and NOT required; however, RCS pressure will be decreasing.
After the "Silent Pass" through the IOAs it is permissible to perform Prudent Operator Actions. This includes closing the PORV Block valve. If the ATC and CRS have diagnosed the leaking PORV, then the PORV Block Valve should be closed at this time. This is Event 8.
If the PORV leak is NOT diagnosed then the crew will continue. il BOP/ATC Check AFW Status II
- Observes Total of all SG flow indicators IS NOT> 686 gpm CRS Transition to ES-O.1 CRS Transition to FR-H.1 due to loss of all AFW U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 15 of20
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: ~
Event Time Position Examinee's Actions or Behavior ATC Diagnose leak by from PORV 45!5C
- Pressurizer PORV and Safety Acoustic Monitoring Annunciator
- Pressurizer Relief Line High Temp Annunciator
- Acoustic Monitor ATC Announce Closing Block Valve for PORV-455C then close the valve.
The CRS may direct closing the PORV Block Valve (535) before the A TC makes the above announcement ATC Verify PORV Block Valve closed and leakage is stopped.
U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 16 of20
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: 1 Event No.:-1.
Event
Description:
~~~~~~~--.---------------------------------------------*------------~I Time Position Examinee's Actions or Behavior CRS/ATC Determine if Heat Sink is required
- Check RCS Temperature> 350°F (Panel FDF)
CRS/BOP Check if Bleed and Feed is required
- Average of the 3 lowest wide range SG Levels < 20% (Panel SCF)
This is NOT expected at this time CRS/BOP Prepare to establish AFW flow
- Check SG Blowdown isolation and sample valves closed(Panel SCF)
- Check CST Level> 3 Feet
- Check valves CT-6 & 64 Open (Panel sCFL ___________-l i
CRS/BOP Establish AFW Flow using Motor Driven Pumps
- Check 480V power available Bus 3A or 6A energized
- Check Motor Driven Pups both running o Start motor driven AFW Pumps
- If unable to start either motor driven AFW Pump, o Close is SG Aux Feed Reg Valves (FCV-406A-406D) o If both motor driven AFW pumps are unavailable Go to Attachment 2fur32Pum~.~p_er_a_ti_o_n ________________________________n CRS/BOP Determine that 32 AFW Pump is NOT available
- Determine 32 AFW Pump NOT running (Tagged Out)
- Determine 32 ABW Pump Overspeed Trip Valve Closed alarm (Panel SKF) is actuated due to tag out
______+!________+-___
- __~R~e~tu~r_n~to~P~ro~c~e~d~u~re_S~e~c.~t~i0~n_S~t~ep~5____.________________________~
I CRS/ATC Stop all RCPs CRS/ATC Try to establish Feedwater flow to any SG BOP
- Check Condensate Pump Power Supplies Available o 6.9 kV buses 1, 2, 4 energized (Panel SHF)
- Go To Attachment 3 to establish feedwater from secondary source.
U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 17 of20
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No,: _1_ Scenario No,: _1_ Event No,: J..
Event DescripJion:
Time Position Examinee's Actions or Behavior CRS/ATC Check if a low pressure water source is available BOP
- Check any condensate pumps running (Panel SCF)
- Check only one condensate pump running o Secure all by one condensate pump
- Check MBFPs any running o Cannot Reset and Start 1 MBFP r-.----+-------~--------~~~~~~~~~~~~~-------------------------~
CRS/BOP Block Automatic SI Actuation
- Check SI NOT Actuated
- Place SI block key switches to DEFEAT (Panel SBF-2)
CRS/BOP Check Condensate Pump only feed source CRS/ATC Depressurize at least ONE SG to less than 380 psig to establish feed flow,
- Manually dump steam using atmospherics from at least one SG at maximum rate CRS/BOP Dispatch NPO to MBFP discharge valve breakers
- Place MFRVs in manual and close (Panel FBF)
- Ensure Bypass FRVs Closed (Panel FBF)
- Place Feedwater Isolation Defeat key switches in DEFEAT o Obtain keys from key locker o 1/FW1DA (Rack G4) o 1/FW1DB (Rack: G-6)
- Check SI Actuated
- Check verification of SI Automatic Actions of step 2 - 12 of RO-1 completed o If BOP available perform steps 2 - 12 of RO-1 o Press both SI Reset buttons on panel SBF-2 i o Check SI Reset - SI Actuated lights extinguished U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control AvaiL NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 180[20
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.:...J..
Event Time Position Examinee's Actions or Behavior CRS/ATC Establish Initial FW conditions BOP
- Ensure Bypass FeedwatE~r MOVs open BFD-MOV-90 BFD-MOV-90-4 (Panel SCF)
- Crack Open Bypass Feedwater FRVs o FCV-417L o FCV-427L o FCV-437L o FCV-447L CRS/ATC Place Steam Flow and Feed Flow Recorders to NARROW
- Steam Flow switches on FBF (Red)
- Manually close MBFP Recirc Valves
- Align MBFP Discharge Valves o Open BFD-MOV-2-31/32 o When valves are Open, direct NPO to open discharge valve breakers on MCC 36A and MCC 36B
. Booth Operator Insert LOA-CPW066 and LOA-CFW067 to DEENERGIZE and valves rlA** AnArl1fi71l,rl ATC Control bypass feedwater FRVs to rapidly resptore at least one SG Narrow Range Level to > 9%
- Control Low Flow Bypass valves Lead Examiner
- Terminate the Scenario when adequate feedwater flow is established.
U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip A vaiL, 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 19 of20
Appendix 0 Scenario Outline Form ES-D-1 Post Scenario Event Classification Event Classification - Alert EAL 1.1.1 Failure of an Automatic trip signal to reduce power range < 5%
AND Manual Trip is successful NOTE: The following event classification is possible depending on plant conditions when scenario is terminated.
Event Classification - Site Area Emergency RED PATH in FO.3 Heat Sink AND Feed and Bleed is required.
U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.
Page 20 of20
Appendix 0 Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.: _2_ Op-Test No.:_1 Examiners: Operators:
Initial Conditions:
Reset simulator to 9% Load Simulator Schedule-Scellari02 The Plant is in Mode 1 just above 9% power preparing to come on line.
Turnover:
Raise power to approximately 12% to place MTG in service. No equipment is out of service .
.... . Event Event No. No. Type* Description 1 N/A R(ATC) Power ascension, maintain SG levels in manual.
N(CRS)
N(BOP) 2 MOC C(CRS) 31 CCW Pump trip with failure of 32 to auto start.
SWSOO7 C(BOP)
TS(CRS) 3 XMT I(ALL) Controlling PZR Pressure transmitter fails high.
RCS028 A TS(CRS) 4 MOV C(CRS) FCV-625 spurious closure.
CCWOO 8 C(BOP)
MAL M(ALL} Steam leak in the Turbine Buildin~~ leading to plant trip. 33 MSIV SGNOO5 fails to close.
6 BKR C(ALL} Entered at setup, Reactor Trip Breakers will not open causing PPLOO3! team to enter FR-S.1.
4 7 MAL C(BOP) Entered at setup, AFW will not auto-start requiring manual action CFWOO1 in FR-S.1 AlC 8 RLY C(CRS) Entered at setup, SI does not automatically actuate. Manual PPL4871 actuation will be required.
8 C(BOP}
- {N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page I of 17
Session Outline:
The scenario begins with the plant at 9% power with no equipment is out of service. The team has been instructed to raise power to approximatl91y 12% and place MTG in service.
After taking the watch, the crew will commence raising power. After the power escalation has progressed, 31 CCW Pump will trip and 32 CCW Pump will fail to auto-start. The team will start 32 CCW pump per ARP-010.
Following the restoration of CCW, a failure high of PT-455 will occur. The team will respond using AOP-INST-1 "Instrument or Controller Failures." The channel will be removed from service.
After the channel is removed from service, FCV-625 will go closed with no apparent reason. The team should respond per ARP-01 0 and re-open the valve. If the team elects to not re-open the valve, the scenario may continue.
Prior to completion of the Subsequent Actions of AOP-CCW-1, a steam break will occur in the turbine building. The team will attempt to manually trip the plant but the reactor trip breakers will not open.
The reactor will not trip from the Control Room and the team will respond per FR-S.1 ,
"Response to Nuclear Power Generation I ATWS," and will shutdown the reactor by manually inserting control rods and initiating Emergency Boration. The reactor trip breakers will be locally opened after an NPO is dispatched. 33 MSIV will fail to close from the control switches. The Team will also determine that SI did not automatically actuate and must manually actuate SI.
The team will proceed through FR-S.1 until transition to E-O, "Reactor Trip or Safety Injection."
After the transition to E-O is made, the team will determine that three SGs are intact and 33 SG is faulted. The team will transition to E-2, Faulted Steam Generator Isolation and isolate 33 SG.
At this point the scenario is terminated.
Procedure flow path: POP-1.3, ARP-010, AOP-INST-1, ARP-010, AOP-UC-1, E-O, FR-S.1, E-O, E-2 Critical Tasks:
CT-1 Insert negative reactivity into the core by at least one of the following methods before completing FR-S.1 step 4:
- De-energize the control rod drive MG sets
- Place rod control in manual and insel1 RCCAs
- Establish emergency boration flow to the RCS.
CT-2 Establish at least 686 gpm AFW flow to the SGs before completion of FR-S.1 step 3.
CT-3 Manually actuate at least one train of SIS actuated safeguards before completion of E-O step 4.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV -625 Closure, Steam Line Rupture, A TWS, Faulted sa.
Page 2 of 17
Simulator Setup and Instructor Directions
, Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSEIINSTRUCTOR CUES IC Reset Use IC for NRC Scenario 2 I Reset Simulator to 9% power Ie 9% Power Starting U~ I SES Setup Run Schedule and verify Loads Reactor Trip Breaker malfunction Schedule malfunctions and over-rides Loads Auto 51 Failure have been entered Loads MS Isolation failure Carefully walk boards and Loads 32 CCW Pump Autostart failure check for items like Turbine Loads 31/33 AFW Pumps Autostart failures and FWH alarms that may be Loads 31 CCW Pump failure on Trigger 1 distractions to candidates. Loads PT-455 failure on Trigger 2 Loads FCV-625 failure on Trigger 3 I Loads Turbine Hall Steam Leak on Trigger 4 Floor Setup Perform setup checklist Event 1 Respond as reqUested~rew performs power ascension
. Crew i Event 2 ~uate Trigger 1 when When directed by the Lead Evaluator, directed activate Trigger 1 to cause 31 CCW Pump to trip.
MAL-CCW001A to TRIP Role Play If called to check 31 and 32 3'1 CCW Pump Motor has slight acrid odor.
CCWPumps Breaker tripped on over-current. The pump that was started is operating with no issues .
. 32 CCW Pump, Motor, and Breaker all aQQear normal I Event 3 Actuate Trigger 2 when When directed by the Lead Evaluator, directed activate Trigger 2 to cause PT-455 to fail high with a 60 second ramp.
MAL-PRS005A to 2500 with 60s ramp Role Play If I&C is contacted about Report back that a troubleshooting package PT-455 failure will be prepared Event 4 Actuate Trigger 3 vVhen directed by the Lead Evaluator, activate Trigger 3 to FCV-625 to fail closed.
At lead evaluator direction SWI-CCW010C to On AS SOON AS VALVE GOES CLOSED ACTIVATE TRIGGER 29 TO REMOVE OVERRIDE L__ ~.
I I U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SO.
Page 3 of 17
Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play I When Nuclear NPO Nuke NPO reports that flow at FIC-625 is dispatched normal after valve is re-opened.
EventS Actuate Trigger 4 VVhen directed by the Lead Evaluator, i activate Trigger 4:
At lead evaluator Insert MAL-MSS009A to 6650000 in 600 direction Role Play If NPO dispatched to look If NPOs are dispatched to look for steam, for steam leak report back that a large steam leak exists at the north end of the turbine hall.
Role Play NPO cannot locally trip If trigger does not work, remove overrides reactor until Emergency preventing reactor trip. May have to insert Boration is commenced. manual reactor trip Actuate Trigger 30 to trip reactor.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT 455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SO.
Page 4 of 17
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: ...L Event No.: _1_ Page _1_of .1 Event
Description:
Power Ascension Time Position Applicant's Actions or Behavior Note:
The reactivity plan for the power ascension should be developed by team in briefing room prior to taking the watch. The plan could call for dilution and/or rod withdrawal.
CRS Assigns roles for power ascension ATe Reviews reactivity plan ATe If rods are withdrawn:
- Places/verifies rods are in Manual
- Withdraws rods
- Observes:
0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod withdrawal ATe If dilution is performed:
- Places ReS Makeup control to Stop
- Place ReS Makeup Mode selector to Dilute
- Adjusts integrator to desired dilution amount
- Places ReS Makeup control to Start
- Observes:
0 Proper makeup responsEi 0 Tavg 0 Power BOP Peer check dilution Adjust Low Flow Feed Reg Valves to maintain SG levels.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 5 of 17
Appendix 0 Required Operator Actions Form Lead Evaluator When the following has been demonstrated/observed:
- Sufficient load ascension.
- Sufficient normal plant operations by the BOP.
Then instruct Booth to insert Event 2.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SO.
Page 6 of 17
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: ~ Event No.: -.l... Page Event
Description:
31 CCW Pump trip Time Position Applicant's Actions or Behavior BOP Observes CCW Pump Discharge Alarms and only 33 CCW Pump running BOP Recommends/announces starting 32 CCW Pump BOP May refers to ARP 3-ARP-10 CRS Concurs with recommendation or orders 32 CCW Pump start BOP Starts 32 CCW Pump CRS May enter AOP-CCW-1 CRS Refers to T.S. 3.7.8 and TRM 3.7.B and determines plant is in a 30 Day AOT Lead Evaluator After CRS has evaluated TRMITS. have Booth initiate Event 3 U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS" Faulted SO.
Page 7 of17
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: L Event No.: -L Page_1_of Event
Description:
Controlling PZR Pressure transmitter fails high Time Position Applicant's Actions or Behavior BOP PZR Hjgh Pressure Channel Trip and PZR Hjgh Pressure alarms ATC Diagnose PZR Pressure instrument failure based on above and Spray Valves opening Announces and places Master Pressure Controller in Manual CRS Instructs team to perform immediate operator actions of AOP-INST-1 ATC Checks all instrumentation listed in AOP-INST-1 for failures Announces immediate operator actions complete CRS Announces entry into AOP-INST-1 Re-checks all instrumentation with ATC Verifies PZR pressure is in Manual CRS Directs BOP to defeat PT-455 in pressure control circuit and delta-t circuit BOP In Rack B-6 places P/455A in Defeat 1 & 4 BOP In Rack B-8 places T/4111A in Defeat Loop 1 ATC Switches recorder to an operable channel ATC Returns Master Pressure Controller to Auto CRS Refers to T.S.
Table 3.3.1-1 Function 5 and 7 Table 3.3.2-1 Function 1d and 7 Determines in 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AOT to trip bistables May have T.S. condition due to low PZR Pressure 3.4.1 Condition A Lead Evaluator Bistables do not have to be tripped. When T.S. evaluated instruct Booth to insert Event 4 U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 8 of 17
_A---,--p,,-pe_n_d_i_x_O~______R_e.quired Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.:..1.- Event No.: ~ Page _1_of ..1 Event
Description:
FCV-625 spurious closure ,
Time Position Applicant's Actions or Behavior BOP Notes CCW Thermal Barrier Return Low Flow alarm
! BOP Observes FCV-625 has gone closed BOP Refers to ARP-01 0 Note:
CRS should determine based on ARP guidance and indications that the closure was spurious and re-opening the valve is appropriate. If the valve remains closed, the scenario can continue.
BOP Re-open FCV-625 BOP Direct Nuke NPO to monitor flow at FI-625 Lead Evaluator When valve is re-opened, or it is clear it will remain closed, instruct Booth to initiate Event 5.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 9 of 17
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: -.L Event No.: i Page _1_of J.
Event
Description:
Steam leak in the Turbine Building leading to plant trip.
Time Position App,licant's Actions or Behavior ATC Diagnose Steam Leak:
- Power increase
- Tavg decrease
- Steam Flow increase
- Trip Reactor (Reactor does not trip)
- Go to E-O Proceed to Event 6 when CRS gives order to trip reactor U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 10 of 17
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: Event No.: 6/7_ Page _1_of .1 Event
Description:
Entered at setup, Reactor Trip Bneakers will not open causing team to enter 2-FR S.1. Entered at setu AFW will not auto-start manual action in FR-S.1 Time licant's Actions or Behavior Will ~ttml')t to tri reactor BOP Start 31 and 33 or 32 AFW Pumps establish 686 gpm BOP/ATC Initiate Emergency Boration:
- Verify Charging Pump running
- Open MOV-333~
- Close HCV-104/10S
- Place both boric acid pumps in high speed and restart
- Place Charging Pump in manual
- Maximize char!ging pump speed At this point the Booth willi trip the reactor locally.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted SO.
Page 11 of 17
~ppendix D Required Operator Actions Form ES-D-2 Note:
At this point or prior, the crew may attempt to close MSIVs. When 33 MSIV does not close, AFW should be secured to 33 SG. Also with the reactor tripped, the crew may back down on AFW flow.
Op-Test No.: _1_ Scenario No.:..L Event No.: -1L Page_1_of A Event
Description:
Entered at setup, SI does not automatically actuate. Manual actuation will be required.
Time Position icant's Actions or Behavior CRS/ATC Recognize that SI should have actuated and is needed for Steamline delta-p ATC/BOP Manually actuate SI ATC May restart charging pump BOP Perform Steps 35-42 of E-O:
- Verify SI Pumps Running
- Open SW VaIVE!S for Containment Cooling
- Reactor trip brE!akers open
- Neutron flux decreasing
- Rod bottom lights lit
- IRPls all < 20 Steps U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 12 of 17
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: -L. Event No.: Page-L.of ~
Event
Description:
Entered at setup, SI does not automatically actuate. lVIanual actuation will be required.
CRS/ATC Secure Emergency Boration
- Close MOV-333
- Place BATPs in slow
- Open HCV-104/105 to 25%
CRS/ATC Check RCP Seal Cooling (if charging was not started and FCV-625 was left closed, RCPs may be tripped at this point)
CRStATC Restore charging flow CRSt Verify SDM With SI. this is not necessary. but the team may start a boration CRS Transition to E-O ATC Verifies Reactor Trip: (Panel FCF)
- Reactor trip and bypass breakers open
- Rod bottom lights lit
- IRPls < 20 steps ATC Verifies Turbine Trip by ()bserving stop valves closed (Panel FAF)
BOP Check status of 480V buses (Panel SHF)
Observe ALL busses energized from Offsite Power ATC Check SI status Determine SI is Actuated
- Any SI Annunciator - Lit (Panel FDF)
- SI Pumps Any Running (Panel SBF-1, SBF-2)
ATC/BOP Manually Actuates SI U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 13 ofl7
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: .JL.
Event
Description:
Entered at setup, SI does not automatically actuate. Manual actuation will be required.
BOP/ATC Check AFW Status Observes Total of all SG flow indicators> 365 gpm (Panel SCF)
Controls feed flow to maintain SG levels 9 - 50%
- Adjust flow control valve potentiometers CRS Direct BOP to perform RO-1 BOP Operator Actions during use of EOPs ATC Verify Feedwater Isolation
- Check Main Boiler Feed Pumps Tripped (Panel FAF)
- Check MBFP Discharge Valves Closed (Panel FAF)
- Check Feed Reg Valves and Bypasses Closedllsolated o Main and Bypass MOVs Closed (Panel SCF) o Main FRVs 2 is True (Panel SNF) o Bypass FRVs (Panel FAF)
ATC Check Blowdown Isolation Valves Closed (Panel SCF)
- Check Pressure < 1700 psig (Panel FBF, or FDF)
- Check High Head Pump Flow Indicators (Panel SBF-2)
- Check Pressure < 360 psig (Panel FDF WR Press Recorder)
- Check RHR Pumps Flow Indicators (Panel SBF-2_
ATC Verify Containment Spray NOT required
- Check Containment Pressure remained < 22 psig (Panel J01 or SBF-2)
- Bearing Coolant Low Flow Alarm Clear (Panel SGF)
ATC Establish Charging Flow U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 14 of 17
_A---L....pL-pe_n__d_i_x_D_ _ _._ __R_e_q.L...u~ir.~d Operator Actions ATC Check RCS Temperature ATC Check if RCPs should be stopped. RCPs may have been secured earlier.
They will not be tripped at this step.
ATC Check PORVs, Safety Valves, Sprays Closed Op-Test No.: Scenario No.: Event No.: ~ Page~of~
Event
Description:
Entered at setup, SI does not automatically actuate. Manual actuation will be required.
CRS/ATC Determine 33 SG is faulted CRS Announce entry into E-2 NOTE:
E-2 contains the first specific steps to close MSIVs and isolate AFW flow to faulted SG.
However, there is administrative guidance to take these actions ahead of E-2 steps. It is expected that these actions would have been taken either in FR-S.1 after the reactor being tripped locally or in E-O. If these actions have not been taken at this point, the scenario may continue to allow the team to take actions per E-~~.
Lead Evaluator Terminate Scenario U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, A TWS, Faulted SG.
Page 15 of 17
Post Scenario Event Classification Event Classification - Site Area EmergencyAh3rt EAL 1.1.2 RED path in Subcriticality and all attempts at tripping the reactor from the control room have failed to reduce power range < 5%.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.
Page 16 of 17
DatelTime: Today/Now Condition: Plant Startup
% Power:
Xenon: Equilibrium RCS Boron: 1547 ppm Rods CB D - 128 PZR Press Control: Channel 1 PZR Level Control: Channel 2 RCS Total Leakage: 0.1 gpm RCS Unidentified Leakage: 0.01 gpm Condenser Air leakage 6SCFM RCS Gas activity 1.78E-2 I-ICi/cc Risk Assessment: Green Plant Equipment Status:
Plant is at 9% power with a startup in progress. No equipment is out of service.
Instructions:
Raise power to approximately 12% power and then warm up and place the MTG in service.
U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted sa.
Page 17 of 17
Appendix 0 Scenario Outline Form ES-O-1 Facility: IPEC Unit 3 Scenario No.: 3 Op-Test No.: 1 Examiners: Operators:
Initial Conditions: 34% Power IC-153 PORV 455C Leaks by seat - Block Valve 535 is closed Turnover:
Raise Power to 100%.
Event Malf. No. Event Event No. Type" Description R (ATC) 1 N/A N (CRS)
Power Increase N (BOP)
I (ALL) 2 MAL- Controlling Pressurizer Level Channel fails low TS (CRS)
PRS006 B
PORV 456 leaks by seat. Close PORV Block Valve.
PRS003 10 i I (ALL) 4 MAL- PT -412B failurE! causing AMSAC to be inoperable and requiring TS (CRS)
TUR010 tripping of bistables B
M (ALL) 5 MAL- Loop Flow Transmitter penetration failure (SBLOCA)
RCS017 A
C (BOP) 6 . MAL- 31 AFW Pump Trip C (CRS)
! CFW001 A
7 MAL-M (ALL)
SG Tube Leak to Rupture 32 SG I SGN005 B
- (N)ormal, (R)eactivity, (I)nstrument (C)omponent, (M)ajor U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page I of33
Appendix 0 Scenario Outline Form ES-O-1 Session Outline:
The evaluation begins with power is at 34% steady state. The crew will be directed to raise power to 100%.
After adequate power change has occurred, Pressurizer Level Channel LT-460 will fail low resulting in a loss of letdown. The crew will respond in accordance with 3-AOP-INST-1, Instrument and Controller Failures. The procedure will address both the instrumentationlTech Spec actions and restoration of charging and letdown. This is a Tech Spec for Instrumentation.
At lead examiner discretion, Pressurizer PORV 456 will start to leak past seat. The crew will attempt to close the PORV which will not be successful. The crew will then close the motor operated block valve At lead examiner discretion, PT-4128 will fail low requiring bypassing AMSAC and tripping bistables. This is a Tech Spec for Instrumentation.
At lead examiner discretion, 31 Loop Flow Transmitter Penetration will fail resulting in a small break LOCA The crew may respond using 3-AOP-LEAK-1. The crew will likely trip the reactor and manually actuate Safety Injection.
Following the Safety Injection 31 AFW pump will trip on overcurrent. This will require the crew to start 32 AFW pump to supply flow to 31 and 32 SG.
The crew will proceed through E-O to E-1. When the crew enters E-1 a SGTR will occur in 32 SG. The crew will transition to E-3 when diagnostic check for SGTR or on Foldout page based on uncontrolled level increase.
The crew will perform actions in E-3. After the cooldown, the crew will not be able to use normal spray to depressurize the RCS. The crew will depressurize the RCS using the PORV. After depressurization actions the procedure checks 51 Termination Criteria and this will not be met (RCS pressure will not be stable or increasing) and transition to ECA-3.1due to LOCA with SGTR.
The scenario will be terminated when the team demonstrates they control plant Cooldown or at the lead examiners discretion.
Procedure Flowpath: POP-1.3, AOP-INST-1, ARP-FAF, AOP-INST-1, AOP-LEAK-1, E-O, E-1, E-3, ECA-3.1 Critical Tasks:
CT-1 E-O-M Close block MOV upstream of stuck-open PZR PORV by completion of the first step in the ERG network that directs the crew to close the block valve.
CT-2 Isolate feed to 32 SG prior to completion of E-3 Step 3.
CT-3 Initiate RCS Cooldown of <100 °F/hr to prE~vent SG overfill in ECA-3.1 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 2 of33
Appendix 0 Scenario Outline Form ES-O-1 Simulator Setup and Instructor Directions i Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSEIINSTRUCTOR CUES IC Reset Reset Simulator to IC-153 SES Setup Insert malfunction MAL- PRESSURIZER LEVEL CHANNEL 460 FAILURE Schedule PRS006B to 0 on event 2 Insert malfunction MAL PRESSURIZER RELIEF VALVE 456 VALVE PRS003D to 10.00000 in 60 on POSITION FAILURE event 3 Insert malfunction MAL TURB FIRST-STAGE PRESS TRANS FAILURE TUR01 DB to 200.24899 on event (PT-412B) 4 Insert malfunction MAL FAILURE OF FLOW TAP PENETRATION FT-414 RCSO 17A on event 5 Insert malfunction MAL AUXILIARY FEEDWATER PUMP 31 FAILURES CFW001A to TRIP on Insert malfunction MAL STEAM GENERATOR 32 TUBE LEAK SGN005B to 10.00000 on event 7
Insert override SWI-AIR002C to PCV-1228 OPEN POS INSTRUMENT AIR ISOL Off on event 30 VLV NO. PCV-1228 CONTROL SWITCH Create Event 30 JPPLP4(1 }==1 Actuate Trigger 30 when the Reactor Trips (which
-desc Set Trigger 30 to actuate will then prevent 1228 from opening when attempted) i i after Reactor Trip SES Setup Load Schedule and verify Schedule malfunctions and overrides have been entered Floor Setup Perform Setup Checklist Hang CTO on PORV Block Valve 535 Close PORV Block Valve
, and hang CTO Risk is ?????
Event 1 Respond as requested by the . Crew performs power ascension i
- crew
. Event 2 I Actuate Trigger 2 MAL PRS006B LT-460 fails low isolating i letdown Role Play I Acknowledge requests for I&C will develop a troubleshooting plan i I&C to troubleshoot Event 3 Activate trigger 3 MAL-PRS003D PORV 456 starts to leak by.
Role Play I Respond as requested by the crew U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 3 of33
Appendix 0 Scenario Outline Form ES-O-1 Event 4 Activate trigger 4 MAL-TUR10B PT-412B Fails low.
Role Play
- Respond as requested by the i crew
- Event 5 Activate Trigger 5 i MAL-RCS017 A Failure of RCS flow tap. This is
- a small LOCA.
Role Play Respond as requested by the
- crew I Event 6 I Loaded at setup MAL-CFW001A Trip of 31 AFW Pump I Role Play
- Respond as requested by the I crew Event 7 : Activate Trigger 7 MAL-SGN005B Tube rupture in 32 SG
. Role Play i Respond as requested by the ;
I crew I I I
U3 NRC Scenario 3 Power increase from 35%,LT*460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 4 of33
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: L Event No.: _1_
Event
Description:
Power Escalation Time Position Applicant's Actions or Behavior The reactivity plan for the power ascension should be developed by the team in the briefing room prior to takin! the watch. The plan could call for dilution and/or rod withdrawal CRS Assigns roles for power ascension Reviews reactivity plan ATC If rods are withdrawn:
- Places/verifies rods are in Manual
- Withdraws rods
- Observes:
o Proper rod motion o Tavg o Power BOP Peer checks rod withdrawal ATC If dilution is performed:
- Places RCS Makeup control to Stop
- Place RCS Makeup Mode selector to Dilute
- Adjusts integrator to desired dilution amount
- Places RCS Makeup control to Start
- Observes:
o Proper makeup response o Tavg o Power BOP Peer check dilution U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 5 of33
Appendix D Scenario Outline Form ES-D-1 ATe/BOP Initiate Turbine Load Increase at desired rate
- Governor (Preferred)
- Load Limit 1
- Load Limit 2 Lead Evaluator When the following has been demonstrated/observed:
- Sufficient load ascension.
- Sufficient normal plant operations by the BOP.
Then instruct Booth to insert Event 2.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 3 I AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 6 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: ~
Event Descri tion: Failure of Pressuriz_e_r_C'-o'-ntr_o_lI......
__ in.....g_L_e_v-'-e_1C.c--ha__nn-ce_I______________
..... ----11 Time Examinee's Actions or Behavior ATC/BOP Diagnose Failure of LT-460 I
i ATC Place 33 charging pump in Manual and stabilize pressurizer level.
. CRS Direct Perform Immediate Operator Actions of AOP-INST-1 i i
ATC Silently evaluates for failure of control system inputs
- Rod Control 0 NIS Power Range 0 RCS Temp 0 Turbine 1st Stage Pressure
- Pressurizer Pressure
- Pressurizer Level Control 0 RCS Temperature
- SG Pressure Control 0 Atmospheric Steam Dumps i 0 High Pressure Steam Dumps CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbalizing each input I
i I
U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 7 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: ~
Event
Description:
Failure of Pressurizer Controlling Level Channel Time Position Examinee's Actions or Behavior CRS/ATC Determine an Instrument failure has occurred.
CRS Identify section 4.105 of procedure CRS/ATC Determine the charging pump is in manual speed controlling pressurizer level in accordance with Graph RCS-2 CRS/ATC Determine channel has failed low CRS/BOP Place Ll460A LEVEL DEFEAT switch in DEFEAT CH 2 (RACK B-6 CRS/BOP Determine Letdown is isolated (LCV-459 is closed) (Panel SFF)
CRS/BOP Close Orifice Isolation Valve (CH-AOV-200 A - C) (Panel SFF)
CRS/BOP Place CH-PCV-135 Controller in MAN and adjust output to 50% (Panel SF F)
CRS/BOP Place AC-TCV-130 Controller in MAN and adjust output to 50% (Panel SFF)
CRS/BOP Determine CH-AOV-201 and 202 are OPEN (Panel SFF)
CRS/BOP Determine CH-LCV-459 is closed and OPEN CH-AOV-459 and return to AUTO (Panel SFF)
CRS/BOP Open ONE Orifice Isolation Valve (Panel SFF)
- CH-AOV-200C BOP/ATC Coordinate to adjust charging flow as necessary
- Charging pump speed (Panel FBF)
- Open HCV-142(Panel SFF)
- Close CH-409 (Local Action)
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 4561eak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 8 of33
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: -.1.. Event No.: .2..
j::vent D~scrietion: Failure of Pressurizer Controlling Lelvel Channel Time ! Position I i
Examinee's Actions or Behavior CRS/BOP I Adjust CH-PCV-135 as necessary to prevent flashing in the letdown line (Throttle closed to raise pressure to approximately 250 psig (Panel SF F)
CRS/BOP Acljust AC-TCV-130 as necessary to maintain letdown temperature 100 - 130°F CRS/ATC Place Modulating Heater switch to off for 5 seconds then Start and return to AUTO CRS/ATC Place control switch for Pressurizer Backup Heaters to OFF for 5 seconds then i return to auto.
CRS/ATC Place one set of Backup Heaters to ON. NOTE: Heaters were in ON for dilution for
- power ascension. Crew may return all heaters to ON.
CRS/ATC Determine if Pressurizer Level Recorder is selected to a Non-Affected Channel and
. select an operable channel if necessary CRS Refer to Technical SpeCifications CRS Determines 0 TS 3.3.1-1 Function 8 AOT -6Hours 0 TS 3.3.3-1 Function 12 AOT 30 days 0 TS Basis 3.3.4 I 0 TRO 3.3.0.1 AOT 30 Dal's
\ CRS/BOP Determine that NO redundant Bistable Status Lights are illuminated (Panel SOF)
CRS/BOP Trip Bistables for LT -460 Rack White A-10 Bistable LOOP 2, High Level CRS/BOP Check Bistable Status Light for failed instrument illuminated Lead Examiner I nstruct the Booth to insert Event 3
, Tripping bistable has no impact on the remainder of the scenario. Once Letdown is i restore, the scenario can proceed.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak. PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 90f33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: --L Event No.: ~
Event PORV 456 Leaks seat Time Position Examinee's Actions or Behavior ATC Diagnose leak by from PORV 456
- Pressurizer PORV and Safety Acoustic Monitoring Annunciator
- Pressurizer Relief Line High Temp Annunciator
- Acoustic Monitor ATC Announce Closing Block Valve for PORV-455C then close the valve.
The CRS may direct closing the PORV Block Valve (536) before the A TC makes the above announcement Verify PORV Block Valve closed and leakage is stopped.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 10 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: ~ Event No.:
Event
Description:
Turbine First StClge Pressure Transmitter Failure Low i
Time Position Examinee's Actions or Behavior ATCIBOP Diagnose Failure of PT-412B r--
i CRS I Direct p~rform Immediate Operator Actions of AOP-INST-1 ATC Silently evaluates for failure of control system inputs
- Rod Control 0 NIS Power Range 0 RCS Temp st 0 Turbine 1 Stage Pressure
- Pressurizer Pressure
- Pressurizer Level Control 0 RCS Temperature
- SG Pressure Control 0 Atmospheric Steam Dumps i
0 High Pressure Steam Dumps i CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbalizing each input I CRS/ATC Determine an Instrument failure has occurred.
i CRS Identify section 4.172 of procedure i
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SaTR 32 SO, Steam Generator Tube Rupture with LOCA.
Page 11 of33
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: .L Event No.: ~
Event
Description:
Turbine FirstStage Pressure Transmitter Failure Low i
Time I Position Examinee's Actions or Behavior CRS/ATC Determine Channel A has NOT failed.
CRS/ATC Check Steam Dumps NOT in Pn3ssure Mode Place Steam Dumps in Pressure Mode
- Place Steam Dump Controller in Manual (Panel FCF)
- Adjust Steam Dump Controller output to 0%
I
- Place Steam Dump Control Switch to RESET and return to PRESS CO NT I--
- Place Steam Dump Controller in AUTO i CRS/BOP . Place BS/2MSS 400 block switch in AMSAC cabinet to BYPASS (UP) position to i block AMSAC system CRS Refer to Technical SpeCifications o TS 3.3.1-1 Function 17b Completion Time 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> o TS 3.3.1.1 Function 17e Completion Time 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> o TS 3.3.2-1 Function 19 AOT 6 Hours o TS 3.3.2-1 Function 4d AOT 6Hours o TS 3.3.2-1 Function 4e AOT 6Hours CRS/BOP Determine that NO redundant Bistable Status Lights are illuminated (Panel SOF)
CRS/BOP Trip Bistables for PT-412B
i CRS/BOP Check Bistable Status Light for failed instrument illuminated Lead Examiner Instruct the Booth to insert Event 5 Tripping bistable has no impact on the remainder of the scenario.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 12 of33
Appendix 0 Scenario Outline Form ES~D~1 Op-Test No.: _1_ Scenario No.: L Event No.: ~
Event
Description:
RSC Leak/Small Break LOCA Time I Position Examinee's Actions or Behavior ATC Diagnose RCS Leak
- Decreasing Pressurizer Level and Pressure (Panel FBF)
- PRZR LOW PRESSURE Annunciator
- PRZR LOW LEVEL Annunciator
- VC SUMP PUMP RUNNING Annunciator
- C.B. COOLER COND HIGH LEVEL Annunciator CRS Enter AOP-LEAK~ 1 CRS/ATC If At Any Time step to Isolate Leak if location is known. Determines location of leak i
is NOT know BOP I
CRS/BOP Determine plant is NOT on RHF! cooling CRS/ATC If At Any Time Step to Trip the Reactor and Initiate SI if Pressurizer Pressure decreases to s 1930 psig.
Evaluate RCS Pressure - If < 1930
- Trip the Reactor
- Verify Reactor Tripped
- Manually Actuate SI
- Go To E-O CRS/ATC If At Any Time Step to Trip the Reactor and Initiate SI if Pressurizer Level cannot be maintained with 2 charging pumps in service and letdown flow at 45 gpm or < 14%
Evaluate PRZR Level - If conditions are satisfied
- Trip the Reactor
- Verify Reactor Tripped
- Manually Actuate SI i
- Go To E-O CRS/ATC As necessary:
- Increase Charging Pump Speed nd
- Start 2 Charging Pump i L
- Reduce Letdown to 45 gem I : CRS/ATC Determine there is NO PORV leakage.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 13 of33
Appendix D Scenario Outline Form ES-D-1 CRS/ATC Determine there is NO indication of Safet~ Valve Leakage CRS/ATC Determine leak is too large. Direct Reactor Trip and Safety Injection.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOeA.
Page 14 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: L Event No.: L Event
Description:
Reactor Trip and Safety Injection Time Position Examinee's Actions or Behavior CRS When Unit trips. direct team to perform immediate actions of E-O
- Verifies immediate actions using the procedure.
I I When the CRS directs "Perform the Immediate Operator Actions of E-O, the A TC and BOP will first
- perform the IOAs silently only announcing unexpected conditions. The crew will then re-perform the IOAs vfJrbalizim each item.
ATC Verifies Reactor Trip: (Panel FCF)
- Reactor trip and bypass breakers open
- Rod bottom lights lit i
- IRPls < 20 steps
- Nuclear flux decreasing ATC Verifies Turbine Trip by observing stop valves closed {Panel FAF}
BOP Check status of 480V buses (Panel SHF)
- Any SI Annunciator - Lit (Panel FDF)
- SI Pum s An Runnm -
Panel SBF 1, SBF 2 ATC/BOP Manually Actuates SI if--"---+-----r----. Depresses SI Actuation pushb'-u_tt_o_n...l.(_P_an_e".;...I_S_B_F-'-_ _ _ _ _ _ _ _ _-l1 BOP/ATC Check AFW Status Observes Total of all SG flow indicators> 365 gpm (Panel SCF)
Controls feed flow to maintain SG levels 9 - 50%
Ir--_ _-+_ _ _ _r---_._ _A.;...d""'*..;.;.us"-'t'-.f...:.lo--'w control valv~; potentiometers CRS Direct BQP to perform RO-1 BOP Operator Actions durin use of EOPs U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 15 of33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: L Event
Description:
Reactor Tri(:! and Safet;, Injection Time Position Examinee's Actions or Behavior ATe Verify Feedwater Isolation
- Check Main Boiler Feed Pumps Tripped (Panel FAF)
- Check MBFP Discharge Valves Closed (Panel FAF)
- Check Feed Reg Valves and Bypasses Closedllsolated 0 Main and Bypass MOVs Closed (Panel SCF) 0 Main FRVs 2 is True (Panel SNF) 0 Bl~ass FRVs (panel FAF}
ATC Check Slowdown Isol(1tion Valves Closed (Panel SCF)
- Check Pressure < 1700 psig (panel FBF, or FDF)
- Check High Head Pump Flow Indicators (Panel SBF-2)
- Check Pressure < 360 psig (Panel FDF WR Press Recorder)
ATC Verify Containment Spray NOT required
!
- Bearing Coolant Low Flow Alarm Clear (Panel SGF) i
ATC Establish Charging Flow
- Check CCW Available (Panel SBF-1 lights only this is adequate; Panel SGF Breakers & Flow indicators)
- Check HCV 142 Fully Open (Panel SFF)
- Check CH-AOV-204B Open (Panel SFF)
- Open CH-LCV-112B (Panel SFF)
- Then Close CH-LCV-112C (Panels SFF)
- Set Speed Controller to Starting Position (Panel FBF)
I
- Start 1 Charging Pump (Panel FBF)
- Adjust Speed for Minimum Seal Injection (Panel SAF)
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 16 of33
Appendix 0 Scenario Outline Form ES-D-1
~
Op-Test No.: _1_ Scenario No.: Event No.: L i Event
Description:
Reactor Tri~ and Safety Injection Time Position Examinee's Actions or Behavior ATC Check RCS Average Temperature
- Any RCPs Running - Tc,wg Trending to 547°F (Panel FDF)
- No RCPs running - Tcold Trending to 547°F (Panel FDF)
- If Temp < 547" and decreasing 0 Stop Dumping Steam 0 Control Total Feed Flow 0 Maintain> 365 until one SG > 9%
0 If cooldown continues, Close MSIVS
- If Temp> 547" and incn:!asing 0 Dump steam to condenser 0 DUI11~ Steam using Atmos~herics ATC Check if RCPs should be stoppEld
- At least 1 HHSI Pump running (Panel SBF-2)
- Subcooling < value in table (QSPDS Monitor on desk) i
Check Safety Valves Closed
- Tailpipe Temperatures Normal (Panel FBF)
- Acoustic Monitors Normal (Above Door into Supervisory Panel)
Spray Valves Closed (Panel FBF)
Check Aux Spray Valve Closed Panel (Panel SFIL ATC Determine if SGs are Faulted
- Any SG Pressure decreasing in uncontrolled manner (Panel FBF)
- Any SG Com~letely depressurized {Panel FBF}
ATC Determine if SG Tubes are Ruptured
- Condenser Air Ejector Radiation recorder Trend (Rad Monitor Rack)
- SG Blowdown Recorder Trend (Rad Monitor Rack)
- Main Steam Line Radiation Recorders (Rack 0-3 behind the Flight Panel)
- Any SG level increasin!~ in an uncontrolled manner (Panel FBF)
U3 NRC Scenario 3 Power increase from 35%,LT -460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 17 of33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: L Event No.: L Event
Description:
Reactor Trip and Safety Injection Time i Position Examinee's Actions or Behavior ATC Check if RCS is intact
- Containment Pressure Normal (Panel J-O or SBF-1)
- Containment Sump Level Normal (Panel J-O)
- Containment Radiation Normal 0 R-2 and R-7(Rack D-1 Behind Flight Panel)
I l 0 R-25 and R-26 CRS l~o TO E-j Booth Operator : When crew enters E-1 Activate Trigger 7 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4l2B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 1.8 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 5 & 6
- Event
Description:
BOP Operator Actions - Automatic Action Verification ~
I I Time Position II---......--'--+----'---'--+--~----------'-
Examinee's Actions or -Behavior
---'--------. .1
. BOP Enter RO-1
---+--
BOP Monitor Control Room Alarms
- Acknowledge Supervisory Alarms
- Report Unusual Alarms
- Monitor High Containment Temp alarm (SCF)
- Monitor 480 Safeguards Undervoltage alarm.>..(:S::..:B::..:F-,,2=~}_ _ _ _ _ _ _ _--11 BOP Verify SI Pumps running
- Three SI Pumps (SBF-2)
- Two RHR Pumps (SBF-1 or SGF)
BOP Verify Containment FCU Status
- Check all FCU running
- Place Damper Control Switches in Incident Mode (Panel SBF-2) o Damper AlB Closed o Damper C Closed o Damper D Open
- Place Control Switches for 1104 and 1105 to Open (Panel SBF-1)
- Safeguards Valve Off Normal alarm CLEAR
- Ensure following OPEN o BIT Discharge 1835A1B (Panel SBF-2) o BIT Inlet 1852AJB (Panel SBF-2) o High Head Stop Valves 856J, H, C, E (Panel SBF-2)
- Check if MSIVS should remain OPEN o High Steam Flow SIIHi-Hi VC Pressure Alarm Clear (FDF)
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 19 of33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:.....L Event No.: 5 & 6_
- Event
Description:
BOP Operator Actions - Automatic Action Verification I Time Position Examinee's Actions or Behavior BOP Verify Aux Boiler Feed Pump Status
- Check Motor Driven Pumps Both Running 0 Only 3'JAFW Pump is running
- Check Turbine Pump Running 0 Raise Speed of 32 AFW PUMP (Panel SCF) 0 OPEN Aux Feed Reg Valves 405A and 405B to feed 31 and 32 SGs BOP Verify Aux Feed Valve Alignment
- Motor driven AFW Pumps (Panel SCF) 0 Set 406A - D to full open (Panel SCF)
- Check SG Blowdown isolation valves CLOSED (Panel SCF)
- All 3 Pumps Running i I
I
I BOP Check Essential Service Water Pumps - 3 Running BOP Verify Containment Ventilation Phase A & B (Panel SNF)
- Phase A actuated
- Phase B Actuated
- Check Phase A valve CLOSED I
- Check Phase B valves CLOSED BOP Verify Containment Ventilation Isolation
- Purge Valves CLOSED 0 FCV-1170 - 1173 (Panel SLF)
- Pressure Relief Valves CLOSED 0 PCV-1190 - 1192 (Panel SLF)
- Check WCCPP Low Pressure Zone Alarms NOT Lit.
- Verify IVSWS Valves OPEN 0 IV-AOV-1410,IV-AOV-1413 I 0 IV-SOV-6200,IV-SOV-6201 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 sa, Steam Generator Tube Rupture with LOCA.
Page 20 of33
. Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: . l Event No.: 5 & 6_
Event Desc;ri~tion: BOP 9~erator Actions - Automatic Action Verification Time Position Examinee's Actions or Behavior BOP Verify Emergency Diesel Generator Status
- Check ALL EDGs RUNNING (Panel SBF-2)
- Check EDG Outlet Flow Control Valves OPEN i 0 FCV-1176/1776A (Panel SBF-2}
BOP Verify Control Room Ventilation
- Set Control Room Ventilation Control Switch to 10% incident mode (By Supervisory Panel Entrance)
- Check Damper Status 0 A-Dim 0 B - Bright
\
0 Either F1 or F2 Bright 0 Dampers D1 and D2 Bright
- Verify AlC Compressors and fans ALL Running 0 ACC 31A1B ON Bright 0 ACC 32 AlB 01\1 Bright 0 ACF 31/32 ON Bright BOP Verify Emergency DC Oil Pump Status
- Main Turbine Emergency Bearing Oil Pump Running (Panel SEF) i
- Dispatch NPO to verify Main Gen Air Side Seal Oil Pump Running i
BOP Reset Safety Injection
- Press both SI Reset buttons (Panel SBF-2)
- If RCS pressure is < 360 psig place Makeup Control Switch to stop
- Dispatch NPO to align and reset MCC per SOP-EL-15 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 21 of33
Appendix 0 Scenario Outline Form ES-O-1
- Op-Test No.: Scenario No.: ..l.. Event No.: 5 & 6 Event
Description:
BOP Operator Actions - Automatic Action Verification Time Position Examinee's Actions or Behavior BOP Check if additional actions should be performed
- If transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 Do not perform additional steps
I 0 When transition out of E-O then continue U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 22 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: L i
. Event
Description:
Small Break LOCA
. Time
~.
I Position Examinee's Actions or Behavior i I CRS Enter E-1 ATC Check if RCPs should be stopped
- At least 1 HHSI Pump running (Panel SBF-2)
- Subcooling < value in table (QSPDS Monitor on desk)
Sto~ All RCPs ATC Determine if SGs are Faulted
- Any SG Pressure decreasing in uncontrolled manner (Panel FBF)
- Any SG Completely depressurized (Panel FBF)
Determines NO SG Faulted ATC/BOP Check Intact SG Levels
- Check Level Response in all SGs Normal (Panel FBF)
- Control Feed Flow to maintain 9 [141- 50%
It is possible that the crew ma)' diagnose the SGTR at this point and may transition to E-3 ATC/BOP Reset SI
- Check RO-1 Steps 2 - 1~~ complete (report from BOP)
- Press both SI Reset Push buttons (Panel SBF-2)
ATC/BOP Reset Phase A and B
- Place switches for 200 A, B, C in Close (Panel SFF)
- Depress Phase A Reset pushbuttons (Panel SNF)
- Depress Phase B Reset push buttons If Actuated ..(Panel SNF)
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 3 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 23 of33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.:
Event
Description:
Small Break LOCA Time Position Examinee's Actions or Behavior CRS Check Secondary Radiation ATC/BOP
- Check Seismic Event NOT occurred (Alarm on SDF Clear)
- Direct Watch Chemist to Sample SGs
- Direct Watch HP to perform contact surveys steam lines & blowdown lines
- Reset SG Sample ValvE~s 0 Place Blowdown Switches to Close 0 Press SG Blowdown & Sample Valves Reset Push buttons 17 - 24 on Panel SMF
- Check secondary radiation 0 R-15 (Radiation Monitor Control Cabinet 0 R-19 (Radiation Monitor Control Cabinet 0 R-62 A-D (Rack D3 Behind Flight Panel)
- Check level in isolated SGs Stable (Panel FBF)
It is expected that the crew diagnose the SGTR at this pOint and may transition to E-3. "the crew continues in E-1, they will be required to transition to E-3 on foldout page criteria.
ATC Check PRZR PORVs and Block Valve
- Check Power Available to Block Valves 0 Check Breakers for MCC-36A1B closed (Panel SBF-2) 0 Check Block Valves both energized (Panel FBF)
- Check PORVs Closed (Panel FCF)
- Open one Block Valves_Wanel FCF)
BOP/ATC Establish Instrument Air to Containment
- Check Inst. Air Low Press Alarm Clear (Panel SJF)
- Press Inst. Air Reset Pushbutton 28 (Panel SMF)
- Open IA-PCV-1228 (Panel SNF)
I 0 IA-PCV-1228 will NOT OPEN U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 24 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.:L Event
Description:
Small Break LOCA Time Position Examinee's Actions or Behavior ATC/BOP Check RCP Seal Cooling
- Seal Injection Established (Panel SAF)
- Bearing Coolant Low Flow Alarm Clear (Panel SGF)
ATC/BOP Check CCW for Charging Pump Available
- Check Pumps operating (Panels SBF-1 or SGF)
ATC Determine jf Charging Flow Has Been Established
- Check LCV-112B and LCV-112C both energized and one open (Panel SFF)
- Check CH-AOV-204B Open (Panel SFF)
- Check HCV-142 Fully Open (Panel SF F)
- Check/Start a Charging Pump (Panel FBF)
CRS ATC Check if SI should be terminated BOP
- Subcooling > 40°F [Table for Adverse] (QSPDS Monitor on Desk)
- Secondary Heat Sink o Total Feed Flow> 365 gpm Available (Panels SCF) o SG Level> 9% [14%] (Panel FBF)
- RCS Pressure o > 1700 psig [2000] (Panel FDF) o Stable or Increasing
- Pressurizer Level> 14% [32%] (Panel FBF) 51 Termination Criteria will NOT be met U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 25 of33
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.:
Event Steam Generator Tube R re with Small Break LOCA Time Examinee's Actions or Behavior
, Check if RCPs should be stopped
- At least 1 HHSI Pump running (Panel SBF-2)
- Unexpected Levellncre,ase 32 SG (Panels FBF or SCF)
- High radiation from any SG Sample (Chemistry Report)
- High radiation from any Steam Line (Rad Monitor Control Cabinet, QSPDS, D-Racks behind ht Panel ATC Isolate Flow From Ruptured 32 SG
- Adjust Atmospheric to 1040 and check closed (Panel FBF)
- 32 is affected - direct NPO to isolate steam to 32 AFW Pump o Trip 32 AFW pump if at least 1 MDAFW pump running (Panel SCF) o SG-33 Close MS-42 o Restart 32 AFW Pump if necessary (Panel SCF)
- Verify Blowdown Isolated (Panel SCF)
- Dispatch NPO to isolatet Upstream steam traps per Operator Aid
Check Rupture SG Level> 9% [14%]
- Stop Feed Flow to ruptured SG (Panel SCF)
This action ATC/BOP Check Ruptured SG pressure> 400 psig (Panel FBF)
- Transition to ECA-3.1 if < 400 psig
. This is NOT U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 26 of33
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: -.L Event No.:
Event
Description:
Steam Generator Tube Rupture with Small Break LOCA Time Position Examinee's Actions or Behavior CRS/ATC Determine Target Temperature for Cooldown
- Determine Pressure of Huptured SG (Panel FBF)
- Using Table Determine Target Temperature j ATC Dump Steam to condenser from intact SGs do not exceed 0.4 E6 Ibm/hr per intact SG.
Procedure actions continue until coo/down termination criteria are met.
i ATC Stop cooldown when CET temp (QSPDS) is less than target temp.
- Close Steam Dumps/Atmospherics (Panel FCF/FBF) 0 Null deviation meter on controller to match Auto setpoint with actual current pressure.
0 Close valves in manual i
0 Place controller in automatic ATC Maintain CET temp < target temp
- Monitor CET Temperature and adjust controller setpoint to control < target temp ATC/BOP Check Intact SG Levels
- Level response Normal (Panel FBF and/or SCF)
- Control feed flow to maintain level 13% [19%] to 50% (Panel SCF)
ATC Check PORVs and Block Valves
- Check power available to block valves (lights lit) (Panel FCF)
- Check PORV Closed 0 Light indicating PORVs closed (P':lnel FCF) 0 Tailpipe Temperatures consistent with plant conditions (Panel FBF) 0 Accoustic Monitors No lights lit. (Above door into Supervisory Panel)
- Check Block Valves Open 0 Both Block Valves are CLOSED to isolate leaking PORVs.
i i 0 The Block Valves should be left shut U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 27 of33
Appendix D Scenario Outline Form ES-D-1 II Op-Test No.: _1_ Scenario No.: --L Event No.: L-Event
Description:
Steam Generatqr Tube Ru~ture with Small Break LOCA Time I Position Examinee's Actions or Behavior ATC/BOP Reset SI
- Check RO-1 Steps 2 - 12 complete (report from BOP)
- Press both SI Reset Push buttons (Panel SBF-2)
ATC/BOP Reset Phase A and B
- Place switches for 200 A, B, C in Close (Panel SF F)
- Depress Phase A Reset pushbuttons (Panel SNF)
- pe~ress Phase B Reset ~ushbuttons {panel SNF)
BOP/ATC Establish Instrument Air to Containment
- Check Inst. Air Low Press Alarm Clear (Panel SJF)
- Press Inst. Air Reset Pushbutton 28 (Panel SMF)
- Open IA-PCV-1228 (Panel SNF) 0 IA-PCV-1228 will NOT OPEN BOP ! Determine if RHR Pumps should be stopped
- Check RCS Pressure> 360 psig [700] (Panel FDF or SFF)
I
- Sto~ RHR Pum~s and ~Iace in Auto (Panel SGF)
ATC/BOP Check RCP Seal Cooling
- Seal Injection Established (Panel SAF)
- Bearing Coolant Low Flow Alarm Clear (Panel SGF)
Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF)
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 28 of33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: EventNo*:L Event
Description:
Steam Generator Tube Rupture with Small Break LOCA Time Position Examinee's Actions or Behavior ATC Establish Charging Flow
- Check CCW for Charging Pump Available 0 Check Pumps operating (Panels SBF-1 or SGF)
- Check HCV-142 Fully Open (Panel SFF)
- Check CH-AOV-204B Open (Panel SFF)
- Open LCV-112B then close LCV-112C (Panel SFF)
- Check/Start a Charging Pump and adjust to maximum (Panel FBF)
Expect a charging pump is already running at this point.
Actions to terminate coo/down repeated be/ow. If crew get to this step before CE~
they should wait here. When CET Temps, target temp then they should continue ATC Check if cooldown should be stopped -- CET temp (QSPDS) is less than target temp.
- Close Steam Dumps/Atmospherics (Panel FCF/FBF) 0 Null deviation meter on controller to match Auto setpoint with actual current pressure.
0 Close valves in manual 0 Place controller in automatic to maintain temp ATC Check Ru~tured SG Pressure Stable or Increasin~1 (Panel FBF)
ATB/BOP Check subcooling based on CETs > 60°F [see table for adverse values]
Depending on value for subco,oling, the crew should transition to ECA-3.1 at this point ATC Depressurize RCS using PRZR Spray flow
- Open one PORV
- Check Pressure Decreasing (Panel FBF)
U3 NRC Scenario 3 Power increase from 35%,LT -460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LoeA.
Page 29 of33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: ~ Event No.: L Event
Description:
Steam Generator Tube Rupture with Small Break LOCA Time Position Examinee's Actions or Behavior ATC Terminate Depressurization whe:n:
- Both oRCS Pressure < Ruptured SG Pressure (Panel FBF) o PRZR level> 14% [50] (Panel FBF)
- PRZR Level> 73% [58] (Panel FBF)
- Subcooling < 40° [See Table for Adverse] (QSPDS)
ATC Stop Depressurization
- Close PORV (Panel FCF)
ATC Check RCS Pressure Increasing (Panel FBF)
CRS ATC Check if SI should be terminated BOP
- Subcooling > 40°F [Table for Adverse] (QSPDS Monitor on Desk)
- Secondary Heat Sink o Total Feed Flow> 365 gpm Available (Panels SCF) o SG Level> 9% [14%] (Panel FBF)
- RCS Pressure o Stable or Increasing
- Pressurizer Level> 14% [32%] (Panel FBF)
If not accomplished prior to this step, the crew should transition to ECA*3.1 at this time.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4128 failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 30 of33
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.:
Event
Description:
Time Position Examinee's Actions or Behavior CRS Enter ECA-3.1 ATCIBOP Reset SI
- Check RO-1 Steps 2 - 12 complete (report from BOP)
- Press both SI Reset Push buttons (Panel SBF-2)
- Check SI Reset i
0 SI Actuated Light Extinguished (Panel SBF-2)
BOP Reset Phase A and B
- Place switches for 200 A, B, C in Close (Panel SF F)
- Depress Phase A Reset pushbuttons (Panel SNF)
- Depress Phase B Reset push buttons If Actuated (Panel SNF}
BOP Establish Instrument Air to Containment
- Check Inst. Air Low Press Alarm Clear (Panel SJF)
- Press Inst. Air Reset Pushbutton 28 (Panel SMF)
I
- Open IA-PCV-1228 (Panel SNF) 0 IA-PCV-1228 will NOT OPEN .. - -.. i BOP Check Status of 480V buses All energized byu off site power Ensure MCC and lighting are reset per SOP-EL-15 I!
CRS/ATC I Align PRZR Heater Switches
- Control Group Trip Pull Out I
- Backup Groups OFF I I
CRSATC . Check if Spray Pumps should be stopped BOP Containment spray wj3s never activated
- CRS/ATC Check 32 SG Level > 9% i
- Stop Feed Flow to 32 SG
~
i I CRS/BOP I Determine if RHR Pumps should be stopped RHR Pumps were previously st()eeed U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 31 of33
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.:
Event Ilo,et"'r'l"Itlrln' Time Examinee's Actions or Behavior CRS/BOP Evaluate Plant Status usi Attachment 1 CRS/ATC Check Seal Cooling Established Seal Coo established CRS/ATC Establish Charging Flow
- Charging Flow Previously Established using one pump
- Start all available charging pumps
- Establish Maximum Flow CRS/ATC Determine SGs are NOT Faulted CRS/ATC Check Intact SG Level NORMAL CRS/ATC Initiate RCS Cooldown to Cold Shutdown
- Verify All control rods < 20 steps
- Maintain Cooldown Rate < 1000 Ihour CRS/ATC Determine if Subcooled Recovery is appropriate
- RWST Level> 24 Feet
- 32 SG NR levels < 95°/c, d Examiner Terminate Scenario U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 32 of33
Appendix 0 Scenario, Outline Form ES-D-1 Post Scenario Event Classification Event Classification - ALERT EAL 3.1.2 Primary system leakage exceeding the capacity (>75 gpm) of a single charging pump.
U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.
Page 33 of33
Appendix 0 Scenario Outline Form ES-D-1 Facility: IPEG Unit 3 Scenario No . 4 Op*Test No.: 1 Examiners: Operators:
Initial Conditions: 100% power steady state. 32 HHSI pump is OOS, expected to return to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Turnover: Maintain 100% Power Event Malf. Event Event No. No. Type* Description 1 MAL* I (CRS) PT-404 failure requiring manual control of Main Boiler Feed Pumps.
MSS003 I(ATC) 2 MAL- C (ALL) Fault on 480V Bus 6A. This will require starting an ESW pump and EPS005 charging pump.
D TS (CRS) 3 N/A R (ATe) T.S. load reduction.
N (CRS)
N (BOP) 4 MAL- C(ALL) Rod K-14 fails to move during power reduction CRF004 AU TS (CRS) 5 MAL- i M (ALL) SBLOCA RCSOO1 A
6 MAL C (ALL) ATWS RPSOO2 AlB 7 MAL C (BOP No Auto SI SIS001A C (CRS)
, IB , .
II * {N)ormal, !Rleactivit~, {Qnstrument, {C)omponent, (M)ajor U3 NRC Scenario 4. PT-404 Failure High ~ Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page I of35
Appendix 0 Scenario Outline Form ES-D-1 Summary The evaluation begins with the plant at 100% power steady state operation. 32 SI pump is out of service for bearing inspection. 32 SI Pump was removed from service 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago, expected return in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
After the crew assumes the watch, PT-404 Steam Header Pressure fails high. ATC diagnoses failure and places Main Boiler Feed Pump speed control to manual. CRS directs crew to perform AOP-INST-1, Instrument/Controller Failures.
Next, a fault occurs on Bus 6A. Team enters AOP-480V-1, Loss of 480 V Bus to stabilize the plant. The crew will start a charging pump, ESW Pump and determine that a shutdown must commence. This is a Tech Spec for the CRS.
During shutdown Control Bank D rod K-14 fails to move. The crew will respond using AOP-ROD-1.
Reactor Engineering will direct the crew to continue with the shutdown allowing rods to step in. This is a Tech Spec for the CRS.
After sufficient shutdown, a SBLOCA occurs. Auto reactor trip is demanded but the Reactor trip breakers do not open. The reactor will not trip from the Control Room and the team will respond per FR-S.1, "Response to Nuclear Power Generation I ATWS" and will SID the reactor by manually inserting control rods and initiating Emergency Boration via an alternate method since MOV-333 cannot be opened from the Control Room. The turbine will be manually tripped. The reactor trip breakers will be locally opened and the team will transition to E-O, "Reactor Trip or Safety Injection".
An Auto SI is required, but will not actuate. The RO will manually actuate SI. 33 SI pump cannot be powered. 32 SI pump is OOS. 31 SI pump initially starts but trips. 31 and 32 Charging Pumps are eventually started after manual action to align suction to the RWST. The team will diagnose RCS not intact and transition to EOP E-1, Loss of Reactor or Secondary Coolant.
As the team progresses through E-1, Reactor Vessel level will continue to lower. When level lowers to 44% RCP running range (after about 30 minutes following the ATWS), an orange path on core cooling will require a transition to FR-C.2, Response to Degraded Core Cooling.
The team will initiate depressurization of SGs per FR-C.2. The scenario is terminated after SG depressurization has Deen initiated.
Procedure Flowpath: AOP-INST-1, AOP-480V-1, AOP-ROD-1, FR-S.1, EOP E-o, EOP E-1, FR-C.2 Critical Tasks are as follows:
FR-S.1 - C Insert negative reactivity into the core by at least one of the following methods before step 4 of FR-S.1 is complete:
o De-energize the Rod Drive MG Sets o Manually insert the rods o Establish Emergency Baration FR-S.1 -- B Start AFW pumps and establish 686 gpm before transition out of FR-S.1 E-o -- D Manually actuate at least one train of SIS actuated safeguards before completion of FR S.1 step 6 FR-C.2 -A Depressurize SGs to atmospheric pressure (at < 100°Flhr) to inject ECCS accumulators and establish low-head injection flow before a Core Cooling red path develops.
U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 2 of35
Appendix D Scenario Outline Form ES-D-1 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS IEXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Reset Simulator to IC-11 SES Setup Insert override SWI-SIS002G to PULL OUT POS Sf PUMP #32 CONT SW Schedule On Insert malfunction MAL-SIS004A SAFETY INJECTION PUMP 31 FAILURES to TRIP Insert malfunction MAL- REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002A to ALL_FAIL FAILURE)
Insert malfunction MAL- REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002B & MANUAL)
Insert malfunction MAL-SIS001A SAFETY INJECTION FAILURE TRAIN A Insert malfunction MAL-SISOO'I B SAFETY INJECTION FAILURE TRAIN B Insert malfunction MAL-MSS003 STEAM HEADER PRESSURE DETECTOR PT-404 to 1200.00000 in 40 on event 1 FAILURE nsert malfunction MAL- LOSS OF 480 V BUS 6A EPS005D on event 2 Insert malfunction MAL- Res RUPTURE (LOOP I COLD LEG)
RCS001A to 0.50000 on event 5 Insert malfunction MAL- STUCK ROD (CBD-KI4)
CRF004AU to UNTRIPPABLE Local Reactor Trip Removes Malfunctions:
Delete malfunction MAL- REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002A to ALL FAIL FAILURE)
Delete malfunction MAL- REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002B & MANUAL)
Insert remote LOA*CVC034 to 288 RWST TO CHARGING PUMP HEADER ISO 1.00000 Insert remote LOA-SIS014 to NONE LOA TO DEENERGIZE VALVE 894A ENERGIZE in 360 Insert remote LOA-SIS015 to NONE LOA TO DEENERGIZE VALVE 894B ENERGIZE in 360 Insert remote LOA*SIS016 to NONE LOA TO DEENERGIZE VALVE 894C ENERGIZE in 360 Insert remote LOA-SIS017 to NONE LOA TO DEENERGIZE VALVE 894D ENERGIZE in 360 Set RCCH822B=1 in 600 Locally open 822B SES Setup Load Schedule and verify
! Schedule malfunctions and overrides bave been entered Floor Setup Perform Setup Checklist Hang Danger Tags on 32 HHSI Pump Update Protected Equipment Hang Protected Equipment Tags for 31 and 33 I
PC HHSI Pumps Risk is ?????
Event 1 Activate Trigger 1 when MAL-MSS003 PT-404 failure directed ~
U3 NRC Scenario 4. PT*404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 3 of35
Appendix 0 Scenario Outline Form ES-D-1 Role Play Respond as requested NPO may be directed to investigate PT-404 and MBFP I&C will prepare a Troubleshoot and Repair Package Event 2 Activate Trigger 2 when
- MAL-EPS005D Fault on bus 6A directed Role Play Respond as requested
- Report acrid smell in 480V switchgear room when asked to investigate Event 3 No action TS 3.0.3 shutdown
- Role Play
- Respond as requested
- If necessary SM direct initiate shutdown
- immediately i Event 4 Inserted at setup MAL-CRF004AU Rod K-14 stuck Role Play
- Respond as requested I&C will prepare a Trouble Shoot and Repair Package Event 5 I Activate Trigger 5 when I MAL-RCS001A RCS Leak
- directed Role Play Respond as requested i I Event 6 Inserted at setup I MAL-RPS002A (Trip breakers fail to auto open)
MAL-RPS002B (Trip Breakers fail to man open)
ATWS Role Play I When NPO directed to locally After emergency boration initiated, REMOVE trip reactor MAL-RPS002A and MAL-RPS002B Event 7 ! Inserted at Setup MAL-SIS001A Auto Failure Train A Sl I MAL-SIS001 B Auto Failure Train B SI I Role Play il Respond as requested U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 4 of35
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: _1_
Event
Description:
PT-404 Failure High -Manual con1trol of Main Boiler Feed Pumps Time Position Examinee's Actions or Behavior ATC/BOP Diagnose Failure of PT-404 ATC Place both MBFPs in Manual and stabilize plant.
CRS Direct Perform Immediate Operator Actions of AOP-INST-1 ATC Silently evaluates for failure of control system inputs
- Rod Control o NIS Power Range oRCS Temp o Turbine 151 Sta~Je Pressure
- Pressurizer Pressure
- Pressurizer Level Control oRCS Temperature
- SG Pressure Control o Atmospheric Steam Dumps o High Pressure Steam Dumps CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbaliz.ing each input CRS/ATC Determine an Instrument failure has occurred.
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR.-C.2 Page 5 of35
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: _1_
Event
Description:
PT-404 Failure High - Manual control of Main Boiler Feed Pum~s Time Position Examinee's Actions or Behavior CRS Identify appropriate section 4.17 of procedure
- CRS/ATC Determine Steam Dumps are in Temperature Mode - No action required. (Panel FBF)
ATC Determines Main Boiler Feed Pumps are in Manual (Panel FAF) This should have been done as part of the Immediate Operator Actions ATC Adjust MBFP Speed to Match Steam Flow and Feed Flow.
When stable, adjust Feed Reg Valve AP Program ~er Attachm~nt 13 gra~h I CRS/ATC Return controls for unaffected equipment to auto as desired. The FRVs may have been placed in manual, they can be returned to auto here.
I
~
Lead Evaluator Instruct Booth to insert Trigger 2 I!
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 6 of35
Appendix 0 Scenario Outline Form ES-D-1 S",c"QiIU Event
Description:
Loss of 480V Bus 6A Time Position Examinee's Actions or Behavior CRS/BOP Multiple alarms - Diagnose Loss of Bus 6A CRS Enter AOP-480V-1 CRS/BOP Determine power is lost to Bus 6A and RHR was not in service CRS/ATC Determine no Charging Pump is running
- Start 31 or 32 Charging Pump and match speed with previous conditions CRS/BOP Determine 2 CCW Pumps are running CRS/BOP Determine Essential Service Water Header Pressure is < 60 psig and no SW pumps are operating on the Essential SW Header
- Start 34 or 35 SW Pump CRS/ATC Determine Turbine is on line CRS/ATC Determine Power has not been lost to IRPI CRS/ATC Determine Vacuum NOT decreasing BOP CRS/BOP Determine ISO PHASE BUS RETURN AIR HIGH TEMP alarm is clear CRS/BOP Determine waste release is NOT in progress BOP Dispatch operator to monitor EDGs CRS/ATC Determine IRPI is operable CRS Initiate Review of Tech Specs
- TS 3.8.9 E -Inoperable train with loss of safety function
- TS 3.5.2 - 2 Inoperable HHSI Pumps (Loss of safety function)
U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 7 of3S
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.:
Event
Description:
Loss of 480V Bus 6A . .
Time I Position Examinee's Actions or Behavior I CRS Determine that 2 SIS pumps are inoperable necessitating a shutdown per T.S.
! 3.8.9 E
. CRS/BOP Determine bus 6A NOT energized by EDG CRS/BOP Determine 32 EDG is running !
! BOPINPO Determine white supervisory light for relay 86/6A is extinguished BOP/NPO Dispatch an operator to:
- OPEN Breakers for 0 MCC-36B 0 MCC-36D 0 MCC-37
- Perform visual inspection of 480V bus 6A
! The NPO will report NO FIRE; however an acrid smell exists in the 480 V switchgear room and bus 6A is damaged.
CRS/BOP Place Control Switches/breakers for 480V loads in pullouUoff/open 0 33 Charging Pump 0 PRZR Modulating Heaters 0 32 Boric Acid Transfer Pump 0 32 Containment Spray l:Jump 0 32 Recirc Pump 0 MCC36B 0 33 SI Pump 0 35 FCU 0 33 ABFP 0 Turb Aux Oil Pump 0 32 RHR Pump 0 33 SW Pump 0 36 SW Pmp I 0 39 SW Pump U3 NRC Scenano 4. PT-404 Failure HIgh Manual control MFW Pumps; Fault on Bus 6A; TS requIred shutdown; During Shutdown I Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip sllccessful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 8 of35
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: .L
- Event
Description:
Loss of 480V Bus 6A Time I Position Examinee's Actions or Behavior I
CRS Determine indication of Fault on Bus 6A i i
BOP Direct operator to shutdown 32 EDG I
U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 9 of35
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: ~
Event
Description:
Power Reduction Time Position I Applicant's Actions or Behavior Note:
The reactivity plan for the power reduction should be developed by the team in the briefing room prior to takin ;J the watch. The plan could call for boration and/or rod insertion I CRS
. ....."'P-2.1 and SM ~ermission for Qower reduction CRS Use Attachment 3 from POP-2.1 for power reduction CRS Record power reduction data and contact the SM to make required notifications CRS Direct ATC/BOP to perform a Reactivity Calculation for the power reduction ATC/BO ..... i'i<;;fJare Reactivity Calculation using the Daily Reactivity Sheet, OP CRS Assigns roles for power reduction ATC Reviews reactivity plan ATC If rods are inserted:
- Places/verifies rods are in Manual
- Inserts rods specified number of steps
- Observes:
0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod insertion ATC Diagnose Rod K-14 Not inserting with the remainder of Control Bank D NOTE: If the crewe/ec:ts to use boration first, there will be some time before rod motion is rE!Cluired.
CRS Suspend Power Reduction Enter AOP-ROD-1 U3 NRC Scenario 4. PT*404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 10 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: ~ Event No.:
Event
Description:
Power Reduction Position Applicant's Actions or Behavior ATC If boration is performed:
- Energize All Pressurizer Heaters
- Places RCS Makeup control to Stop
- Place RCS Makeup Mode selector to borate
- Adjusts integrator to desired boration amount
- Places RCS Makeup control to Start
- Observes:
0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration ATC/BOP Initiate Turbine Load Reduction at desired rate
- Governor (Preferred)
- Load Limit 1
ATC Adjust Control Rod Position per TS and Graph-RPC-16 Lead Evaluator When the following has been demonstrated/observed:
- Sufficient load reduction.
- Sufficient normal plant operations by the BOP.
Then instruct Booth to insert Event.
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss ofal! Sf Pumps results in FR-C.2 Page II of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:....1... Event No.:
Event
Description:
Power Reduction/Stuck Rod K-14 Time I Position Examinee's Actions or Behavior I .
i CRS I Enter AOP-ROD-1 I CRS/ATC
- Determine procedure was NOT entered due to continuous rod motion
- CRS Determine procedure section 4.42 for misaligned rod CRS/ATC Determine rod is misaligned I
A TC If not already accomplished for power reduction, place rod control in Manual
- CRS If At Any Time step for power reduction a Adjust boron concentration and turbine load eRS Refer to Tech Specs a TS 3.1.4 Group Alignment Limits a TS 3.2.3 Axial Flux Difference o TS 3.2.4 Quadrant Power Tilt Depending on how quickly the crew diagnoses the stuck rod, actual Tech Spec limits may not be exceeded. The OPERABILITY of rod K-14 is in Ir-____-+_________ ~~qlu~es~t~io~~.~.--------------------------------------------------~i BOP Notify I&C to investigate rod control system for the cause of misaligned/stuck rod.
i
- r--___ .~~______--I--'R'-'-eport as I&C there is NO obvious cause for the misaligned rod.
Lead Evaluator When sufficient load reduction and progress throL1gh AOP-ROD-1 direct booth to activate event 5 U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 12 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: ~ Event No.: l Event
Description:
SBLOCA I Time Position Examinee's Actions or Behavior i
ATC Diagnose ra~idl~ decreasing Pressurize Pressure and Level.
CRS Direct ACT to trip the reactor ancl when verified tripped, Ii Direct the BOP to initiate Safe~ Injection ATC Verifies Reactor NOT Tripped: (Panel FCF)
- Reactor trip and bypass breakers NOT open
- Rod bottom lights NOT lit
- IRPls NOT < 20 steps I * . Nuclear flux NOT decreaslDg BOP
- Attem~t to Tril2 the reactor using the l2ushbutton on Panel SBF-2 i BOP I Direct NPO to locally tril2 the reactor in the cable spreading room i
i CRS/ATC Determine power is > 5% and transition to FR-S.1 U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 13 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.:..ft...
Event Descri ATWSI FR-S.1 Time Position Examinee's Actions or Behavior CRS Enter FR-S.1- Direct crew to ",c,,'rr'lrlrTl Immediate l"'t:>,r<>t."r Actions of FR-S. 1 CRS/ATC Determine reactor NOT tripped ATC
- May take manual control and insert rods
- let automatic control insert control rods.
ATC Determine Turbine NOT Tripped
- Manually trip Turbine BOP Check Auxiliary Feedwater Pumps Running NONE running
- Start 31 AFW Pump
- Start 32 AFW Pump o Increase speed and open throttle valves to feed 33 & 34 SG U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown J Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 14 of35
Appendix 0 Scenario Outline Op-Test No.: _1_ Scenario No.: ~ Event No.: ~
Event Descri on: ATWSI FR-S.1 Time Position Examinee's Actions or Behavior ATC Initiate Emergency Boration
- Check 31/32 charging pump running
- Determine MOV-333 cannot be opened.
o Place FCV-110A in Manual o Ensure FCV-110A Fully Open (Controller output = 0) o Place 111A in Manual o Ensure 111A is Fully Closed (Controller output =0) o Place Makeup Mode Selector Switch in MANUAL o Turn Makeup Control Switch to START o Transfer Charging Pump to Manual o Increase Charging Pump Speed to maximum o Close Boric Acid Storage Tank Recire Valves BOP Verify Containment Ventilation Isolation
- Purge Valves CLOSED o FCV-1170 - 1173 (Panel SLF)
- Pressure Relief Valves CLOSED o PCV-1190 - 1192 (Panel SLF)
- Check WCCPP Low PrE!SSUre Zone Alarms NOT Lit.
- Determine SI Not Actuated o Manually actuate SI o Perform E-O 35 - 42 in with this ure U3 NRC Scenario 4. PT-404 Failure High - Manual control. MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 15 of35
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: ~
ATC Check Reactor Subcritical
- Power Range < 5%
- Intermediate Range Channels 0 or negative
- Check all rods < 20 steps Manual actuation of SI in previous step will strip the Rod Drive MG sets r .."'U'TI,nn in a reactor Booth Instructor Remove malfunctions for Reactor Trip Breakers and ensure reactor trip occurs.
Remove MAL-RPS002A & MAL-RPS002B CRS/ATC Secure Emergency Boration BOP
- Turn Makeup Control Swi:tch to STOP
- Establish Auto Makeup per SOP-CVCS-003
- Place Boric Acid Transfer Pumps in Slow Speed
- BAST Recirc control to 25%
CRS/ATC Check RCP Seal Coo Ii Established CRS/BOP Check Charging Status
- Check CCW available for Charging pump
- Check Charging Pump Running
- Maintain seal 'ection 6 - 12 CRS/ATC Verify Adequate Shutdown Margin BOP
- Verify Control Rods < 20 Steps
- Direct Chemist to Sample RCS
- Check Boron> Cold Shutdown Concentration o Establish normal boration CRS U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 16 of35
Appendix 0 Scenario Outline Form ES~D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: l Event Descri~tion: SBLOCA ~-
Time I Position ,I Examinee's Actions or Behavior CRS i Return to E-O Ste~ 1 ATC Verifies Reactor Tripped: (Panel FCF)
- Reactor trip and bypass breakers open
- Rod bottom lights lit
- IRPls < 20 steps
_.
- Nuclear flux decreasing .--.---.-- I I
ATC Verifies Turbine Trie b~ observing stoe valves closed {Panel FAF}
BOP Check status of 480V buses (Panel SHF)
Observe ALL busses energized from Offsite Power I
I ATC Check SI status Determine SI is Actuated
- Any SI Annunciator - Lit {panel FDF)
- SI Pum~Any Running (Panel SBF-1, SBF-2) .~
ATCIBOP Manually Actuates SI
._~~esses SI Actuation pushbutton {panel SBF}
BOP/ATC Check AFW Status Observes Total of all SG flow indicators> 365 gpm (Panel SCF)
Controls feed flow to maintain SG levels 9 - 50%
- t. Adjust flow control valve potentiometers. .
! CRS i Direct BOP to ~erform RO-1 BOI? Operator Actions during use of EOPs ATC Verify Feedwater Isolation
- Check Main Boiler Feed Pumps Tripped (Panel FAF)
- Check MBFP Discharge Valves Closed (Panel FAF)
- Check Feed Reg Valves and Bypasses Closedllsolated 0 Main and Bypass MOVs Closed (Panel SCF) 0 Main FRVs 2 is True (Panel SNF) 0 Bypass FRVs (Panel FAFL___.___.
I ATC Check Blowdown Isolation Valves Closed (panel SCF)
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 17 of35
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: l Event
Description:
SBLOCA Time Position Examinee's Actions or Behavior ATC Verify SI Flow
- Check Pressure < 1700 psig (Panel FBF, or FDF)
- Check High Head Pump Flow Indicators (Panel SBF-2)
- Check Pressure < 360 p!;ig (Panel FDF WR Press Recorder)
- Check RHR Pumps Flow Indicators (Panel SBF-2 ATC Verify Containment Spray NOT required
- Check Containment Pressure remained < 22 I2si9 (panel J01 or SBF-2}
- Bearing Coolant Low Flow Alarm Clear (P::mel SGF)
ATC Establish Charging Flow
- Check CCW Available (Panel SBF-1 lights only this is adequate; Panel SGF Breakers & Flow indicators)
- Check HCV 142 Fully Open (Panel SFF)
- Check CH-AOV-204B Open (Panel SFF)
- Open CH-LCV-112B (Panel SFF)
- Then Close CH-LCV-112C (Panels SF F)
- Set Speed Controller to Starting Position (Panel FBF)
- Start 1 Charging Pump (Panel FBF)
- Adiust Speed for Minimum Seal Injection {Panel SAF}
ATC Check RCS Average Temperature I
- Any RCPs Running - Tavg Trending to 547°F (Panel FDF)
- No RCPs running - Tcold Trending to 54rF (Panel FDF)
ATC Check if RCPs should be stopped
- At least 1 HHSI Pump running (Panel SBF-2)
- Subcooling < value in table (QSPDS Monitor on desk)
- Stop All RCPs U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 18 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: ~ Event No.: l Event
Description:
§BLOCA Time Position Examinee's Actions or Behavior ATC Check PORVs Closed (Panel FCF)
Check Safety Valves Closed
- Tailpipe Temperatures Normal (Panel FBF)
- Acoustic Monitors Normal (Above Door into Supervisory Panel)
Spray Valves Closed (Panel FBF)
Check Aux Spray Valve Closed Panel (Panel SFF)
! ATC Determine if SGs are Faulted
- Any SG Pressure decreasing in uncontrolled manner (Panel FBF)
- Any SG Completely depressurized (Panel FBF)
ATC Determine if SG Tubes are Ruptured
- Condenser Air Ejector Radiation recorder Trend (Rad Monitor Rack)
- SG Blowdown Recorder Trend (Rad Monitor Rack)
- Main Steam Line Radiation Recorders (Rack D-3 behind the Flight Panel)
- Any SG level increasing in an uncontrolled manner (Panel FBF)
- Containment Pressure Normal (Panel J-O or SBF-1)
- Containment Sump Level Normal (Panel J-O)
- Containment Radiation Normal o R-2 and R-7(Rack D-1 Behind Flight Panel}
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sf Pumps results in FR-C.2 Page 19 of35
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.:
Event
Description:
BOP Actions during E-O (Procedure RO-1)
.,..,. Position Examinee's Actions or Behavior BOP Monitor Control Room Alarms
- Acknowledge Supervisory Alarms
- Report Unusual Alarms
- Monitor High Containment Temp alarm (SCF)
- Monitor 480 Safeguards Undervoltage alarm (SBF2)
- Three SI Pumps (SBF-2)
- Two RHR Pumps (SBF-1 or SGF)
BOP Verify Containment FCU Status
- Check all FCU running
- Place Damper Control Switches in Incident Mode (Panel SBF-2) o Damper AlB Closed o Damper C Closed o Damper D Open
- Place Control Switches for 1104 and 1105 to Open (Panel SBF-1)
- Safeguards Valve Off Normal alarm CLEAR
- Ensure following OPEN o BIT Discharge 1835A1B (Panel SBF-2) o BIT Inlet 1852A1B (Panel SBF-2) o High Head Stop Valves 856J, H, C, E (Panel SBF-2)
- Check if MSIVS should remain OPEN o High Steam Flow SIIHi-Hi VC Pressure Alarm Clear (FDF)
- IF RWST Purification Loop in service contag!-=-N'-'-P--=O=--=-=to:....:s::..::e=-=c'-=u'-"re'-'-._ _ _ _ _-I BOP Verify Aux Boiler Feed Pump Status
- Check Motor Driven Pumps Both Running
- Check Turbine Pump Running U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 20 of35
Appendix D Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: ~ Event No.: ~
Event
Description:
BOP Actions during E-O (Procedune RO-1)
Time Position Examinee's Actions or Behavior BOP Verify Aux Feed Valve Alignment
- Motor driven AFW Pumps (Panel SCF) o Set 40SA - D to full open (Panel SCF)
- Check SG Blowdown isolation valves CLOSED (Panel SCF)
- All 3 Pumps Running
BOP Check Essential Service Water Pumps - 3 Running BOP Verify Containment Ventilation Phase A & B (Panel SNF)
- Phase A actuated
- Phase B Actuated
- Check Phase A valve CLOSED
- Check Phase B valves CLOSED BOP Verify Containment Ventilation Isolation
- Purge Valves CLOSED o FCV-1170 - 117'3 (Panel SLF)
- Pressure Relief Valves CLOSED o PCV-1190 - 1192 (Panel SLF)
- Check WCCPP Low Pressure Zone Alarms NOT Lit.
!
- Verify IVSWS Valves OPEN o IV-AOV-1410,IV-AOV-1413 o IV-SOV-S200, IV-SOV-S201 BOP Verify Emergency Diesel Generator Status
- Check ALL EDGs RUNNING (Panel SBF-2)
- Check EDG Outlet Flow Control Valves OPEN o FCV-117S/177SA (Panel SBF-2)
U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod wi II fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 21 of35
Appendix 0 Scenario Outline Form ES-O-1 II Op-Test No.: _1_ Scenario No.: --+/-- Event No.: i Event
Description:
BOP Actions during E-O (Procedure RO-1}
Time Position Examinee's Actions or Behavior BOP Verify Control Room Ventilation
- Set Control Room Ventilation Control Switch to 10% incident mode (By Supervisory Panel Entrance)
- Verify AlC Compressors and fans ALL Running 0 ACC 31A1B ON I3right 0 ACC 32 AlB ON Bright 0 ACF 31/32 ON Bright BOP Verify Emergency DC Oil Pump Status
- Main Turbine Emergency Bearing Oil Pump Running (Panel SEF)
- Dispatch NPO to verify Main Gen Air Side Seal Oil Pump Running
BOP Reset Safety Injection
- Press both SI Reset buttons (Panel SBF-2)
- If RCS pressure is < 360 psig place Makeup Control Switch to stop
- Dispatch NPO to align and reset MCC per SOP-EL-15 U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 22 of35
Appendix 0 Scenario IOutline Form ES*D*1 Op-Test No.: _1_ Scenario No.: ~ Event No.:
Event
Description:
BOP Actions during E-O (Procedure RO-1)
Time Position Examinee's Actions or Behavior BOP Check if additional actions should be performed
- If transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 Do not perform additional steps
- If Not transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 When transition out of E-O then continue U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 23 of35
Appendix D Scenario Outline Form ES~D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 5 Continued Event
Description:
Procedure E-1 Time Position Examinee's Actions or Behavior i Approximately 30 minutes after the A TWS event ReS inventory will be low enough to require a transition to FR-C.2 ATC Check if RCPs should be stopped
- At least 1 HHSI Pump running (Panel SBF-2)
- Subcooling < value in table (QSPDS Monitor on desk)
Stop All RCPs ATC Determine if SGs are Faulted
- Any SG Pressure decrealsing in uncontrolled manner (Panel FBF)
- Any SG Completely depressurized (Panel FBF)
Check Faulted SG Isolated (Unless needed for cooldown)
- MSIVs (Panel SBF-1)
- SF Atmospherics (Panel FBF)
- SG Blowdown Isolation (Panel SCF)
ATC/BOP Check Intact SG Levels
- Check Level Response in all SGs Normal (Panel FBF)
- Control Feed Flow to maintain 9 [14] - 50%
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sf Fails; Loss of all SI Pumps results in FR-C.2 Page 24 of35
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 5 Continued Event
Description:
Procedure E-1 ATC/BOP Reset SI
- Check RO-1 Steps 2 - '12 complete (report from BOP)
- Press both SI Reset Pushbuttons (Panel SBF-2)
- Place switches for 200 A. B. C in Close (Panel SF F)
- Depress Phase A Reset pushbuttons (Panel SNF)
- Depress Phase B Reset pushbuttons (Panel SNF)
CRS Check Secondary Radiation ATC/BOP
- Check Seismic Event NOT occurred (Alarm on SDF Clear)
- Direct Watch Chemist to Sample SGs
- Direct Watch HP to perform contact surveys steam lines & blowdown lines
- Reset SG Sample Valves o Place Blowdown Switches to Close o Press SG Blowdown & Sample Valves Reset Push buttons 17 - 24 on Panel SMF
- Check secondary radiation o R-15 (Radiation Monitor Control Cabinet o R-19 (Radiation Monitor Control Cabinet o R-62 A-D (Rack D3 Behind Flight Panel)
- Check level in isolated SGs Stable (Panel FBF)
ATC Check PRZR PORVs and Block Valve
- Check Power Available to Block Valves o Check Breakers for MCC-36NB closed (Panel SBF-2) o Check Block Valves both energized (Panel FBF)
- Check PORVs Closed (Panel FCF)
- Open one Block Valves (Panel FCF)
U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 25 of35
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event
Description:
Procedure E-1 I BOP/ATC Establish Instrument Air to Containment
- Check Inst. Air Low Pre~;s Alarm Clear (Panel SJF)
- Press Inst. Air Reset Pushbutton 28 (Panel SMF)
- Open IA-PCV-1228 (Panel SNF)
ATC/BOP Check RCP Seal Cooling
- Seal Injection Established (Panel SAF)
OR I
i
- Bearing Coolant Low Flow Alarm Clear (Panel SGF)
ATC/BOP Check CCW for Charging Pump Available i
- Check Pumps operating (Panels SBF-1 or SGF)
ATC Determine if Charging Flow Has Been Established
- Check LCV-112B and LCV-112C both energized and one open (Panel SF F)
- Check CH-AOV-204B Open (Panel SF F)
- Check HCV-142 Fully Open (Panel SFF)
- Check/Start a Charging PumQ (Panel FBF)
CRSATC Check if SI should be terminated BOP
- Subcooling > 40°F [Table for Adverse] (QSPDS Monitor on Desk)
- Secondary Heat Sink 0 Total Feed Flow> 365 gpm Available (Panels SCF) 0 SG Level> 9% [14%) (Panel FBF)
- RCS Pressure 0 > 1700 psig [2000] (Panel FDF) 0 Stable or Increasing
!
- Pressurizer Level> 14% [32%1 (Panel FBF)
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sl Pumps results in FR-C.2 Page 26 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 5 Continued Event
Description:
Procedure E-1 CRSATC Check if Spray Pumps should be stopped BOP
- Check Any spray pumpl> running (Panel SBF-1)
- Check if Spray should be secured 0 5 Fan Cooler Units Running (Panel SBF-2)
OR 0 Containment Pressure < 16 psig (Panel SBF-1)
- Depress Containment Spray Reset push buttons (Panel SBF-1)
- Check Containment Radiation Normal 0 R-2 and R-7 (Rack 0-1 Behind Flight Panel)
- Stop Containment Spray Pumps and place in auto (Panel SBF-1)
- Close Pump discharge valves 866 AlB (Panel SBF-1)
BOP Determine if RHR Pumps should be stopped
- Check RCS Pressure> 360 psig (Panel FDF or SFF)
- Check RCS Pressure stable or increasing
I
- Stop RHR Pumps and place in Auto (Panel SGF)
- Check pressures in all SG stable or increasing (Panel FBF) i
- 480V buses energized by offsite power (Panel SHF)
- CRS directs BOP to ~erform Attachment 1 ATC Check if RCS Cooldown and Depressurization is Required i
- Check RCS pressure Greater than 360 (Panel FDF or SFF)
- Check RTHR Pump Flow Less than 300 gpm (Panel SBF-2)
CRS Transition to ES-1.2 Post LOCA Cooldown and Depressurization U3 NRC Scenario 4, PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 27 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: -A.... Event No.: 5 Continued
. Event
Description:
Procedure E-1 ATC/BOP I Determine if Transfer to Cold Leg Recirc is required.
i
- Check RWST Level < 11.5 feet (Panel SBF-1 or SBF-2)
BOP Check at least one recirc flowpath using Recirc Pumps Available
- 31 or 32 Recirc Pump Available (Panel SBF-1)
- Discharge Valves 1802A or B Open (Panel SBF-1)
- 31 RHR Heat Exchanger 0 822A Open/Available 0 638 Open/Available 0 747 Open/Available 0 899B Open/Available 0 888A AND 888B Both Closed 0 745A AND 745B Both Open OR
- 32 RHR Heat Exchanger 0 822B Open/Available 0 640 Open/Available 0 746 Open/Available 0 899A Open/Available 0 888A AND 888B Both Closed
- At least 1 Non Essential Service Water Pump Available
- MCC36A or MCC36B Energized U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 28 of35
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 5 Continued Event
Description:
Procedure E-1 Check at least one recirc flowpath using RHR Pumps Available
- 31 or 32 RHR Pump Available (Panel SBF-1)
- 744 and 882 Available
- 31 RHR Heat Exchangef o 822A Open/Available o 638 Open/Available o 747 Open/Available o 899B Open/Available o 888A AND 888B Both Closed o 745A AND 745B Both Open
- 32 RHR Heat Exchanger o 822B Open/Available o 640 Open/Available o 746 Open/Available o 899A Open/Available o 888A AND 888B Both Closed
- At least 1 Non Essential Service Water Pump Available
- MCC36A or MCC36B Ener ized U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 29 of35
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 5 Continued Event
Description:
Procedure E-1 Check at least one recirc flowpath using High Head SI Pumps Available
- One HHSI Pump Available (Panel SBF-1)
- One Recirc or RHR Pump capable of supplying HHSI Pump 0 1802A or B Available if using Recire 0 885A AND 885B Available If using RHR (Panel SBF-1)
- 31 RHR Heat ExchangE~r 0 822A Open/Available 0 638 Open/Available 0 747 Open/Available 0 899B Open/Available 0 888A AND 8888 Both Closed 0 745A AND 7458 Both Open OR
- 32 RHR Heat ExchangE~r 0 822B Open/AvClilable 0 640 Open/Available 0 746 Open/Available 0 899A Open/Available 0 888A AND 8888 Both Closed
- High Head Valves Available 0 744 AND 882 Available 0 842 OR 843 Available 0 887 A AND 88713 Available 0 851A OR 851 B Available 0 1810 Available 0 743 OR 1870 Available 0 850A AND 850C Available if 31 HHSI Pump to be used 0 1852A OR 18528 Available if 32 or 33 HHSI Pump to be used 0 1835A OR 1835B Available if 32 or 33 HHSI Pump to be used 0 1813 Available U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on 8us 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 30 of35
Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event
Description:
Procedure E-1
- At least 1 Non Essential Service Water Pump Available
- MC936A or MCC36B Energized CRS
- IF unable to verify 1 low-head or 1 High-head Recirculation Flowpath Available, Transition to ECA-1.1
. BOP Determine if PAB Conditions Normal
- R-64, 55 Ft Elev CompOSite PAB
- R-65, 73 Ft Elev CompOSite PAB
- R-66, 34 Ft Elev Composite PAB
- R-67, 41 Ft Elev Composite PAB
- R-68, 15 Ft Elev CompOSite PAB
- R-69, 54 Ft EI Pipe Pen Comp
- PAB & TRENCH AREA HI TEMP alarm on SDF ~anel- NOT LIT CRS/BOP IF PAB Radiation Is NOT Normal
- Try to identify and isolate leakave
- If loss of RCS outside Cc)ntainment is in ~r9gress, Transition to ECA-1.2 CRS/BOP Direct Watch Chemist to sample:
- Containment Atmospere 0 Activity 0 Hydrogen
- Recirc Sump 0 Boron 0 CI 0 02 0 pH U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all Sf Pumps results in FR.*C.2 Page 31 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event
Description:
Procedure E-1 CRS/BOP Determine availability of the following:
- Charging Pumps
- Safety Injection Pumps
- RHR Pumps
- Recirc Pumps
- Auxiliary Feedwater Pumps
- Component Cooling Water Pumps
- Service Water Pumps
- Containment Spray System
- Containment Isolation System
- Hydrogen Recombiner
- Fan Cooler Units
- PAB Exhaust Fans
- Diesel Generators
- Offsite Power
- 480V Safeguards Buses
- 125V Batteries
- Instrument Air System and PORV Nitrogen Backup BOP . Place Hydrogen Monitoring System in service . _ _ _ _ _ _ _- - I BOP/CRS I Notify Emergency Director of any systems/Equipment NOT available.
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 32 of35
Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.:
Event Descri tion: Degraded Core Cooling FR-C.2 Time Position Examinee's Actions or Behavior CRS Transition to FR-C.2 BOP
- Verify SI Valve Alignment Proper
- Attachment 1 Injection phase SI Valve Lin--=e...;cu-"--_ _ _ _ _ _ _ _ _ _-11 BOP/ATC Verify SI Flow in all Trains
- Check High Head Flow Indicated o No Flow Indicated o Establish Maximum Charging with all Available Pljm=p-=..s__ ----11 ATC Check RCS Pressure Less Than 360 psig to check if RHR should be verified .
. Pressure is greater than 360.
- Check Power to PORV Block Valves o Power is NOT available to MOV-535
- Valve was open when bus de-energized
- Expect valve OPEN
- Check PORVs Closed
- Check RVLlS Full Ranqe NOT greater than 33%
BOP Check power to accumulator isolation valves status
- Power available o Discharge NPO to energize valves
- Dischar e valves OPEN U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto Sf Fails; Loss of all SI Pumps results in FR-C.2 Page 33 of35
Appendix D Scenario Outline Form ES-D-1 ATC Check intact SG levels
- Any greater than or equal to 9%
o Increase feed flow to restore narrow range level> 9% in at least one SG
- Control feed flow to maintain level between 9 and 50%
ATC Depressurize All Intact SG to 175 psig
- Maintain cooldown rate in RCS cold legs < 100°F/hr
- Dump steam to condensers o If condensers not available o Manually open SG Atmospherics
- Check SG pressure < 175 and Temp < 390 0 Lead Examiner Terminate scenario when cooldown established.
U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto S( Fails; Loss of all S( Pumps results in FR-C.2 Page 34 of35
Appendix 0 Scenario Outline Form ES-D-1 Post Scenario Event Classification Event Classification - Site Area Emergency EAL 1.1.2 RED path in F-O.1 Subcriticality AND ALL manual attempts at tripping the reactor from the control room have failed to reduce power range < 5%
Also possible:
EAL-1.2.1 ORANGE or RED path in F-O.2 CORE COOLING U3 NRC Scenario 4. PT -404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 35 of35