ML12152A391
| ML12152A391 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/11/2012 |
| From: | NRC Region 4 |
| To: | Luminant Generation Co |
| References | |
| Download: ML12152A391 (112) | |
Text
Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 5 CPNPP NRC 2012 JPM RA1 Rev d.docx Facility: CPNPP JPM # NRC RA1 Task # RO1413 K/A # 2.1.25 3.9 / 4.2
Title:
Determine Loss of RHR Time Limitations Examinee (Print):
Testing Method:
Simulated Performance:
Classroom:
X Actual Performance:
X Simulator:
Alternate Path:
Plant:
Time Critical:
READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.
When you complete the task successfully, the objective for this JPM will be satisfied.
Initial Conditions:
Given the following conditions:
Unit 2 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.
All Pressurizer Safety Valves have been removed.
Reactor Coolant System temperature is 100°F.
The Reactor was shut down 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> ago.
A Loss of Residual Heat Removal cooling has just occurred.
Initiating Cue:
The Unit Supervisor directs you to PERFORM the following:
CALCULATE per ABN-104, Residual Heat Removal System Malfunction,, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:
DETERMINE Time to Saturation.
DETERMINE most limiting Containment Closure Time.
Task Standard:
Utilizing ABN-104, determined Time to Saturation and most limiting Containment Closure Time following a Loss of the Residual Heat Removal System.
Required Materials: ABN-104, Residual Heat Removal System Malfunction, Rev. 8-10.
Validation Time:
15 minutes Completion Time:
________ minutes
Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 5 CPNPP NRC 2012 JPM RA1 Rev d.docx Comments:
Result:
SAT UNSAT Examiner (Print / Sign):
Date:
Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 5 CPNPP NRC 2012 JPM RA1 Rev d.docx CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
ABN-104, Residual Heat Removal Malfunction.
Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory.
Attachment 19, Available Time for Containment Closure.
Appendix C JPM STEPS Form ES-C-1 Page 4 of 5 CPNPP NRC 2012 JPM RA1 Rev d.docx
- Check Mark Denotes Critical Step START TIME:
Examiner Note:
The following steps are from ABN-104, Attachment 5.
Perform Step: 1 Determine Time to Saturation:
Find Time to Saturation from Attachment 5, Page 1.
Standard:
REFERRED to Page 1 of Attachment 5 and PLOTTED the intersection of Time After Shutdown (336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br />) and Initial Temp (100ºF) and DETERMINED: TIME TO SATURATION = 22 +/- 1 minutes.
Comment:
SAT UNSAT Examiner Note:
The following step is from ABN-104, Attachment 19.
Perform Step: 2 Determine most limiting Containment Closure time:
Find Containment Closure Time from Attachment 19:
Radiological Environment Limiting Curve.
Thermal Environment Limiting Curve.
Standard:
REFERRED to Attachment 19 and PLOTTED the intersection of Time After Shutdown (336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br />) and DETERMINED: Radiological Environment Limiting Containment Closure Time is most limiting =
75 +/- 3 minutes.
Terminating Cue:
This JPM is complete.
Comment:
SAT UNSAT STOP TIME:
Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP NRC 2012 JPM RA1 Rev d.docx INITIAL CONDITIONS:
Given the following conditions:
Unit 2 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.
All Pressurizer Safety Valves have been removed.
Reactor Coolant System temperature is 100°F.
The Reactor was shut down 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> ago.
A Loss of Residual Heat Removal cooling has just occurred.
INITIATING CUE:
The Unit Supervisor directs you to PERFORM the following:
CALCULATE per ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:
DETERMINE Time to Saturation. ________
DETERMINE most limiting Containment Closure Time.
CPSES ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 PROCEDURE NO.
ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 58 OF 102 ATTACHMENT 5 PAGE 1 OF 2
[C]
TIME TO SATURATION FOR LOSS OF ALL RHR WITH THE RCS AT REDUCED INVENTORY (assuming no makeup)
CPNPP NRC 2012 JPM RA1 Answer Key Rev d CPNPP NRC 2012 JPM RA1 Answer Key Rev d
CPSES ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 PROCEDURE NO.
ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 99 OF 102 9 ATTACHMENT 19 PAGE 1 OF 1
[C]
AVAILABLE TIME FOR CONTAINMENT CLOSURE CPNPP NRC 2012 JPM RA1 Answer Key Rev d CPNPP NRC 2012 JPM RA1 Answer Key Rev d
Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 5 CPNPP NRC 2012 JPM RA2 Rev d.docx Facility: CPNPP JPM # NRC RA2 Task # RO1804 K/A # 2.1.23 4.3 / 4.4
Title:
Perform a Calorimetric Heat Balance Examinee (Print):
Testing Method:
Simulated Performance:
Classroom:
X Actual Performance:
X Simulator:
Alternate Path:
Plant:
Time Critical:
READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.
When you complete the task successfully, the objective for this JPM will be satisfied.
Initial Conditions:
Given the following conditions:
A Unit 1 Calorimetric is required.
The Plant Computer is unavailable for use.
All Prerequisites have been completed.
OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.
An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.
Initiating Cue:
The Shift Manager directs you to PERFORM the following:
COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.
START at Step 8.2.2.9.
Task Standard:
Utilizing OPT-309, OPT-309-2, and OPT-309-11 calculated a Unit 1 calorimetric.
Required Materials: OPT-309, Unit Calorimetric, Rev 14.
OPT-309-2, Calorimetric Data Reduction Worksheet, Rev 8.
OPT-309-11, Unit 1 Calorimetric Data Sheet, Rev 6.
Validation Time:
20 minutes Completion Time:
________ minutes Comments:
Result:
SAT UNSAT Examiner (Print / Sign):
Date:
Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 5 CPNPP NRC 2012 JPM RA2 Rev d.docx CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
OPT-309, Unit Calorimetric, completed through Step 8.2.2.8.
OPT-309-2, Calorimetric Data Reduction Worksheet, completed through Step 8.2.2.8.
OPT-309-11, Unit 1 Calorimetric Data Sheet with data entered.
Steam Tables.
Calculator.
Appendix C JPM STEPS Form ES-C-1 Page 3 of 5 CPNPP NRC 2012 JPM RA2 Rev d.docx
- Check Mark Denotes Critical Step START TIME:
Examiner Note:
The following steps are from OPT-309, Section 8.2.
Perform Step: 1 8.2.2.9, 8.2.2.9.A, &
8.2.2.9.B Perform Steam Generator Enthalpy Rise Calculation as follows:
Enter corrected steam pressures given in column 5 of Step 8.2.2.5, in column 2.
Using Steam Tables obtain the steam enthalpies AND enter results in column 3.
Standard:
CALCULATED Steam Generator Enthalpy Rise using corrected steam pressures (PSIA) then CALCULATED associated steam enthalpy values using Steam Tables and ENTERED data on OPT-309-2.
Comment:
SAT UNSAT Perform Step: 2 8.2.2.9, 8.2.2.9.C, 8.2.2.9.C 2nd bullet, &
8.2.2.9.D Perform Steam Generator Enthalpy Rise Calculation as follows:
Enter feedwater enthalpy from one of the following sources:
IF Steam Generator Blowdown NOT isolated, THEN enter value given in column 2 of Step 8.2.2.8 into column 3, or Using Steam Tables obtain the enthalpy of the feedwater liquid AND enter result in column 4.
Subtract the value in column 4 from values in column 3 AND enter the results in column 5.
Standard:
CALCULATED Feedwater Enthalpy using Steam Tables then SUBTRACTED value in column 4 from values in column 3 and ENTERED data on OPT-309-2.
Comment:
SAT UNSAT
Appendix C JPM STEPS Form ES-C-1 Page 4 of 5 CPNPP NRC 2012 JPM RA2 Rev d.docx Perform Step: 3 8.2.2.10, 8.2.2.10.A, 8.2.2.10.B, 8.2.2.10.C,
& 8.2.2.10.D Perform Steam Generator Heat Gain Calculation as follows:
Enter the enthalpy rise for each Steam Generator given in column 5 of Step 8.2.2.9, into column 2.
Calculate steam flow for each Steam Generator by using the formula given in the heading of column 3. Use data for Feedwater flow given in column 4 of Step 8.2.2.4 AND blowdown flow given in column 3 of Step 8.2.2.7. Enter results in column 3.
Multiply the entries in column 2 by entries in column 3, AND enter results in column 4.
Total the entries of column 4 and enter result at the base of this column.
Standard:
CALCULATED Steam Generator Heat Gain; RECORDED enthalpy rise for each Steam Generator then RECORDED steam flow for each Steam Generator then MULTIPLIED the entries in column 2 by entries in column 3, and ENTERED results in column 4 then TOTALED the entries and ENTERED data on OPT-309-2.
Comment:
SAT UNSAT Perform Step: 4 8.2.2.11, 8.2.2.11.A, 8.2.2.11.B, 8.2.2.11.C,
& 8.2.2.11.D Perform Percent Rated Thermal Power Calculation as follows:
Enter the Steam Generator Heat Gain given in space at the base of column 4 from Step 8.2.2.10, in column 1.
IF Steam Generator Blowdown NOT isolated, THEN enter the Blowdown Heat Loss given in column 3 of Step 8.2.2.8, in column
- 2.
Calculate Net Reactor Power by using the formula given in the heading of column 4 AND the data given in columns 1, 2 and 3.
Enter results in column 4.
Substitute values from column 4 and column 5 into the formula in the heading of column 6 AND calculate Percent Rated Thermal Power. Enter the result in column 6.
Standard:
CALCULATED Percent Rated Thermal Power using Steam Generator Heat Gain then CALCULATED Net Reactor Power value then SUBSTITUTED values and CALCULATED Percent Rated Thermal Power and ENTERED data on OPT-309-2.
CALCULATED a Percent Rated Thermal Power of 94 +/- 1.0%.
Terminating Cue:
This JPM is complete.
Comment:
SAT UNSAT STOP TIME:
Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP NRC 2012 JPM RA2 Rev d.docx INITIAL CONDITIONS:
Given the following conditions:
A Unit 1 Calorimetric is required.
The Plant Computer is unavailable for use.
All Prerequisites have been completed.
OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.
An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.
INITIATING CUE:
The Shift Manager directs you to PERFORM the following:
COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.
START at Step 8.2.2.9.
OPT-309-2 REV. 8 PAGE 1 OF 3 CALORIMETRIC DATA REDUCTION WORKSHEET Unit Date 8.2.2.2 - Feedwater Average Temperature Parameter Average Value of Data Sets
(°F)
Overall Average
(°F)
S/G 1 Feedwater Temperature S/G 2 Feedwater Temperature S/G 3 Feedwater Temperature S/G 4 Feedwater Temperature 8.2.2.3 Feedwater Average Pressure Parameter Average of Data Sets (PSIG)
Corrected Pressure (PSIG + 14.7 = PSIA)
Overall Average (PSIA)
S/G 1 Feedwater Pressure S/G 2 Feedwater Pressure S/G 3 Feedwater Pressure S/G 4 Feedwater Pressure 8.2.2.4 - Feedwater Flow Averages Parameter (WF)
Average Value of Data Sets (LB/HR)
Correction Factor (CF)
(NOTE 1)
Corrected Value LB/HR x CF (LB/HR)
S/G 1 Feedwater Flow S/G 2 Feedwater Flow S/G 3 Feedwater Flow S/G 4 Feedwater Flow 8.2.2.5 - Corrected Steam Generator Steam Pressure Averages Parameter Average of Data Sets (PSIG)
Corrected Pressure (PSIG+14.7 = PSIA)
Pressure Drop Due to Line Loss (PSIA)
(NOTE 2)
Corrected Pressure (PSIA)
Overall Average (PSIA)
S/G 1 Steam Pressure 5.55 S/G 2 Steam Pressure 5.88 S/G 3 Steam Pressure 7.04 S/G 4 Steam Pressure 6.13 NOTE 1:
Correction Factor is 1 when LEFM data is used. When other Feedwater Flow data is used, Correction Factor is from Attachment 10.1 using Feedwater Temperature for the associated SG calculated in Step 8.2.2.2 (Column 2).
NOTE 2:
The steam line pressure drops are the same for both Units.
CPNPP NRC 2012 JPM RA2 Answer Key Rev d CPNPP NRC 2012 JPM RA2 Answer Key Rev d 1
Today 440 440 440 440 440 1160 1160 1160 1160 1175 1175 1175 1175 1175 3.8xE6 3.8xE6 3.8xE6 3.8xE6 3.8xE6 3.8xE6 3.8xE6 3.8xE6 1.0 1.0 1.0 1.0 979.7 979.4 978.4 979.1 994.4 994.1 993.1 993.8 999.95 999.98 1000.14 999.93 1000
OPT-309-2 REV. 8 PAGE 2 OF 3 CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.6 - Steam Generator Blowdown Average Values Parameter Average Value of Data Sets SG Blowdown Flow (GPM)
SG Blowdown Hx Out Temp (°F) 8.2.2.7 - Blowdown Flow Conversion Average Blowdown Flow, F (GPM)
Specific Volume, V FT3/lbm Blowdown Flow, Fbd (LBM/HR) 8.2.2.8 - Blowdown Heat Loss Calculation Blowdown Enthalpy, (BTU/LBM)
Feedwater Enthalpy, (BTU/LBM)
Blowdown Heat Loss, Qbd (BTU/HR) 8.2.2.9 - S/G Enthalpy Rise Calculation SG No.
Corrected Steam Pressure (PSIA)
Steam
- Enthalpy, (BTU/LBM)
- Enthalpy, (BTU/LBM)
Enthalpy Rise (BTU/LBM) 1 2
3 4
CPNPP NRC 2012 JPM RA2 Answer Key Rev d CPNPP NRC 2012 JPM RA2 Answer Key Rev d 335 250 335 0.0170 161967 542.6 419.9 19873351 1000 1000 1000 1000 419.9 1192.9 1192.9 1192.9 1192.9 773 773 773 773
OPT-309-2 REV. 8 PAGE 3 OF 3 CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.10 - SG Heat Gain Calculation SG No.
Enthalpy Rise, (BTU/LBM)
Steam Flow (LBM/HR)
S/G Heat Gain, (BTU/HR) 1 2
3 4
8.2.2.11 - Percent Rated Thermal Power Calculation SG Heat Gain (BTU/HR)
Blowdown Heat Loss, (BTU/HR)
Non-Reactor Heat Gains, (BTU/HR)
Net Reactor
- Power, (BTU/HR)
Rated Thermal
- Power, (BTU/HR)
Percent Rated Thermal Power
(%)
5.4 X 107 1.2328 x1010 Comments:
Performed By: Date:
Reviewed By: Date:
CPNPP NRC 2012 JPM RA2 Answer Key Rev d CPNPP NRC 2012 JPM RA2 Answer Key Rev d 773 773 773 773 3,759,508 2,906,099,877 1.1624xE10 1.1624xE10 19873351 1.1590xE10 94.02 3,759,508 3,759,508 3,759,508 2,906,099,877 2,906,099,877 2,906,099,877
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Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 7 CPNPP NRC 2012 JPM RA3 Rev d.docx Facility: CPNPP JPM # NRC RA3 Task # RO4108 K/A # 2.2.12 3.7 / 4.1
Title:
Perform Control Room Air Conditioning System Surveillance Data Examinee (Print):
Testing Method:
Simulated Performance:
Classroom:
X Actual Performance:
X Simulator:
Alternate Path:
Plant:
Time Critical:
READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.
When you complete the task successfully, the objective for this JPM will be satisfied.
Initial Conditions:
Given the following conditions:
Both Units are operating at 100% power with all controls in Automatic.
Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.
The 30 minute run time since completion of the Prerequisites is complete.
The following parameters are observed:
CR A/C UNIT 03-X-PI-3585A reads 150 psig and is operating 33%
unloaded.
CR A/C UNIT 04 -X-PI-3586A reads 140 psig and is operating 50%
unloaded.
X-TR-4123 reads 105°F.
X-TI-5933 reads 72°F.
X-TI-5734 reads 73°F.
X-TI-5735 reads 73°F.
Initiating Cue:
The Unit Supervisor directs you to PERFORM the following:
COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.
RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.
Task Standard:
Utilizing OPT-116, recorded data on OPT-116-1, plotted air conditioning unit cooling capacity, and determined Acceptance Criteria met.
Required Materials: OPT-116, CR AC System, Rev. 4.
OPT-116-1, CR AC System Data Sheet, Rev. 4.
Validation Time:
25 minutes Completion Time:
________ minutes
CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 1 OF 4 R-4 STEP OBSERVED REQUIRED TEST CONDITIONS INITIALS 6.0 PREREQUISITES MET N/A N/A AND TIME/DATE N/A 8.1 CR A/C UNITS BEING TESTED N/A 8.2 TIME AND DATE
$30 MIN PAST STEP 6.0 8.3 RECORD THE FOLLOWING:
X-TR-4123 OUTSIDE TEMPERATURE N/A X-TI-5933
$60°F X-TI-5734
$60°F X-TI-5735
$60°F COMPRESSOR DISCHARGE PRESSURES (N/A for shutdown units)
CR A/C UNIT 01 (X-PI-3583A)
<170 PSIG CR A/C UNIT 02 (X-PI-3584A)
<170 PSIG CR A/C UNIT 03 (X-PI-3585A)
<170 PSIG CR A/C UNIT 04 (X-PI-3586A)
<170 PSIG 8.4 ALL ABOVE REQUIRED TEST CONDITIONS MET N/A NOTE 1 NOTE 1:
If test conditions are not met, terminate test at this point. Test shall be restarted when conditions can be met.
CPNPP NRC 2012 JPM RA3 Answer Key Rev d CPNPP NRC 2012 JPM RA3 Answer Key Rev d N/A N/A N/A N/A RB RB Today @ 0800 Units 03 & 04 Today @ 0900 RB RB 105 F 72 F 73 F 73 F RB RB RB RB RB RB RB 150 psig 140 psig
CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 2 OF 4 R-4 STEP OBSERVED INITIALS 8.5 A/C UNIT % UNLOADED (N/A for shutdown units)
A/C UNIT 01 A/C UNIT 02 A/C UNIT 03 A/C UNIT 04 8.6 CALCULATE AVERAGE A/C UNIT NO. A/C UNIT NO.
% UNLOADED + % UNLOADED 2
=
TRAIN AVERAGE COMPRESSOR COOLING CAPACITY AVAILABILITY VERIFIED 8.7 COMPARE OUTSIDE TEMP (STEP 8.3) AND AVERAGE COMPRESSOR COOLING CAPACITY AVAILABILITY (STEP 8.6) TO CURVE (FIGURE 1)
OPERATION ABOVE/BELOW CURVE ACCEPTANCE CRITERIA SAT IF OPERATION IS ABOVE CURVE SAT/UNSAT CPNPP NRC 2012 JPM RA3 Answer Key Rev d CPNPP NRC 2012 JPM RA3 Answer Key Rev d RB RB RB RB RB 03 04 33 50 41.5 N/A N/A N/A N/A 33 50 N/A
CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 3 OF 4 R-4 0
10 20 30 40 50 60 70 0
10 20 30 40 50 60 70 80 90 100 110 120 OUTSIDE TEMPERATURE (F)
COOLING CAPACITY AVAILABLE (%)
FIGURE 1 OUTSIDE TEMPERATURE 110 100 90 80 70 60 50 40 30 20 PERCENT UNLOADED 16.7 24.3 32.0 39.6 47.2 51.7 54.1 56.5 58.9 61.3 CONTROL ROOM HVAC MINIMUM REQUIRED AVAILABILITY THE UNLOADED COMBINED AVERAGE OF THE TWO 50% CONTROL ROOM HVAC UNITS MUST BE ABOVE THE CURVE REPRESENTED BELOW:
CPNPP NRC 2012 JPM RA3 Answer Key Rev d CPNPP NRC 2012 JPM RA3 Answer Key Rev d
CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 4 OF 4 R-4 COMMENTS/DISCREPANCIES:
CORRECTIVE ACTIONS:
PERFORMED BY: DATE:
SIGNATURE REVIEWED BY: DATE:
OPERATIONS MANAGEMENT CPNPP NRC 2012 JPM RA3 Answer Key Rev d CPNPP NRC 2012 JPM RA3 Answer Key Rev d
Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 7 CPNPP NRC 2012 JPM RA3 Rev d.docx Comments:
Result:
SAT UNSAT Examiner (Print / Sign):
Date:
Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 7 CPNPP NRC 2012 JPM RA3 Rev d.docx CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
OPT-116, CR AC System.
INITIAL and N/A as appropriate up to Step 8.3.
OPT-116-1, CR AC System Data Sheet.
INITIAL and N/A as appropriate up to Step 8.3
Appendix C JPM STEPS Form ES-C-1 Page 4 of 7 CPNPP NRC 2012 JPM RA3 Rev d.docx
- Check Mark Denotes Critical Step START TIME:
Examiner Note:
The following steps are from OPT-116, Section 8.2.
Perform Step: 1 8.3 & 1st bullet RECORD the following:
X-TR-4123, outside temperature (10M PRI) (X-CV-05)
Standard:
RECORDED X-TR-4123, outside temperature of 105°F on OPT-116-1 and INITIALED.
Comment:
SAT UNSAT Perform Step: 2 8.3 & 2nd bullet RECORD the following:
X-TI-5933 ECB EXH TEMP (X-CV-01)
Standard:
RECORDED X-TI-5933, ECB EXH TEMP of 72°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.
Comment:
SAT UNSAT Perform Step: 3 8.3 & 3rd bullet RECORD the following:
X-TI-5734, AB EXH TEMP EL-852' 6" (X-CV-03)
Standard:
RECORDED X-TI-5734, AB EXH TEMP of 73°F on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.
Comment:
SAT UNSAT Perform Step: 4 8.3 & 4th bullet RECORD the following:
X-TI-5735, AB EXH TEMP EL-831' 6" (X-CV-03)
Standard:
RECORDED X-TI-5735, AB EXH TEMP of 73°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.
Comment:
SAT UNSAT
Appendix C JPM STEPS Form ES-C-1 Page 5 of 7 CPNPP NRC 2012 JPM RA3 Rev d.docx Perform Step: 5 8.3 & 5th bullet RECORD the following:
Compressor discharge pressures for operating A/C units.
CR A/C Unit 03 (X-PI-3585A)
Standard:
RECORDED CR A/C Unit 03 (X-PI-3585A) pressure of 150 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.
Comment:
SAT UNSAT Perform Step: 6 8.3 & 5th bullet RECORD the following:
Compressor discharge pressures for operating A/C units CR A/C Unit 04 (X-PI-3586A)
Standard:
RECORDED CR A/C Unit 04 (X-PI-3586A) pressure of 140 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.
Comment:
SAT UNSAT Perform Step: 7 8.4 VERIFY the above readings are within the specified limits. If any of the above readings are NOT within the specified limits, this test should be terminated and restarted when the above conditions can be met.
Standard:
VERIFIED that all readings are within limits and INITIALED.
Comment:
SAT UNSAT Perform Step: 8 8.5 RECORD % unloaded (lights on A/C Unit Control Panel) for both operating A/C units.
A/C UNIT 03 Standard:
RECORDED A/C UNIT 03 % unloaded of 33% on OPT-116-1 and INITIALED.
Comment:
SAT UNSAT Perform Step: 9 8.5 RECORD % unloaded (lights on A/C Unit Control Panel) for both operating A/C units.
A/C UNIT 04 Standard:
RECORDED A/C UNIT 04 % unloaded of 50% on OPT-116-1 and INITIALED.
Comment:
SAT UNSAT
Appendix C JPM STEPS Form ES-C-1 Page 6 of 7 CPNPP NRC 2012 JPM RA3 Rev d.docx Perform Step: 10 8.6 CALCULATE the average % unloaded by adding the % unloaded from the operating compressors and dividing by 2.
Standard:
ADDED 33% and 50% and DIVIDED by 2 to yield an average of 41.5%;
RECORDED on OPT-116-1 and INITIALED.
Comment:
SAT UNSAT Perform Step: 11 8.7 Using outside temperature (Step 8.3) and the calculated average compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.
Standard:
PLOTTED the intersection point for 105 degrees and 41.5% on Figure 1 and COMPARED to the acceptability curve.
Comment:
SAT UNSAT Perform Step: 12 8.7 Using outside temperature (Step 8.3) and the calculated average compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.
Standard:
VERIFIED plotted point is ABOVE the curve on Figure 1 and CIRCLED ABOVE then SAT on OPT-116-1 and INITIALED.
Terminating Cue:
This JPM is complete.
Comment:
SAT UNSAT STOP TIME:
Appendix C JPM CUE SHEET Form ES-C-1 Page 7 of 7 CPNPP NRC 2012 JPM RA3 Rev d.docx INITIAL CONDITIONS:
Given the following conditions:
Both Units are operating at 100% power with all controls in Automatic.
Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.
The 30 minute run time since completion of the Prerequisites is complete.
The following parameters are observed:
CR A/C UNIT 03-X-PI-3585A reads 150 psig and is operating 33% unloaded.
CR A/C UNIT 04 -X-PI-3586A reads 140 psig and is operating 50% unloaded.
X-TR-4123 reads 105°F.
X-TI-5933 reads 72°F.
X-TI-5734 reads 73°F.
X-TI-5735 reads 73°F.
INITIATING CUE:
The Unit Supervisor directs you to PERFORM the following:
COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.
RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.
CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 1 OF 4 R-4 STEP OBSERVED REQUIRED TEST CONDITIONS INITIALS 6.0 PREREQUISITES MET N/A N/A AND TIME/DATE N/A 8.1 CR A/C UNITS BEING TESTED N/A 8.2 TIME AND DATE
$30 MIN PAST STEP 6.0 8.3 RECORD THE FOLLOWING:
X-TR-4123 OUTSIDE TEMPERATURE N/A X-TI-5933
$60°F X-TI-5734
$60°F X-TI-5735
$60°F COMPRESSOR DISCHARGE PRESSURES (N/A for shutdown units)
CR A/C UNIT 01 (X-PI-3583A)
<170 PSIG CR A/C UNIT 02 (X-PI-3584A)
<170 PSIG CR A/C UNIT 03 (X-PI-3585A)
<170 PSIG CR A/C UNIT 04 (X-PI-3586A)
<170 PSIG 8.4 ALL ABOVE REQUIRED TEST CONDITIONS MET N/A NOTE 1 NOTE 1:
If test conditions are not met, terminate test at this point. Test shall be restarted when conditions can be met.
CPNPP NRC 2012 JPM RA3 Answer Key Rev d CPNPP NRC 2012 JPM RA3 Answer Key Rev d N/A N/A N/A N/A RB RB Today @ 0800 Units 03 & 04 Today @ 0900 RB RB 105 F 72 F 73 F 73 F RB RB RB RB RB RB RB 150 psig 140 psig
CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 2 OF 4 R-4 STEP OBSERVED INITIALS 8.5 A/C UNIT % UNLOADED (N/A for shutdown units)
A/C UNIT 01 A/C UNIT 02 A/C UNIT 03 A/C UNIT 04 8.6 CALCULATE AVERAGE A/C UNIT NO. A/C UNIT NO.
% UNLOADED + % UNLOADED 2
=
TRAIN AVERAGE COMPRESSOR COOLING CAPACITY AVAILABILITY VERIFIED 8.7 COMPARE OUTSIDE TEMP (STEP 8.3) AND AVERAGE COMPRESSOR COOLING CAPACITY AVAILABILITY (STEP 8.6) TO CURVE (FIGURE 1)
OPERATION ABOVE/BELOW CURVE ACCEPTANCE CRITERIA SAT IF OPERATION IS ABOVE CURVE SAT/UNSAT CPNPP NRC 2012 JPM RA3 Answer Key Rev d CPNPP NRC 2012 JPM RA3 Answer Key Rev d RB RB RB RB RB 03 04 33 50 41.5 N/A N/A N/A N/A 33 50 N/A
CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 3 OF 4 R-4 0
10 20 30 40 50 60 70 0
10 20 30 40 50 60 70 80 90 100 110 120 OUTSIDE TEMPERATURE (F)
COOLING CAPACITY AVAILABLE (%)
FIGURE 1 OUTSIDE TEMPERATURE 110 100 90 80 70 60 50 40 30 20 PERCENT UNLOADED 16.7 24.3 32.0 39.6 47.2 51.7 54.1 56.5 58.9 61.3 CONTROL ROOM HVAC MINIMUM REQUIRED AVAILABILITY THE UNLOADED COMBINED AVERAGE OF THE TWO 50% CONTROL ROOM HVAC UNITS MUST BE ABOVE THE CURVE REPRESENTED BELOW:
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CR A/C SYSTEM DATA SHEET CONTINUOUS USE OPT-116-1 PAGE 4 OF 4 R-4 COMMENTS/DISCREPANCIES:
CORRECTIVE ACTIONS:
PERFORMED BY: DATE:
SIGNATURE REVIEWED BY: DATE:
OPERATIONS MANAGEMENT CPNPP NRC 2012 JPM RA3 Answer Key Rev d CPNPP NRC 2012 JPM RA3 Answer Key Rev d
CPNPP NRC 2012 JPM RA3 Form Rev d CPNPP NRC 2012 JPM RA3 Form Rev d
CPNPP NRC 2012 JPM RA3 Form Rev d CPNPP NRC 2012 JPM RA3 Form Rev d
CPNPP NRC 2012 JPM RA3 Form Rev d CPNPP NRC 2012 JPM RA3 Form Rev d
CPNPP NRC 2012 JPM RA3 Form Rev d CPNPP NRC 2012 JPM RA3 Form Rev d
CPNPP NRC 2012 JPM RA3 Procedure Rev d CPNPP NRC 2012 JPM RA3 Procedure Rev d
CPNPP NRC 2012 JPM RA3 Procedure Rev d CPNPP NRC 2012 JPM RA3 Procedure Rev d
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Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 5 CPNPP NRC 2012 JPM RA4 Rev d.docx Facility: CPNPP JPM # NRC RA4 Task # RWT029 K/A # 2.3.13 3.4 / 3.8
Title:
Determine Containment Stay Time Requirements Examinee (Print):
Testing Method:
Simulated Performance:
Classroom:
X Actual Performance:
X Simulator:
Alternate Path:
Plant:
Time Critical:
READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.
When you complete the task successfully, the objective for this JPM will be satisfied.
Initial Conditions:
Given the following conditions:
A Containment entry is about to be performed by a 4 member team.
The estimated gamma dose rate is 75 mrem/hr.
The estimated neutron dose rate is 10 mrem/hr.
Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.
Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.
The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.
The Heat Stress Action Time has been determined to be 40 minutes.
Initiating Cue:
The Work Control Supervisor directs you to PERFORM the following:
CALCULATE the following:
Gamma dose stay time per team.
_____ minutes.
Neutron dose stay time per team.
_____ minutes.
Heat Stress Stay Time
_____ minutes.
DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:
Limiting Containment entry time:
_____ minutes.
Task Standard:
Utilizing STA-620/655/657/660/674, calculated gamma and neutron dose stay times for the team, Heat Stress Stay Time, and determined limiting Containment entry time.
Required Materials: STA-620, Containment Entry, Rev. 13.
STA-655, Exposure Monitoring Program, Rev. 20.
STA-657, ALARA Job Planning/Debriefing, Rev. 14.
STA-660, Control of High Radiation Areas, Rev. 15.
STA-674, Heat Stress Management, Rev. 8.
Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 5 CPNPP NRC 2012 JPM RA4 Rev d.docx Validation Time:
15 minutes Completion Time:
________ minutes Comments:
Result:
SAT UNSAT Examiner (Print / Sign):
Date:
Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 5 CPNPP NRC 2012 JPM RA4 Rev d.docx CLASSROOM SETUP EXAMINER:
MAKE the following available in the classroom:
STA-620, Containment Entry.
STA-655, Exposure Monitoring Program.
STA-657, ALARA Job Planning/Debriefing.
STA-660, Control of High Radiation Areas.
STA-674, Heat Stress Management ENSURE examinee has a calculator.
Appendix C JPM STEPS Form ES-C-1 Page 4 of 5 CPNPP NRC 2012 JPM RA4 Rev d.docx
- Check Mark Denotes Critical Step START TIME:
Examiner Note:
Provide the examinee with copy of JPM Cue Sheet #1.
Perform Step: 1 Calculate gamma dose stay time per team.
Standard:
CALCULATED the following:
75 mrem/hr gamma x 4 persons = 300 mrem/hr from gamma.
500 person-REM allowed 100 minute gamma Stay Time Comment:
SAT UNSAT Perform Step: 2 Calculate neutron dose stay time per team.
Standard:
CALCULATED the following:
10 mrem/hr neutron x 4 persons = 40 mrem/hr from neutron.
50 person-REM allowed 75 minute neutron Stay Time Comment:
SAT UNSAT Examiner Note:
The following step is from STA-674, Section 4.0, Definitions.
Perform Step: 3 Calculate Heat Stress Stay Time.
Standard:
CALCULATED the following:
Heat Stress Action Time is 40 minutes per the Initial Conditions.
Heat Stress Stay Time is 2 x 40 minutes = 80 minutes Comment:
SAT UNSAT Perform Step: 4 Determine limiting Containment entry time.
Standard:
DETERMINED the limiting Containment entry time is 75 minutes based on Neutron Dose Stay Time.
Terminating Cue:
This JPM is complete.
Comment:
SAT UNSAT STOP TIME:
Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP NRC 2012 JPM RA4 Rev d.docx INITIAL CONDITIONS:
Given the following conditions:
A Containment entry is about to be performed by a 4 member team.
The estimated gamma dose rate is 75 mrem/hr.
The estimated neutron dose rate is 10 mrem/hr.
Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.
Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.
The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.
The Heat Stress Action Time has been determined to be 40 minutes.
INITIATING CUE:
The Work Control Supervisor directs you to PERFORM the following:
CALCULATE the following:
Gamma dose stay time per team. _____ minutes.
Neutron dose stay time per team. _____ minutes.
Heat Stress Stay Time
_____ minutes.
DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:
Limiting Containment entry time: _____ minutes.
COMANCHE PEAK NUCLEAR POWER PLANT l
STATION ADMINISTRATION MANUAL FOR EMPLOYEE USE:
l DATE VERIFIED/INITIALS
/
LATEST PCN/EFFECTIVE DATE NA
/
l LEVEL OF USE:
l INFORMATION USE l
QUALITY RELATED CONTAINMENT ENTRY PROCEDURE NO. STA-620 REVISION NO. 13 SORC MEETING NO. #12-002 DATE: 1/30/12 EFFECTIVE DATE: 2/09/12 MAJOR REVISION l
PREPARED BY (Print):
AMY DOWELL EXT.
5272 TECHNICAL REVIEW BY (Print):
RON CUTLIP EXT.
8228 APPROVED BY:
STEVE SMITH DATE:
2/2/12 PLANT MANAGER CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE
..................................................... 3 2.0 APPLICABILITY................................................. 4
3.0 REFERENCES
.................................................. 5 4.0 DEFINITIONS/ACRONYMS........................................ 7 5.0 RESPONSIBILITIES.............................................. 9 6.0 INSTRUCTIONS................................................ 14 6.1 Precautions.................................................... 14 6.2 Containment Entry Requirements Non-Emergency..................... 18 l
6.3 Emergency Containment Entry Requirements......................... 26 6.4 Use of Emergency Airlock......................................... 27 7.0 FIGURES..................................................... 29 7.1 Containment Pre-Access Filtration System
........................... 30 l
8.0 ATTACHMENTS/FORMS......................................... 29 8.A Guidelines for Containment Visual Inspections
........................ 31 l
8.B Containment Floor Plans
......................................... 32 l
8.C General Airlock Cautionary and Awareness Criteria..................... 36 l
9.0 RECORDS.................................................... 29 CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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[C] 1.0 PURPOSE 1.1 The purpose of this procedure is to delineate responsibilities and provide the necessary instructions required to safely enter Containment during MODES 1 through 4 of operation.
1.2 This procedure satisfies the following requirements of the CPSES Technical Requirements Manual:
TRS 13.5.31.2 visual inspection for loose debris in affected areas of Containment during MODES 1 through 4.
1.3 This procedure is also a trigger procedure for the following requirements of the CPSES Technical Specifications:
SR 3.6.2.1, Containment Airlock operability.
1.4 The figures/attachments/forms listed below do not require SORC review when being modified and issued per STA-202:
Figure 7.1, Containment Pre-Access Filtration System
!.A, Guidelines for Containment Visual Inspections l
!.B, Containment Floor Plans l
!.C, General Airlock Cautionary and Awareness Criteria l
STA-620-1, Containment Entry Authorization and Visual Inspection Verification CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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2.0 APPLICABILITY NOTE:
MODE 4 requirements may be implemented at the discretion of the Shift Manager while the plant is in MODE 5 or 6.
2.1 This procedure applies to all personnel requiring access to Containment during MODES 1 through 4 of operation or following a reactor trip or plant emergency.
2.2 When performing activities associated with this procedure, REFER to STA-919, CPNPP Safety-Security Interface Requirements to determine if a Safety-Security interface requirement may be adversely affected prior to continuing the activity.
[CR-2010-000434]
Example of activity: Emergency entry through the Emergency Airlock CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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3.0 REFERENCES
3.1 Performance References 3.1.1 STA-123, Pre-Job and Post-Job Briefs 3.1.2 STA-607, Housekeeping Control l
l 3.1.3 STA-625, Foreign Material Exclusion l
3.1.4 STA-628, Confined Space Entry 3.1.5 STA-660, Control of High Radiation Areas l
3.1.6 STA-674, Heat Stress Management 3.1.7 STA-681, Pressurized Containment Entry 3.1.8 STA-702, Surveillance Program 3.1.9 STA-729, Control of Transient Combustibles, Ignition Sources and Fire Watches 3.1.10 STA-919, CPNPP Safety-Security Interface Requirements 3.1.11 OPT-305, Containment Closeout Inspection 3.1.12 SOP-801A/B, Containment Ventilation System 3.1.13 A1-0413 Series Drawings, Room Area Designations Unit 1 and 2 CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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3.2 Developmental References 3.2.1 STA-601, Authority for Equipment Operation 3.2.2 STA-606, Control of Maintenance and Work Activities l
3.2.3 STA-656, Radiation Work Control l
3.2.4 OPT-408A/B, Refueling Containment Penetration Verification 3.2.5 RFO-102A/B, Refueling Operation 3.2.6 SOP-907A/B, Containment Personnel Airlocks 3.2.7 CPSES Technical Specifications section SR 3.6.2.1 3.2.8 Commitment #s 00747, 24998, and 26722 l
3.2.9 NRC-60FR46497 (09/07/95) (Modified Security requirements) 3.2.10 AN-96-000190-00-05 3.2.11 CR-2011-010210 Unable to pressurize inner door seal for Unit 1 PAL l
during OPT-802A.
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4.0 DEFINITIONS/ACRONYMS 4.1 Bioshield - The permanent plant shielding encompassing the NSSS components (i.e.,
reactor vessel, steam generators and reactor coolant pumps).
4.2
[C] - Indicates steps referenced in the CPNPP Commitment Management Program l
4.3 Containment Pre-entry Meeting - A meeting typically scheduled at least one (1) day prior to Containment entry. This meeting should be conducted for entries involving non-routine, complex activities or as requested by RP, Operations, or any other organization involved in the entry. Items to be discussed during the conduct of this meeting are described in Step 6.2.3.
4.4 Emergency Entry - Entry into Containment to prevent actual or potential personnel injury or damage to equipment and facilities or as requested by the Shift Manager to address plant operational concerns.
4.5 FME Zone (FMEZ) - The clean area identified by an FMEZ sign (similar to Attachment 8.D) and an FME red/white boundary ribbon/tape where FME controls are required to protect open components or systems from being degraded by foreign material. The natural enclosure of a room or area may be designated as an FMEZ with a sign only at the entrance/s.
4.6 FME Control Plan - A written description of the FME controls, consisting of the Work Order, implementing procedure and the STA-625-4 FME Control Planthat will be discussed during the pre-job brief and used during the work to prevent an FME event.
4.7 General Entry - Includes but are not limited to Operator tours, inspection and system manipulations, RP or Safety surveys, or initial entries to evaluate equipment performance.
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4.8 Multiple RWO Entry - Entry in which multiple RWOs are working on different components in different locations inside Containment.
4.9 Multiple Team Entry - Entry in which one task involves multiple work organizations (e.g.,
valve rework/MM, IC).
4.10 Responsible Work Organization (RWO) - The lead organization (e.g., Chemistry, Maintenance Team, Operations, PROMPT Team or Maintenance Services) that has l
responsibility for resolution of a work activity.
4.11 RWO Supervisor - The individual designee assigned by the RWO and having responsibility for the work activity performance (e.g., a Manager, Supervisor, Team Leader, Craftsman or Technician).
4.12 Scheduled Entry - Entry into Containment for the purpose of conducting routine tasks necessary to support unit operations.
4.13 Unplanned Entry - Entry into Containment that has NOT been included in the POD/Outage schedule.
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5.0 RESPONSIBILITIES 5.1 Shift Manager 5.1.1 Responsible for verifying incore instrumentation is in the stored position and tagged out of service, if required.
5.1.2 Responsible for turning ON Containment lighting prior to Containment Entry and for turning OFF Containment lighting after the work group exits Containment. Security should be contacted to ensure all personnel have exited containment. Contact CAS or SAS at ext. 5606 to obtain accountability report for applicable containment. IF a backup method is utilized for personnel accountability, THEN the RWO Supervisor will provide this information.
5.1.3 Responsible for authorizing a Containment Entry.
5.1.4 Responsible for signing Form STA-620-1 as specified in STA-702.
[C]
5.1.5 Responsible for assigning an individual to operate the Personnel Airlock.
5.1.6 Responsible for ensuring the Operations Department has a representative at the scheduled Containment pre-entry meetings when requested.
5.1.7 Responsible for having Containment checked for Class C Atmosphere as defined by STA-628 if Nitrogen or other gas leaks are suspected.
5.1.8 Responsible for performing leak test of Containment Airlock seals after entry completion as applicable.
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5.2 RWO Supervisor 5.2.1 Responsible for notifying Radiation Protection of pending entry and for notifying Security if the entry is planned through the Emergency Airlock.
5.2.2 Responsible for notifying Control Room before and after Containment entries.
5.2.3 Responsible for coordinating Containment Entry activities and completing applicable forms.
5.2.4 Responsible for Housekeeping in accordance with STA-607, AND Foreign Material Exclusion in accordance with STA-625 including completion of the FME Control Plan form (STA-625-4).
5.2.5 Responsible for ensuring that visual inspections are performed in affected areas of Containment in accordance with Technical Requirements Manual TRS 13.5.31.2 and documented on form STA-620-1. A Form STA-620-1 shall be completed once a day or fraction of a day for the entire job duration. A Form STA-620-1 should be completed as part of each shift turnover of the applicable job.
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5.2.6 Responsible for maintaining personnel accountability in the event of a Containment evacuation.
NOTE:
SMF-2004-00003660 identified an event where personnel accountability was lost when employee badges were unable to be read by the Containment Access Control card readers.
5.2.6.1 Responsible for discussing the methods of accountability with Operations. Reference Step 5.1.2.
Utilization of the Containment Access Control accountability card readers should be used as the primary method for accomplishing personnel accountability.
Use of the RWP access events from the RP computer or manual paper logs are acceptable backup methods for maintaining personnel accountability.
5.2.6.2 Responsible for ensuring all personnel utilize the appropriate method for personnel accountability when entering and exiting the containment.
5.2.6.3 Responsible for ensuring that individuals are familiar with the location of the Containment and Emergency Airlocks, the intended work location(s), and evacuation routes.
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5.2.7 Responsible for completing Containment Entry Checklist (part of STA-620-1) prior to Containment pre-entry meetings.
5.2.8 Responsible for familiarizing self and all team members with the Containment Entry Checklist.
5.2.9 Responsible for attending Containment pre-entry meetings when requested.
5.2.10 Responsible for ensuring a minimum of two people enter Containment.
Reference steps 6.1.5 and 6.3.1.
5.3 Radiation Protection 5.3.1 The On-shift Radiation Protection Technician is responsible for preparation of the RWP when necessary.
5.3.2 Responsible for providing radiological briefing to personnel prior to entry.
5.3.3 Responsible for attending Containment pre-entry meetings when requested.
5.4 Security 5.4.1 Responsible for establishing vital area entry/exit controls for Containment entries through the Emergency Airlock.
5.4.2 Responsible for attending Containment pre-entry meetings when requested.
5.4.3 Responsible for providing a Containment accountability report when requested by the Control Room / Shift Manager.
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5.5 System Engineering 5.5.1 Responsible for attending Containment pre-entry meetings when requested.
5.6 Safety Services 5.6.1 Responsible for attending Containment pre-entry meetings when requested and discussing the heat stress program requirements when appropriate. IF required, the heat stress form should be completed at the meeting.
5.7 Work Control Manager OR Outage Manager 5.7.1 Responsible for scheduling Containment entry activities.
5.7.2 Responsible for scheduling and coordinating Containment pre-entry meetings when required. Reference Step 4.3.
5.7.3 Responsible for contacting the RWOs, RP, OPS, Safety Services and System Engineering of impending Containment entries and pre-entry meetings and for contacting Security if the entry is planned through the Emergency Airlock.
5.7.4 Responsible for chairing Containment pre-entry meetings.
5.8 Maintenance 5.8.1 The Maintenance Support Manager is responsible for maintaining this procedure current.
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6.0 INSTRUCTIONS 6.1 Precautions 6.1.1 IF Containment Evacuation Alarm or Area Radiation Monitor alarms annunciate in the affected areas, or a Containment Evacuation announcement is made over the plant communication system, THEN all personnel shall leave Containment immediately. Containment re-entry shall be authorized by the Shift Manager only when the reason and circumstances associated with the evacuation, AND the existing radiological conditions in Containment are known.
6.1.1.1 Upon exiting Containment, all personnel shall proceed to the designated Containment Evacuation Assembly area.
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6.1.2 During refueling outages and maintenance activities, or when Containment is otherwise occupied for extended periods, the incore detectors should be tagged out of service until work activities are completed and/or arrangements made to preclude entry to the following areas:
808'-Incore Instrumentation Room 808'-Excess Letdown Heat Exchanger Room 808'-Steam Generator Loop Rooms 832'-Incore Instrumentation Room 832'-Regenerative Heat Exchanger Room 849'-Incore Instrumentation Room IF either of the following is true, THEN Caution Tags may be lifted by the Shift Manager:
The detectors have been placed in storage and/or are incapable of being withdrawn or moved during performance of maintenance and testing.
It has been determined by Radiation Protection that operation of the incore detectors will not adversely affect other activities in Containment.
6.1.3 IF entry into the Seal Table or Incore Drive rooms is required for reasons other than repair of the Incore System, THEN the Incore instrumentation shall be placed within the reactor core or otherwise located to minimize exposure; AND should be tagged out of service.
6.1.4 When in MODES 1 and 2, entry into the S/G Loop Rooms should be approved by the Radiation Protection Manager or the Plant Manager. Entry should be in accordance with STA-660.
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6.1.5 The following personnel criteria should be observed :
6.1.5.1 A minimum of two people are required to enter Containment. IF Radiation Protection coverage is provided, THEN the Radiation Protection technician may be considered as the second person.
6.1.5.2 A maximum of 50 people should be allowed in Containment at any one time during MODES 1 and 2. This is an administrative limit recommended by EVAL-2004-000472-01.
6.1.6 WHEN the reactor trip breakers are closed, portable radios with an output power greater than 0.5 watts are prohibited from transmitting on the 842' and 860' elevations inside Containment.
6.1.7 Treat all material/debris inside Containment as potentially contaminated.
6.1.8 Work in progress may allow certain clothing, tools, equipment, etc. to remain in Containment. Such materials shall be removed when work is completed.
6.1.9 Formal visual close-out inspections are not required for General Entries.
Under these circumstances, individuals are responsible for ensuring that any equipment or personal item(s), for example flashlights, survey meters, test equipment, PPE, clipboards, pens, note paper, or similar items, inherently required for the activity are still in their possession upon exit. The RWO Supervisor should ensure that individuals are aware of this requirement prior to entry.
6.1.10 Personnel entering containment are the responsibility of the RWO Supervisor.
NO PERSON should tag along on an open STA-620-1 form without the approval of the RWO Supervisor as indicated in Section 3 of the Containment Entry Checklist.
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6.1.11 Personnel entering the Containment Building during Modes 1 through 4 are entering an FMEZ.
6.1.12 S/G Loop Room platform handrails may be partially to completely removed.
Access to the platforms in these areas may require compensatory fall protection measures.
6.1.13 Verify the PAL OR EAL seals and sealing surfaces are clear of any obvious l
foreign material AND debris when closing the doors during Containment l
entries. (CR-2011-010210-00) l CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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6.2 Containment Entry Requirements Non-Emergency NOTE 1:
IF a multiple team entry is required, (entry in which one work task involves multiple organizations), a Lead RWO Supervisor may be appointed from the disciplines entering Containment. The Lead RWO Supervisor is then responsible for coordinating the Containment entry and visual inspection for loose debris in accordance with Section 5.2 of this procedure.
IF a multiple RWO entry is required, (entry in which multiple RWOs are working on different components in different locations in Containment), RWO Supervisors are responsible for their respective Containment entry and the visual inspection for loose debris in accordance with Section 5.2 of this procedure.
NOTE 2:
Access is limited to those locations/elevations specified by the Shift Manager.
6.2.1 The RWO Supervisor requiring access has the overall responsibility for initiating and coordinating those activities which culminate in entry to Containment.
6.2.1.1 IF this is an Unplanned Entry, the Containment Entry Checklist may be N/Ad with the concurrence of the Shift Manager. ALL other requirements for entry are still applicable. Note reason for entry in ACTION ITEMS/Comments section of STA-620-1.
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6.2.2 The Shift Manager should determine if entry to Containment is feasible on the date and time requested. This determination should be made based on the following general conditions:
The present MODE of operation; Projected or potential changes in the existing MODE of plant operation; Plant evolutions within a given MODE Radiological conditions.
Containment Atmosphere IF Containment Entry is NOT feasible, when requested, the Shift Manager should recommend an appropriate date and time.
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6.2.3 The Work Control Manager, Outage Manager, or designee should perform the following:
When required (Reference Step 4.3), schedule a Containment pre-entry meeting prior to the entry.
Notify the RWOs, RP, Security, OPS, Safety Services, Engineering, and other groups, as appropriate.
When conducted, chair the Containment pre-entry meeting. Each RWO entering Containment should have answered the questions on the Containment Entry Checklist (part of STA-620-1) appropriate to their work. The meeting is to discuss the entry, this includes:
Purpose Participation (Work Week Coordinator to ensure the number of personnel required for entry during MODES 1 and 2 satisfies the requirement of Step 6.1.5.2.)
Specific objective Contingency plans Schedules Individual responsibilities Reinforce the expectation to verify the PAL OR EAL seals and sealing l
surfaces are clear of any obvious foreign material AND debris when l
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6.2.4 Upon determining that Containment Entry is feasible, each RWO Supervisor requiring access should initiate the following as required:
A Confined Space Entry Permit Request IF access is required into any l
confined spaces inside Containment such as sumps, vessels, pits or others identified in accordance with STA-628.
A heat stress survey form in accordance with STA-674.
An FME Control Plan, in accordance with STA-625, describing the FME l
controls that will be used during the work to prevent an FME event.
Notify the Fire Protection Supervisor if the task requires permits associated with hot work activities or transient combustibles in accordance with STA-729.
Ensure the requirements for Pressurized Containment Entry are reviewed and complied with in accordance with STA-681.
Ensure a pre-job and post-job brief per STA-123 is performed for a specific task. This brief is in addition to the Containment pre-entry meeting scheduled by Work Control.
NOTE:
The following is NOT required for an Unplanned Entry.
Complete the Containment Entry Checklist (part of STA-620-1),
Sections 1 Work Scope and 2 Responsibilities, before the Containment pre-entry meeting. Section 3, Personnel, of the Containment Entry Checklist is to be used to list those personnel who have been properly briefed or have permission from the RWO Supervisor for entry on this STA-620-1, not necessarily a list of actual entrants.
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6.2.5 Upon receiving notification of pending entry, Radiation Protection should perform the following tasks:
Evaluate airborne radioactivity concentrations from the respective unit's Containment Particulate, Iodine and Gas (PIG) monitor (1/2RE5502, 1/2RE5503 and 1/2RE5566) or, if the PIG is NOT operable, an air sample should be obtained and evaluated as soon as possible prior to allowing initial entry.
Recommend operation of the pre-access filtration system if airborne activity levels warrant its use. Refer to Figure 7.1 for pre-access filtration system operating characteristics; Review DRMS information applicable to area within Containment where the entry team may traverse; Prepare RWP for Containment Entry or specify the appropriate GAP the entry team may utilize; Determine if Radiation Protection coverage is required based on area to be traversed, radiological conditions and current survey data.; and IF entry is to Seal Table room or Incore Drive room areas for trouble shooting purposes AND incore instruments are NOT tagged out, THEN, prior to entry, obtain approval from the Shift Manager.
6.2.6 Security should establish vital area entry/exit controls adjacent to Containment Emergency Airlock upon receiving notification of a pending entry through the Emergency Airlock.
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6.2.7 Once conditions have been met to proceed with a Containment Entry, the Shift Manager is responsible for the following:
Ensure that incore instrumentation is placed in storage and tagged out of service in accordance with Section 6.1.2.
IF airborne radioactivity concentrations warrant its use, THEN notify the Unit Supervisor to start up the pre-access filtration system in accordance with SOP-801A/B, "Containment Ventilation System;"
Ensure a LCOAR has been initiated to ensure completion of the Containment Airlock seal test as required to satisfy Technical Specification SR 3.6.2.1.
CAUTION:
The following action ensures that there is adequate lighting in Containment for egress. This lighting is NOT load-shed after Safety Injection.
Switch ON all available Containment lighting at the Containment Lighting Local Control Stations located in the Safeguards Building prior to Containment Entry. Normally as a minimum, ensure the following switches are on:
For Unit 1:
1-XF-SC1/3 (TR A Switchgear Room) 1-XF-SC2/4 (TR B Switchgear Room)
For Unit 2:
2-XF-SC1/3 (TR A Switchgear Room) 2-XF-SC2/4 (TR B Switchgear Room)
Sign STA-620-1 authorizing Containment Entry.
IF Nitrogen or other gas leaks are suspected, THEN have Containment sampled and analyzed for Class C Atmosphere as defined by STA-628.
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6.2.8 Once the RWP is approved, Containment Entry may proceed. At this point the work group should perform the following tasks:
Ensure STA-620-1 has been signed authorizing initial entry for the present shift.
NOTE:
A signature on STA-620-1 authorizing Containment Entry does NOT satisfy the requirement to notify the Control Room immediately prior to entry by the RWO.
The RWO Supervisor should notify the Control Room immediately prior to the work group entering Containment.
Maintain material and tool accountability using STA-625-1.
NOTE 1:.B, Containment Floor Plans, may be used to document l
approximate work location(s), and location of any equipment/material left in Containment.
NOTE 2:
Work in progress may allow certain clothing, tools, equipment, etc. to remain in Containment. Such materials shall be removed when work is completed.
[C]
6.2.9 After work is complete or at least once per shift, the RWO Supervisor should ensure a visual inspection of the affected area is performed. All trash, clothing l
or other loose materials shall be secured or removed to prevent transport to the Containment Sump. Refer to Attachment 8.A for final inspection criteria.
l 6.2.9.1 A Form STA-620-1 shall be completed once a day or fraction of a day for the entire job duration.
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6.2.10 Upon exiting Containment, the RWO Supervisor should notify the Control Room immediately.
NOTE:
Containment lighting may be left ON, at the discretion of the Shift Manager, as required to support plant activities, such as an additional Containment entry scheduled near term.
IF ALL Entry Teams have exited Containment, as determined by Containment accountability (reference step 5.1.2), THEN the Shift Manager should have Containment lighting switched OFF at the Containment Lighting Local Control Stations located in the Safeguards Building.
For Unit 1:
1-XF-SC1/3 (TR A Switchgear Room) 1-XF-SC2/4 (TR B Switchgear Room)
For Unit 2:
2-XF-SC1/3 (TR A Switchgear Room) 2-XF-SC2/4 (TR B Switchgear Room)
WHEN entries have been completed and Containment has been secured, THEN the Shift Manager shall ensure the requirements of TS 4.6.1.3a, Containment Operability, are met.
NOTE:
The Shift Managers authorizing signature is only required for the initial entry per shift of the associated job.
6.2.11 The RWO Supervisor shall complete Form STA-620-1, Containment Entry Authorization And Visual Inspection Verification and obtain the Shift Managers signature.
6.2.12 The Shift Manager should subsequently disposition Form(s) STA-620-1 after final acceptance.
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6.3 Emergency Containment Entry Requirements 6.3.1 A minimum of two people are required to enter Containment, one of which should be a Radiation Protection Technician.
6.3.2 All personnel entering Containment should wear the necessary protective clothing recommended by Radiation Protection. Personnel should also wear self contained breathing apparatus if airborne concentration levels are unknown or subject to change due to worsening plant conditions OR IF Nitrogen or other gas leaks are suspected. IF Containment has been sampled and analyzed for Class C Atmosphere as defined by STA-628, THEN Respiratory Protection may NOT be required if entry is made for a non-operational type emergency (e.g., medical injury).
6.3.3 A Containment briefing should be held by the Shift Manager. Each RWO entering into Containment should ensure that all questions on the checklist have been reviewed and that all entry members understand their responsibilities.
6.3.4 The Shift Manager shall approve all entries.
6.3.5 IF the Containment PIG (1/2RE5502, 1/2RE5503 and 1/2RE5566) is NOT operable, the Shift Manager should notify Radiation Protection to obtain Containment air samples in accordance with Section 6.2.5 of this procedure.
6.3.6 The Shift Manager should also notify Security prior to an emergency entry into Containment through the Emergency Airlock.
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NOTE:
During emergencies, an RWP need NOT be completed or issued prior to entry.
The required paperwork is expected to be completed in a timely manner consistent with related emergency response activities.
6.3.7 Containment entry should be documented by filling out an RWP. The RWP should be filled out by Radiation Protection.
6.3.8 A back-up team should be ready for Containment entry to provide assistance, if required.
6.4 Use of Emergency Airlock 6.4.1 Normal access and egress from Containment should be made using the Personnel Airlock. However, it may become necessary to use the Emergency Airlock. This decision should be made by the Shift Manager. For normal access through the Emergency Airlock, Security should be notified and an operator should be stationed with Radio Communication to ensure the Emergency Airlock Interlock is NOT challenged. All entry requirements specified in Sections 6.2 and 6.3 are applicable, with the exception of those items pertaining to the entry location.
6.4.2 The Emergency Airlock should be used for egress under the following conditions:
6.4.2.1 Whenever plant or environmental conditions are such that use of the Personnel Airlock is unfeasible or presents a personnel safety hazard; 6.4.2.2 Whenever the Personnel Airlock door malfunctions, provided that the following conditions are met:
The control room operator is notified and the Shift Manager authorizes use of the Emergency Airlock; and Every reasonable effort has been made to repair and open the inoperable Airlock door.
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NOTE:
Should environmental conditions preclude staying on the 899' elevation (e.g.,
steam generator atmospherics have lifted) personnel may wait for RP at the next lower elevation after exiting Containment.
6.4.3 Upon exiting Containment, personnel should stay in the enclosure on the 899' elevation until RP assistance arrives.
7.0 FIGURES 7.1 Figure 7.1 - Containment Pre-Access Filtration System 8.0 ATTACHMENTS/FORMS 8.1 Attachments 8.1.1.A Guidelines for Containment Visual Inspections l
NOTE:
The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only.
8.1.2.B Containment Floor Plans l
8.1.3.C General Airlock Cautionary and Awareness Criteria l
8.2 Forms 8.2.1 Form STA-620-1, Containment Entry Authorization And Visual Inspection Verification 9.0 RECORDS When completed, the following forms, reports, or other documents generated in response to this procedure should be dispositioned in accordance with STA-302, "Station Records" by the Shift Manager.
9.1 Form STA-620-1, Containment Entry Authorization And Visual Inspection Verification CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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FIGURE 7.1 PAGE 1 OF 1 CONTAINMENT PRE-ACCESS FILTRATION SYSTEM (CPFS)
Below is a table which predicts the reduction of particulate and radioiodine removal by the CPFS as a function of time. The filtration efficiency was set at 90%, and perfect mixing in Containment was assumed. The data below assumes 15,000 CFM from each unit (actual tolerance is 15,000 + 10%). Therefore operating times may vary + 10% from those listed. This table assumes no addition of particulates or iodine (i.e. Reactor NOT at power/no leakage). Cleanup at power will be significantly different and only come to equilibrium.
1 Unit Operating (Minutes)
Both Units Operating (Minutes) 100% of Original 0
0.0 50% of Original 153 76.5 25% of Original 306 153.0 10% of Original 509 254.0 5% of Original 662 331.0 CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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ATTACHMENT 8.A l
PAGE 1 OF 1 GUIDELINES FOR CONTAINMENT VISUAL INSPECTION NOTE 1:
Visual inspection requirements are limited to those areas of Containment that the entry team(s) traversed and where work was performed.
NOTE 2:
OPT-305, Containment Close Out Inspection step 8.1.2 contains a list of items approved by a Technical Evaluation to remain in Containment.
When multiple Containment entries occur over more than one work shift with Containment Integrity established, the inspection shall be performed at least once per shift.
During the final entry, the inspection shall be performed and should also include the l
following:
l 1.
Verify that no attached items/equipment or staging materials have been left behind (e.g.,
plastic sheeting, scaffolding, test equipment, drain hoses, sleeving, etc.).
2.
Verify that no foreign material such as temporary tags or posting materials have been left behind (e.g., work in progress tags, information tags, radiological postings associated with the work activity). Equipment labels, locked valve tags and valve/equipment tags installed per STA-618 are NOT included.
3.
The last person exiting Containment is to verify the PAL OR EAL seals and sealing l
surfaces are clear of any obvious foreign material AND debris prior to final closing of l
each door upon completion of Containment entries. (CR-2011-010210-00) l CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d
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STAIR NO. C-2 STEAM GEN NO. 3 STEAM GEN NO. 2 STAIR NO. C-1 STAIR NO. C-12 ELEVATOR LADDER OPEN OPEN LADDER EMERGENCY AIR LOCK STEAM GEN NO. 4 STEAM GEN NO. 1 REACTOR & CONTAINMENT OPEN OPEN OPEN ELEVATION 905'-6" ATTACHMENT 8.B l
PAGE 1 OF 5 CONTAINMENT FLOOR PLANS NOTE:
The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.
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CONTAINMENT COOLING UNIT CONTAINMENT COOLING UNIT EQUIPMENT HATCH STAIR NO. C-1 RCP
- 2 STEAM GEN #2 STEAM GEN #3 RCP
- 3 STAIR NO. C-2 STAIR NO. C-7 RX STAIR NO. C-5 RCP
- 1 STEAM GEN #1 STEAM GEN #4 RCP
- 4 PRZR ACCUMULATOR LADDERS PENETRATION AREA ROD POSITION INDICATOR ROOM ELEVATOR ELEVATION 860'-0" ATTACHMENT 8.B l
PAGE 2 OF 5 CONTAINMENT FLOOR PLANS NOTE:
The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.
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ELEVATOR LADDER PARTIAL PLAN AT ELEVATION 849'-0
PARTIAL PLAN AT ELEVATION 842'-0
STAIR NO. C-4 PARTIAL PLAN AT ELEVATION 842'-0
AND PARTIAL PLAN AT ELEVATION 849'-0
INCORE INST DRIVE RM ATTACHMENT 8.B l
PAGE 3 OF 5 CONTAINMENT FLOOR PLANS NOTE:
The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.
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ELEVATOR REGEN HX INCORE INST RM ACC
- 1 ACC
- 2 ACC
- 3 RCP #3 RCP #2 RCP #1 RCP #4 LADDER STEAM GEN #3 STEAM GEN #2 STEAM GEN #1 STEAM GEN #4 RX STAIR NO. C-4 STAIR NO. C-2 STAIR NO. C-1 ELEVATION 832'-6" ATTACHMENT 8.B l
PAGE 4 OF 5 CONTAINMENT FLOOR PLANS NOTE:
The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.
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ELEVATOR STAIR NO. C-2 STAIR NO. C-1 LADDER LADDER RECIRC SUMPS RCDT XS LTDN HX RCDT HX RX ELEVATION 808'-0
INCORE INST AREA ATTACHMENT 8.B l
PAGE 5 OF 5 CONTAINMENT FLOOR PLANS NOTE:
The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.
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ATTACHMENT 8.C l
PAGE 1 OF 2 l
l GENERAL AIRLOCK CAUTIONARY AND AWARENESS CRITERIA l
[L]
l l
1.0 CONTACT Operations with any questions or concerns regarding door operations l
l 2.0 IF door operator is starting the entry, THEN contact Control Room prior to opening the l
airlock.
l l
3.0 OPERATIONS is always in charge when in the area.
l l
4.0 WHEN you are operating the airlock, YOU assume responsibility for its operation.
l l
5.0 WHEN operating the airlock, VERIFY correct button to be pressed. Once indicator light l
is lit on the control panel, NEVER press any button other than one of the buttons below l
that indicator light. (PAL Only) l l
6.0 IF there are other personnel in the area, THEN always announce action to be taken.
l l
7.0 DO NOT close the interior door from the exterior. IF this type of action is needed, THEN l
Operations should be called because something is wrong.
l l
8.0 Stop buttons will stop any door at any time. Use them as needed. The stop button may l
be used on every cycle of the door. (PAL Only) l l
9.0 It is expected the door operator go to a stop button once operation of the door has l
started OR be within arms reach of the stop button once operation has started except l
when getting ready to pull the door closed. (PAL Only) l l
10.0 The door is designed to stop with reasonable force applied to it; the door can be stopped l
by pushing it. The direction of the door can be reversed if pushed even harder, it does l
not damage the door. WHEN the door needs to be stopped, the normal action should be l
to use the stop button. (PAL Only) l l
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ATTACHMENT 8.C l
PAGE 2 OF 2 l
l GENERAL AIRLOCK CAUTIONARY AND AWARENESS CRITERIA l
l l
11.0 Once a door has started to close OR open, the correct way to stop the sequence is to l
use a stop button. In order to re-open a door that is closing or is partially closed, USE l
the stop button first. (PAL Only) l l
12.0 DO NOT tolerate horse-play around the airlock. (Zero tolerance) l l
13.0 Watch all personnel entering AND exiting airlock to ensure there is no contact with l
locking ring or sealing surfaces. The seal is greased with silicon grease. The locking l
tabs and ring are greased with petroleum grease. IF petroleum grease is transferred to l
sealing surface, THEN it will dissolve the seal. Always have at least one paper towel to l
do immediate clean up if this occurs.
l l
14.0 DO NOT allow the airlock to be over-filled.
l l
15.0 Watch seals for possible pull out the first time the doors are opened. Occasionally, l
when PAL has been closed for several weeks in a row, seal will pull out of the channel l
when door is opened the first time. (PAL Only) l l
16.0 The hydraulic fluid in the airlock is a solvent that will go right through your skin. Contact l
with eyes, nose and mouth is extremely hazardous and must be reported to Safety even l
if it is only a drop.
l l
IF you get a small amount on clothing, THEN contact someone to take your place.
l Change clothes AND wash area that made contact with the skin. DO NOT ignore it.
l l
17.0 Verify the PAL OR EAL seal and sealing surfaces are clear of any obvious foreign l
material AND debris when closing the doors during Containment entries.
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(For Information Only)
Record of Changes Page 1 Rev/PCN Affected Pages Description of Change 12 / 4 6, 8, 12, 15, 24 Incorporated Foreign Material Exclusion (FME) into the procedure by adding the appropriate definitions, responsibilities, and instructions. This change is in response to the changes made to STA-625. The change heightens the awareness of personnel entering Containment during Modes 1-4 by making it an FME Zone.
12 / 5 3, 12 Added step to exempt figures/attachments/forms from SORC review as per STA-202, 6.2.10. Added step to require compensatory fall protection measures be addressed if accessing S/G Loop Room platforms. Ref: ACTN-MAN-2007-001267-03.
12 / 6 6, 6.1, 7, 8, 9, 10, 14 In support of continuous improvement, the Containment Pre-Entry meeting will be scheduled for non-routine, complex activities or as requested by RP, Operations, or any other organization involved in the entry. For routine maintenance and activities that are scheduled in the POD, this meeting is considered optional.
12/7 4, 25, 26, 27, 28, 29 Removed room numbers from Attachment 8.1.2, Containment Floor Plans.
Provided additional detail in note for each floor plan that plans are provided for information only and A1-0413 series drawings should be referenced for specific details, room numbers, etc. this PCN in response to SMF-2009-002168. This PCN is considered an allowed editorial change per STA-202 ATT. 8.F SECTION 3.0.
12 / 8 5, 18 Editorial PCN adding STA-601 as a Developmental Reference, and adding a clarifying note to Step 6.2.8 stating that a signature on STA-620-1 authorizing Containment Entry does not satisfy the requirement to notify the Control Room immediately prior to entry by the RWO. Ref: AI-CR-2009-005381-00-9.
12 / 9 3, 4 Editorial change approved by SORC (Mtg. #10-003) to add reference to STA-919 and to add a step relative to the implementation of safety-security interface requirements (CR-2010-000434).
13 / 0 All Incorporated previous PCNs, added levels of use, made minor administrative changes. Added requirement for last person exiting Containment to verify PAL/EAL seals and surfaces are clear of foreign material/debris prior to closing the doors. Added new attachment containing general airlock cautionary and awareness criteria. (Ref: AI-CR-2011-010210-9/10)
CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d CPNPP NRC 2012 JPM RA4 Procedure 1 Rev d