ML15245A561
| ML15245A561 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/21/2015 |
| From: | Division of Reactor Safety II |
| To: | Progress Energy Carolinas |
| References | |
| Download: ML15245A561 (143) | |
Text
Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HB ROBINSON Task No.: 01001101601 Task
Title:
Perform Shutdown Margin JPM No.: 2011 NRC JPM Admin Calculation lAW FMP-012 RO-SRO Al-i K/A
Reference:
G2.i.37 (4.3/4.6)
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 was operating at 100% RTP steady state when Control Rod M-08 dropped into the core.
- AOP-OOi, Malfunction of Reactor Control System, was implemented and the crew has reduced reactor power.
- Current plant conditions are as follows:
- Reactor Power is 68%
- RCS Tave is 565 degrees F
- RCS Boron Concentration is 138 ppm sampled today at time now.
- Control Bank D demand position is 153 steps
- Remaining Control and Shutdown Banks demand position is 225 steps Task Standard: Calculate that sufficient shutdown margin exists under the present plant conditions.
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet Required Materials: FMP-OO1, Core Operating Limits Report (COLR)
FMP-012, Manual Determination of Shutdown Margin Boron Concentration Station Curve Book, Section 1 Cycle Data Calculator Straight Edge General
References:
FMP-OO1 FMP-012 Station Curve Book, Section 1 Cycle Data Handouts: FMP-OO1 FMP-012 ERFIS Printout GD ROD LOG Station Curve Book, Section 1 Cycle Data Calculator Straight Edge Initiating Cue: You have been assigned by the CR5 to calculate the present shutdown margin lAW FMP-012.
Time Critical Task: NO Validation Time: 60 minutes 2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet SIMULATOR SETUP N/A 2011 NRC JPM Admin RO-SRO Al-I NUREG 1021, Revision 9, Supplement 1
Appendix C Page 4 of 13 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
General NOTE: FMP-012 Procedure Steps 6.1.1 through 6.1.14 describe the actions to be taken within the steps of Attachment 7.1.
Performance Step: I Complete Section I of Attachment 7.1 Standard: Candidate completes the information needed for Section I:
Date I Time conditions recorded [Todays Date and Time]
Reactor Power [68] % Full Power Demand D Bank Position [153] steps Demand C Bank Position [225] steps Record RPI indication for Control Bank D [All rods except for M-08 should be recorded from printout at 153 steps (within 7.5 inches of bank average)]
Record RPI indication for Control Bank C [All rods should be recorded from printout at 225 steps (within 15 inches of demand position)]
All of the values in BOLD in the standard above should be Examiners NOTE*
recorded by the candidate (See Key)
Comment:
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 13 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 2 Complete Section II of Attachment 7.1 Based on the Power Level and using Curve Book, Table 1.9 or Curve 1.9, the RIL for Control Bank D is and Control Bank C is Standard: Candidate completes the information needed for Section II:
Control Bank D is [100] + 2.5 steps Control Bank C is [225] +/- 2.5 steps Examiners NOTE: Curve 1.9B should be used for MOL to EOL.
Comment:
q Performance Step: 3 Complete Section III of Attachment 7.1 Are the control rods in Control Banks C and D above the RIL, CIRCLE ONE:
YES Adequate SDM exists and no further verification is warranted, and N/A Sections IV through XI, Attachment 7.1
[NO] Further verification of SDM is warranted, complete Sections IV through Xl, Attachment 7.1 Standard: Candidate determines that the Control Bank D rods are NOT above the Rod Insertion Limits and answers NO.
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 6 of 13 Form ES-C-I PERFORMANCE INFORMATION Performance Step: 4 Complete Section IV of Attachment 7.1 Current Cycle exposure (from Control Room Status Board)
MWD/MTU Reactor Power Level Tavg F Latest Available RCS Boron Concentration Sample Time Date Standard: Current Cycle exposure (from Control Room Status Board) 1156971 +/- 250 MWD/MTU Reactor Power Level [68] %
Tavg [565] degrees F Latest Available RCS Boron Concentration [138] ppm Sample Time [NOW], Date [TODAY]
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-I NUREG 1021, Revision 9, Supplement 1
Appendix C Page 7 of 13 Form ES-C-i PERFORMANCE INFORMATION q Performance Step: 5 Complete Section V of Attachment 7.1 Based on the Latest Available RCS Boron Concentration, Power Level, and exposure and using Curve Book, Table 1.3 or Curve 1.3, the Total Power Defect is pcm.
Standard: Candidate determines that Total Power Defect is [1855.5] +25,
-15 pcm.
Examiners NOTE: Candidate should use Curve 1.3C or Table 1.3C based on cycle exposure time (EOL). Value read from Curve 1.3C is 1850 pcm and extrapolated from Table 1.3C is 1855.5 pcm as follows:
50% power, 0 ppm, 1437 pcm 50% power, 200 ppm, 1398 pcm 75% power, 0 ppm, 2077 pcm 75% power, 200 ppm, 2007 pcm 75% 50% 0 ppm difference is 640 pcm I 25%
- = 25.6 pcm I %
25.6 pcm 1% X 18% = 460.8 pcm + 1437 pcm = 1897.8 pcm 68% power 75% 50 % 200 ppm difference is 309 pcm I 25%
- = 24.36 pcm I %
24.36 pcm I % X 18% = 438.5 pcm + 1398 pcm 1836.5 pcm 68% power RCS boron given was 138 ppm 1897.8 pcm 1836.5 pcm = 61.3 pcm I 200 ppm = 0.3065 pcm I ppm 0.3065 pcm I ppm X 138 ppm = 42.3 pcm 1897.8 pcm 42.3 pcm = 1855.5 pcm Comment:
2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 8 of 13 Form ES-C-i PERFORMANCE INFORMATION Procedure NOTE: Data entered into the table below will be based on the lowest indicated RPI in the bank. An untrippable rod should not be counted as a misaligned rod.
q Performance Step: 6 Complete Section VI of Attachment 7.1 Determine the RPI position of the lowest rod in Control Banks D and C and enter into the table below. If a misaligned rod(s) is in CBB, CBA, SBB, SBA, or if the bank(s) are below RIL, then determine the RPI position of the lowest rod(s) within that bank and enter into the table below. N/A columns that are not applicable. Using Table 1.15 of the Station Curve Book, determine the integral bank worth of the inserted/misaligned rod(s) by filling out the table below:
Standard: Candidate determines that Control Bank D has a rod that indicates [0] steps and records [850] pcm from Table 1.15 of the Station Curve Book. This results in a Total Rod Worth of [850]
+0, -1 pcm.
Examiners NOTE: Table 1.15, Inserted I Misaligned Bank Worths (pcm) for Control Bank D.
GD ROD LOG was provided to the candidate with the recorded position for Control Rod M-08 at 1.89 inches.
0 steps, 0 inches = 850 pcm 9 steps, 6 inches = 849 pcm Due to the information provided with the control rod position at 1.89 inches, the tolerance of +0, -1 pcm was given.
Comment:
2011 NRC JPM Admin RO-SRO Al-I NUREG 1021, Revision 9, Supplement 1
Appendix C Page 9 of 13 Form ES-C-i PERFORMANCE INFORMATION q Performance Step: 7 Complete Section VII of Attachment 7.1 Based on the current cycle exposure and using Table 1.15 of the Station Curve Book, the Total Rod Worth is pcm.
Standard: Candidate determines from Table 1.15 of the Station Curve Book that the total rod worth is [5868.5] +/- 3 pcm.
Examiners NOTE: From Table 1.15, Current Cycle Exposure was provided from the Unit 2 Status Board as 15697 MWDIMTU.
15000 MWDIMTU = 5881 pcm 16000 MWDIMTU = 5863 pcm 5881 pcm 5863 pcm = 18 pcm difference 69.7% X 18 = 12.5 pcm 5881 pcm 12.5 = 5868.5 pcm Comment:
q Performance Step: 8 Complete Section VIII of Attachment 7.1 Number of inoperable/untrippable control rods If there are inoperable/untrippable rods then obtain the Most Reactive Rod Worth from Station Curve Book Table 1.15 and calculate the worth by performing the following, otherwise N/A.
- of rods X Most Reactive Rod Worth (pcm) =
Inop./Untrip. Rod Worth (pcm)
Standard: Candidate determines that the number of inoperable rods is [0],
thus this step is [N!A]
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 10 of 13 Form ES-C-I PERFORMANCE INFORMATION J Performance Step: 9 Complete Section IX of Attachment 7.1 The available SDM is calculated by:
Total Rod Worth (Step VII) Inserted/Misaligned Worth (Step VI) Power Defect Worth (Step V) Inop/Untrip Rod Worth (Step VIII) = Available Shutdown Margin Standard: Total Rod Worth (Step VII) = [5868.5] +/- 3 icm Inserted/Misaligned Worth (Step VI) = [850] +0, -1 pcm Power Defect Worth (Step V) = [1855.5] + 25, -15 pcm Inop/Untrip Rod Worth (Step VIII) = [0] pcm Available Shutdown Margin [3141 to 3176] pcm Examiners NOTE:
Comment:
J Performance Step: 10 Complete Section X of Attachment 7.1 Based on the Latest Available Boron Concentration and Figure 5.0 of the COLR (FMP-001), the required SDM is X 1000 pcm/% pcm.
Standard: Candidate determines from FMP-001 Figure 5.0 that required SDM is [1.60]% (+/- 0.05%) and calculates [1600] pcm. This used an RCS boron concentration of 138 ppm and read Figure 5.0 for Mode 1 operation.
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-I NUREG 1021 Revision 9, Supplement 1
Appendix C Page 1 1 of 13 Form ES-C-i PERFORMANCE INFORMATION
.1 Performance Step: 11 Complete Section XI of Attachment 7.1 Is the available SDM greater than the required SDM?
CIRCLE ONE
[YES] Adequate Shutdown Margin Exists NO Adequate Shutdown Margin does not exist Standard: Candidate compares the [3141 to 3176] pcm available shutdown margin to the [1600 to 1650] pcm required shutdown margin and determines that [YES Adequate Shutdown Margin Exists].
Examiners NOTE:
Comment:
END OF TASK Termination Cue: Upon completion of FMP-012, Attachment 7.1, the JPM is complete.
STOP TIME:
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 12 of 13 Form ES-C-I VERIFICATION OF COMPLETION Job Performance Measure No: 2011 NRC JPM Admin RO-SRO Al-I Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
ATTACHMENT 7.1 Page 1 of 3 SHUTDOWN MARGIN MODES 1,2 DATA FORM Current reactor critical conditions:
- 1. Date/Time conditions recorded
- 2. Reactor Power % Full Power
- 3. Demand D Bank Position steps
- 4. Demand C Bank Position a steps
- 5. Record RPI indication for Control Bank D Rod H-04 D-08 H-12 M-08 H-08 Steps /3 /s &
- 6. Record RPI indication for Control Bank C Rod K-04 F-04 D-06 D-1O F-12 K-12 M-1O M-06 Steps 2,i 22S II. Based on the Power Level and using Curve Book, Table 1.9 or Curve 1.9, the RIL for Control Bank D is Ic50 steps Control Bank C is steps Ill. Are the control rods in Control Banks C and D above the RIL, CIRCLE ONE YES Adequate SDM exists and no further verification is warranted, and N/A Sections IV through Xl, Attachment 7.1.
NO Further verification of SDM is warranted, complete Sections IV through Xl, Attachment 7.1.
FMP-012 Rev. 27 Page 22 of 29
ATTACHMENT 7.1 Page 2 of 3 SHUTDOWN MARGIN MODES 1,2 DATA FORM IV. Record the following
- 1. Current Cycle exposure (from Control Room Status Board) is 9 7
- 2. Reactor Power Level %
- 3. Tavg degrees F
- 4. Latest Available RCS Boron Concentration /3 ppm Sample Time 14), Date V. Based on the Latest Available RCS Boron Concentration, Power Level, and exposur nd usin Curve Book, Table 1.34 or Curve 1.3 the To I Pow r Defect is tjpcm NOTE: Data entered into the table below will be based on the lowest indicated RPI in the bank. An untrippable rod should not be counted as a misaligned rod.
VI. Determine the RPI position of the lowest rod in Control Banks D and C and enter into the table below, If a misaligned rod(s) is in CBB, CBA, SBB, SBA, or if the bank(s) are below RIL, then determine the RPI position of the lowest rod(s) within that bank and enter into the table below. N/A columns that are not applicable.
Using Table 1.15 of the Station Curve Book, determine the integral bank worth of the inserted/misaligned rod(s) by filling out the table below:
CBD CBC CBB CBA SBB SBA Total Worth Lowest Indicated RPI [steps]
O WORTH [pcm]
VII. Based on the current cycle exposureppd using Table 1.15 of the Station Curve Book, the Total Rod Worth is pcm FMP-012 Rev. 27 Page 23 of 29
ATTACHMENT 7.1 Page 3 of 3 SHUTDOWN MARGIN MODES 1, 2 DATA FORM VIII. Number of inoperable/untrippable control rods If there are inoperable/untrippable rods then obtain the Most Reactive Rod Worth from Station Curve Book Table 1.15 and calculate the worth by performing the followipg, otherwise N/A.
A/i
- 1(. iVfi7 pcm = (i pcm
- of rods Most Reactive lnop./Untrip.
Rod Worth Rod Worth IX. The available SDM is calculated by:
- 7c- =c/pcm Total Rod lnserted/ Power Inop/Untrip Available Worth Misaligned Defect Rod Worth Shutdown Worth Worth Margin (Step VII) (Step VI) (Step V) (Step VIII)
X. Based on the Latest Available boro co centration and Figure .O of the COLR (FMP-0O1), the required SDM is
CIRCLE ONE Adequate Shutdown Margin Exists NO Adequate Shutdown Margin does not exist; perform the following:
- 1) Based on the current exposure, Tavg, and latest available Boron Concentration, and yi&rg Curve Book, Table 1.5 or Curve 1.5, the Boron Worth is (-) AJ/A pcm/ppm
- k) /
Required SDM pcm)/ (-) IA Boron Worth pcm/ppm =
Amount to borate (Step IX) (Step X) (Step Xl.1)
Performed By: Date:_________
Approved By: Date:__________
SSO or CRSS or Supervisor - Reactor Systems FMP-012 Rev. 27 Page 24 of 29
Appendix C Page 13 of 13 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
- Plant was operating at 100% RTP steady state when Control Rod M-08 dropped into the core.
- AOP-00i, Malfunction of Reactor Control System, was implemented and the crew has reduced reactor power.
- Current plant conditions are as follows:
- Reactor Power is 68%
- RCS Tave is 565 degrees F
- RCS Boron Concentration is 138 ppm sampled today at time now.
- Control Bank D demand position is 153 steps
- Remaining Control and Shutdown Banks demand position is 225 steps INITIATING CUE: You have been assigned by the CRS to calculate the present shutdown margin lAW FMP-012.
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HB ROBINSON Task No.: 01002100401 Task
Title:
Calculate RCS Subcooling lAW OP- JPM No.: 2011 NRC JPM Admin 307, INADEQUATE CORE RO Ai-2 COOLING MONITOR K/A
Reference:
G2.i.25 (3.9)
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:
- Unit 2 is at 100% RTP The Inadequate Core Cooling Monitor is out-of-service.
Task Standard: Subcooling margin is calculated within the specified range.
Required Materials: Steam Tables Calculator OP-307, Section 8.4 General
References:
OP-307, INADEQUATE CORE COOLING MONITOR, Rev. 13 Handout: Steam Tables Calculator OP-307, Section 8.4 Initiating Cue: The CRS has directed you to determine the subcooling margin lAW OP 307, INADEQUATE CORE COOLING MONITOR. Assume that all procedure PREREQUISITES are met. A list of relevant readings is attached to your JPM CUE SHEET.
2011 NRC JPM Admin RO Ai-2 NUREG 1021, Revision 9, Supplement 1
Appendbc C Job Performance Measure Form ESCel Worksheet lime Critical Tat NO VaUdatlon lime: 12 mlnutee 2011 NRC JPM Admln RO A1-2 NUREG 1021, RevisIon 9, Supplement I
Appendix C Job Performance Measure Form ES-C-i Worksheet SIMULATOR SETUP N/A 2011 NRC JPMAdmin ROA1-2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
Performance Step: I This revision has been verified to be the latest revision available.
(Step 8.4.1.1)
Standard: Verifies the current revision number in the procedure data base.
Examiners NOTE:
Examiners CUE: Assume that the procedure provided is the latest revision.
Comment:
Performance Step: 2 Determine primary pressure using the lowest valid pressure indication. (Step 8.4.1.2)
Standard: Selects and logs PT-455 reading: 2229 psig Examiners NOTE:
Comment:
q Performance Step: 3 Convert pressure to absolute by adding 14.7 psi to value determined in Step 8.4.1.2. (Step 8.4.1.3)
Standard: 2229 +14.7 = 2243.7 psia Examiners NOTE:
Comment:
2011 NRC JPMAdmin ROA1-2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 9 Form ES-C-i PERFORMANCE INFORMATION q Performance Step: 4 Enter, from the Saturated Steam Tables, the saturation temperature corresponding to the pressure shown in Step 8.4.i.3 to determine the corresponding temperature. (Step 8.4.1.4)
Standard: Interpolates from Steam Tables and logs:
43.7/100 x (655.89 649.45) + 649.45 652.26 °F
[ 650 °F but 655 °F]
Examiners NOTE:
Comment:
Performance Step: 5 Determine primary temperature using the highest valid core exit thermocouple temperature indication. (Step 8.4.1.5)
Standard: Selects and logs 609 °F Examiners NOTE:
Comment:
J Performance Step: 6 Subtract the temperature of Step 8.4.1.5 from the temperature of Step 8.4.1.4 to determine the margin to saturation in °F. (Step 8.4.1.6)
Standard: [ 650 °F but 655 °FJ 609 °F
- = [ 41 °F but 46 °F]
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO A1-2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 6 of 9 Form ES-C-I PERFORMANCE INFORMATION Performance Step: 7 Completes Performed By section. (Section 8.4 completion)
Standard: Initials block, prints name, and logs the current date.
Examiners NOTE:
Comment:
END OF TASK Termination Cue: When the candidate provides the completed OP-307, Section 8.4 to the Examiner: Evaluation of this JPM is complete.
STOP TIME:
2011 NRC JPM Admin ROAI-2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 7 of 9 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM Admin RO A1-2 Examinees Name:
Date Performed:
Facility Evaluator:
Numberof Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM Admin RO Ai-2 NUREG 1021, Revision 9, Supplement i
CONTINUOUS USE Section 8.4 Pagelofi 8.4 INFREQUENT OPERATIONS INJI 8.4.1 Manual Calculation of Margin to Saturation
- 1. This revision has been verified to be the latest revision available.
Name ( rint) Initial Signature ( Date /
- 2. Determine primary pressure using the lowest vJjd pressure indication. 7 psig 2Z
- 3. Convert pressure to absolute by addin14.7 si to value determined in Step 8.4.1.2. 77psia
- 4. Enter, from the Saturated Steam Tables, the saturation temperature corresponding to the pressure shown in Step 8.4.1.3 to determine the correspondn temperature. LZ4OF
- 5. Determine primary temperature using the highest valid core exit thermocouple temperature indican.
°F
- 6. Subtract the temperature of Step 8.4.1.5 from the temperature of Step 8.4.1.4 to determine tIe marg)n to saturation in °F. ,
I Is me(Print) Date Performed By:
Approved By:
Unit 2 Superintendent Shift Operations
- Date OP-307 I Rev. 13 I Page 15 of 18 I
Appendix C Page 8 of 9 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
- Unit 2 is at 100% RTP
- The Inadequate Core Cooling Monitor is out-of-service.
INITIATING CUE: The CRS has directed you to determine the subcooling margin lAW OP-307, INADEQUATE CORE COOLING MONITOR.
Assume that all procedure PREREQUISITES are met. A list of relevant readings is attached to your JPM CUE SHEET.
2011 NRC JPM Admin RO Al -2 NUREG 1021, Revision 9, Supplement I
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CONTINUOUS USE Section 8.4 Page 1 of 1 8.4 INFREQUENT OPERATIONS JlT 8.4.1 Manual Calculation of Margin to Saturation
- 1. This revision has been verified to be the latest revision available.
Name (Print) Initial Signature Date
- 2. Determine primary pressure using the lowest valid pressure indication. psig
- 3. Convert pressure to absolute by adding 14.7 psi to value determined in Step 8.4.1.2. psia
- 4. Enter, from the Saturated Steam Tables, the saturation temperature corresponding to the pressure shown in Step 8.4.1.3 to determine the corresponding temperature.
- 5. Determine primary temperature using the highest valid core exit thermocouple temperature indication.
°F
- 6. Subtract the temperature of Step 8.4.1.5 from the temperature of Step 8.4.1.4 to determine the margin to saturation in °F.
Initials Name(Print) Date Performed By:
Approved By:
Unit 2 - Superintendent Shift Operations Date OP-307 Rev. 13 Page l5of 18
Appendix C Page 1 of 6 Form ES-C-i PERFORMANCE INFORMATION Facility: HB ROBINSON Task No.:
Task
Title:
Determine Proper Equipment JPM No.: 2011 NRC JPM Admin RO Boundaries A2 K/A
Reference:
G2.2.41 (3.5/3.9)
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 plant is in Mode 1 at 100% RTP.
- Charging Pump A suction relief valve CVC-2080 has failed open.
- The operating crew has entered AOP-016, Excessive Primary Plant Leakage, to control the plant.
Task Standard: Determine the pump boundaries and power supply necessary to isolate the leakage from relief valve CVC-2080.
Required Materials: P&lD 5379-685 Sheet 2 of 3 EDP-002 General
References:
P&ID 5379-685 Sheet 2 of 3 EDP-002 Handouts: P&ID 5379-685 Sheet 2 of 3 EDP-002 Initiating Cue: Using the provided references only, identify the pump boundary valves and motor breaker to expedite the pump isolation and termination of the leakage.
Time Critical Task: NO Validation Time: 30 minutes
Appendix C Page 2 of 6 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
START TIME:
Examiners NOTE: This JPM consists of identifying the boundaries necessary to isolate the leakage path from Charging Pump A suction relief valve CVC-2080. The sequence of the component isolation is NOT required for the performance of this JPM.
Performance Step: I Review P&lDs to determine pump boundary valves.
Standard: Candidate will use the necessary plant drawing(s) to identify the pump boundary valves.
Examiners NOTE: P&ID 5379-685 Sheet 2 of 3 will be used to identify the pump boundary valves.
Comment:
Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 2 Identify the pump boundary valves.
Standard: The following valves are required to be verified in the selected positions to ensure that the leak flow path is isolated:
- CVC-270, Charging Pump A Suction - CLOSED
- CVC-290, Charging Pump A to Charging Line CLOSED -
- CVC-291, Charging Pump A to Seal Injection CLOSED-Not required for credit. Additional isolation valves that can be included are as follows:
- CVC-465, Charging Pump A Suction Vent CLOSED -
- CVC-275F, Charging Pump A Suction Line Vent LOCKED CLOSED
- CVC-280C, Charging Pump A Drain CLOSED-
- CVC-400A, Charging Pump A Leakage Isolation OPEN -
- CVC-277C, Charging Pump A Recirc Root LOCKED CLOSED
- CVC-466, Charging Pump A Suction Stabilizer Drain -
OPEN Examiners NOTE: Vent and drains are NOT required to be included.
Comment:
Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 3 Determine the power supply to Charging Pump A.
Standard: Candidate determines that Charging Pump A power supply is breaker 52/34B RACKED OUT.
Not required for credit. Additional breakers I switches that can be included are as follows:
- RTGB Control switch for Charging Pump A CAPPED
- Power Panel 37 Circuit 2, Charging Pump A Suction Stabilizer Heater Breaker OPEN Examiners NOTE: Charging Pump A power supply is located in EDP-002, Section 7.0, 480V Bus DS, Breaker 52!34B.
Power supply is also available on the RTGB on the pump control switch.
Examiners CUE: Provide copy of EDP-002 if requested by the candidate.
Comment:
END OF TASK Terminating Cue: Charging Pump A valve boundaries and power supply have been identified as directed.
STOP TIME:
Appendix C Page 5 of 6 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM Admin RO A2 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
Appendix C Page 6 of 6 Form ES-C-i JPM CUE SHEET.
INITIAL CONDITIONS:
- The plant is in Mode 1 at 100% RTP.
- Charging Pump A suction relief valve CVC-2080 has failed open.
- The operating crew has entered AOP-016, Excessive Primary Plant Leakage, to control the plant.
INITIATING CUE: Using the provided references only, identify the pump boundary valves and motor breaker to expedite the pump isolation and termination of the leakage.
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: HB ROBINSON Task No.:
Task
Title:
Determine the appropriate Radiation JPM No.: 2011 NRC JPM RO-SRO Work Permit for the assigned task and Admin A3 apply any limitations from the RWP K/A
Reference:
G2.3.7 (3.5/3.6)
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:
- Fuel movement in the Spent Fuel Pool has been ongoing for several weeks in support of Dry Fuel Storage campaign.
- The Spent Fuel Pit Filter has exceeded the differential pressure limit of 25 psid.
- Estimated dose for the Operations task is 29 mR.
Task Standard: Determine which RWP meets the criteria for allowing the valve operation and dose limits for the task assigned and identify any specific restrictions.
Required Materials: RWPs 5498, 5499, 5519 and 6183.
SFP Filter area survey map.
General
References:
RWPs 5498, 5499, 5519 and 6183.
SFP Filter area survey map.
Handouts: RWP5 5498, 5499, 5519 and 6183.
SFP Filter area survey map.
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet Initiating Cue: You have been assigned to hang the clearance and vent and drain the Spent Fuel Pit Filter. Select the appropriate RWP for supporting the task and identify specific restrictions for the task.
Time Critical Task: NO Validation Time: 20 minutes SIMULATOR SETUP N/A 2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
START TIME:_______
- Performance Step: I Determine the dose limits from the SFP Filter area survey map and select the appropriate RWP for the task.
Standard: Candidate determines the dose at the filter housing will require the use of RWP #5519. RWP #5519 states that continuous RC coverage is required.
Examiners NOTE: 1000 mRlhr reading at 30 cm at the filter housing and the posting as a Locked High Radiation Area (LHRA) requires the use of RWP #5519 based on the ED Dose Rate Alarm setpoint.
RWPs #5498 and 5499 state that no entry allowed for> 1000 mR/hr.
RWP #6183 states that ED Dose Alarm is 20 mRem. The initial conditions state that the estimated dose for the Operations task is 29 mR.
Comment:
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 4 of 6 Form ES-C-I PERFORMANCE INFORMATION
- Performance Step: 2 Determine any additional restrictions from the RWP and survey map.
Standard: Candidate determines that a Hot Particle Area exists and additional protective clothing is required.
Examiners NOTE: Hot Particle Area requires full PCs with hood, double rubber gloves and double rubber shoecovers.
Faceshield required when hot particles > 2.0 E6 dpm are present (Noted on survey map as being greater than limit).
SOER 2001-1 pre-job briefing is required.
Comment:
END OF TASK Termination Cue: When the candidate has determined the RWP restrictions from the survey map, the evaluation of this JPM is complete.
STOP TIME:
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 6 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM RO-SRO Admin A3 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 6 of 6 Form ES-C1 JPM CUE SHEET INITIAL CONDITIONS:
- Fuel movement in the Spent Fuel Pool has been ongoing for several weeks in support of Dry Fuel Storage campaign.
- The Spent Fuel Pit Filter has exceeded the differential pressure limit of 25 psid.
- Estimated dose for the Operations task is 29 mR.
Initiating Cue: You have been assigned to hang the clearance and vent and drain the Spent Fuel Pit Filter. Select the appropriate RWP for supporting the task and identify specific restrictions for the task.
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
PASSPORT - TOTAL EXPOSURE SYSTEM piiiiii I111111111111111 1111111111 11111 11111 11111 11111 11111 11111 111111111111111 11111 1111111111 11111 11111 11111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00005498 01 Page : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES - ED SETPOINTS 10/8/120 Type : MR Status: ACTIVE Date : 08/08/2010 12:42 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 08/08/2010 12:42 By: MANNIPO1 MANNING PAUL W Approved Date : 08/08/2010 12:42 By: RITCHW RITCHIE WILLI T Radiological Conditions ED Time Alarm: 840 (in Minutes)
Administrative Dose Limit: 10 (mrem)
ED Dose Alarm: 8 (mrem) ED Dose Rate Alarm: 120 (mrem/hr)
Radiological Hazards Radiological Hazard --Distance--I I Reading I SEE SPECIAL INSTRUCT N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) Multi-Pack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO Hold Points and Special Instructions Nbr Hold Point Description 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VHRA - VERY HIGH RADIATION AREA 10 CV WHEN THE REACTOR IS CRITICAL (EXCEPT FOR FIRE
PASSPORT - TOTAL EXPOSURE SYSTEM I.}DII.rrI3N I lilt liii!11111 11111 III!! 11111liii!lull liii! 11111111111111111111liii!11111 1111111111 liii!11111 11111 11111 III At.ARA Task port ID : TIPH900 RWP Number: 00005498 01 Page : 2 Facility : RNP 10 BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVES WORK 10 IN THE SFP, IE. MOVING FUEL OR COMPONENTS IN SFP.
10 NO ENTRY INTO AREAS GREATER T{ANOR EQUAL TO 10 1000 MREM/HR.
Nbr Special Instructions 5 WORK DESCRIPTION ********************
5 OPERATIONS ACTIVITIES 5 NO SPENT FUEL POOL WORK ON THIS RWP.
5 5
10 l.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM-TRX DOSIMETERS.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7. PAM/TRx REQUIRED FOR WORK IN HRAS 10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2.NO ENTRY IN AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20 30 *****HOT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH HPA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING 30 W/HOOD AND DOUBLE RUBBER GLOVES AND SHOECOVERS.
30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
?ASSPORT - TOTAL EXPOSURE SYSTEM
/3I1( PIR11Ir I 1111111111 11111 1111111111 11111 11111 11111 11111 1111111111111111111111111111111111111111111111111111111111111111 ALARA Task iport ID : TIPH900 RWP Number: 00005498 01 gage : 3 Facility : RNP 30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
30 6.A PRE-JOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 E6 DPM 30 ARE PRESENT.
30 40 **** CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) ***
40 40 l.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.OREX DELUXE WITH HOOD REQUIRED FOR 40 WET WORK AND ADDITIONAL DRESS CONTROLS 40 MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE, 40 IF NEEDED TO CONTAIN LIQUIDS.
40 50 ***********CONTAMINATED AREA ENTRIES*************
50 50 l.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK 50 OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.OREX DELUXE WITH HOOD REQUIRED FOR WET WORK 50 AND ADDITIONAL DRESS CONTROLS MAY BE REQUIRED 50 BASED ON RC INSTRUCTIONS.
50 4.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 60 ********FIRE BRIGADE ENTRY INTO CV**********
60 ***********WITH REACTOR CRITICAL*************
60 60 l.PERMISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 60 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 60 INTO THE CV WITH THE REACTOR CRITICAL.
60 2.CONTINUOUS RC COVERAGE REQUIRED.
60 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 60 ENTRY IS COMPLETE).
60 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND 60 UTILIZING TURNOUT GEAR.
60 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 60 FIRE EQUIPMENT CABINET IN THE RCA.
60 6.VERIFY THE ALARMING DOSIMETER IS ON.
60 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 60 8.ALARM SETPOINTS: DOSE ALARM 750 MREM
PASSORT - TOTAL EXPOSURE SYSTEM IiIIA.1IorT \:JoIIc 1I]..1I1 I liii11111 11111 111111111111111 11111 11111 11111111111111111111 1111111111111111111111111111111111111111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00005498 01
?age : 4 Facility : RNP 60 DOSE RATE ALARM 10000 MREM/HR 60 9.NO ENTRY INTO CV SUMP WITH REACTOR CRITICAL.
60 70 ****REQUIREMENTS FOR VENTING, SAMPLING OR DRAINING****
70 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
70 70 1.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 70 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
70
- End of Report -
PASSPORT - TOTAL EXPOSURE SYSTEM 1IA1IOr 1 P11..11II I 1111111111 11111 1111111111 11111 IIIN11111 1111111111 liii!11111 1111111111 11111 11111 11111 liii!11111 11111 1(111 liii ALARA Task port ID : TIPH900 RWP Number: 00005499 0L age : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES - ED SETPOINTS 20/16/400 Type : MR Status: ACTIVE Date : 08/08/2010 12:41 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 08/08/2010 12:41 By: MANNIPO1 MANNING PAUL W Approved Date : 08/08/2010 12:41 By: RITCHW RITCHIE WILLI T Radiological Conditions ED Time Alarm: 780 (in Minutes)
Administrative Dose Limit: 20 (mrem)
ED Dose Alarm: 16 (mrem) ED Dose Rate Alarm: 400 (mrem/hr)
Radiological Hazards Radiological Hazard I--Distance--I Reading I SEE SPECIAL INSTRUCT N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) Multi-Pack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO Hold Points and Special Instructions
- Nbr Hold Point Description 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VERA - VERY HIGH RADIATION AREA 10 CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL (EXCEPT
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT 1111111111111111 11111 1111111111 hIll111111111111111 11111 11111 1111111111 11111111111111111111 1111111111 11111liii ALARA Task
.port ID : TIPH900 RWP Number: 00005499 01 tage : 2 Facility : RNP 10 FOR FIRE BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVES WORK IN THE 10 SFP, IE. MOVEMENT OF FUEL OR COMPONENTS.
Nbr Special Instructions 5 **************
WORK DESCRIPTION 5 OPERATIONS ACTIVITIES & INSPECTIONS 5 NO SPENT FUEL POOL WORK ON THIS RWP.
5 5
10 1.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM/TRX.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7. PArvl/TRX REQUIRED FOR WORK IN HRAS 10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2. DO NOT ENTER ANY AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20 30 *****HOT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH HPA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING 30 W/HOOD AND DOUBLE RUBBER GLOVES AND RUBBER SHOECOVERS 30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
PASSPORT - TOTAL EXPOSURE SYSTEM Vo1{I( piiiiir 11111111111 11111 1111111111111111111111111 11111 11111 11111 11111 1111111111 11111 1111111111 11111 1111111111 11111 liii ALARA Task sport ID : TIPI-1900 RWP Number: 00005499 01 Page : 3 Facility : RNP 30 6.A PRE-JOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 E6 DPM 30 ARE PRESENT.
30 40 CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) ***
40 40 l.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.FULL PROTECTIVE CLOTHING W/HOOD, OREX DELUXE 40 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 40 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE, 40 IF NEEDED TO CONTAIN LIQUIDS.
40 45 ****REQUIREMENTS FOR VENTING, SAMPLING OR DRAINING****
45 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
45 45 l.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 45 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
45 50 ***********CONTJvIINATED AREA ENTRIES*************
50 50 l.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK SO OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.DOUBLE SURGEONS GLOVES MAY BE SUBSTITUTED FOR RUBBER 50 GLOVES WITH RADIATION CONTROL APPROVAL.
50 4.FULL PROTECTIVE CLOTHING, WATER RESISTANT DRESS 50 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 50 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
50 5.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 70 ********FIRE BRIGADE ENTRY INTO CV**********
70 ***********WITH REACTOR CRITICAL*************
70 70 l.PERMISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 70 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 70 INTO THE CV WITH THE REACTOR CRITICAL.
70 2.CONTINUOUS RC COVERAGE REQUIRED.
70 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 70 ENTRY IS COMPLETE) 70 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND
PASSPORT - TOTAL EXPOSURE SYSTEM VoiIC PI1{1ViI1 I IH11111 11111 1111111111 11111 11111 11111 11111 1111111111 11111 liii!11111 11111 1111111111 11111 1111111111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00005499 01 iage : 4 Facility : RNP 70 UTILIZING TURNOUT GEAR.
70 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 70 FIRE EQUIPMENT CABINET IN THE RCA.
70 6.VERIFY THE ALARMING DOSIMETER IS ON.
70 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 70 8.ALARM SETPOINTS: DOSE ALARM 750 MREM 70 DOSE RATE ALARM 10000 MREM/HR 70 9.NO ENTRY INTO CV SUMP WITH REACTOR CRITICAL.
70
- End of Report -
PASSPORT TOTAL EXPOSURE SYSTEM OI{JC p.jviir 11111111111 11111 11111 11111 11111 1111111111 11111 111111111111111111111111111111111111111111111111111111111111101 ALARA Task port ID : TIPH900 RWP Number: 00005519 01 Page : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES & INSPECTIONS Type : HR Status: ACTIVE Date : 08/08/2010 12:28 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 08/08/2010 12:28 By: MA1NIP0l MANNING PAUL W Approved Date : 08/08/2010 12:28 By: RITCHW RITCHIE WILLI T Radiological Conditions ED Time Alarm: 780 (in Minutes)
Administrative Dose Limit: 40 (mrem)
ED Dose Alarm: 32 (mrem) ED Dose Rate Alarm: 2000 (mrem/hr)
Radiological Hazards Radiological Hazard --Distance--j I Reading I SEE SPECIAL INSTRUCT N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) Multi-Pack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO Hold Points and Special Instructions Nbr Hold Point Description 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VHRA - VERY HIGH RADIATION AREA 10 CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL (EXCEPT
PASSPORT - TOTAL EXPOSURE SYSTEM i4nI4iIcr. PER]1I1 111111lUll11111 11111 liii! lUll 111111111111111hIll liii!11111 [111111111111111111lUll1111111111hIll 11111111 ALARA Task port ID : TIPH900 RWP Number: 00005519 01 Page : 2 Facility : RNP 10 FOR FIRE BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVE WORK IN THE 10 SFP, IE. MOVEMENT OF FUEL OR COMPONENTS.
Nbr Special Instructions 5 ************** WORK DESCRIPTION ********************
5 OPERATIONS ACTIVITIES & INSPECTIONS 5 NO SPENT FUEL POOL WORK ON THIS RWP.
5 5
10 l.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM-TRX DOSIMETERS.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7.TELEMETRY AND/OR PAM REQUIRED FOR WORK IN HRA S T
10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2.CONTINUOU5 RADIATION CONTROL COVERAGE REQUIRED 20 FOR ALL ENTRIES INTO AREAS GREATER THAN OR 20 EQUAL TO 1000 MREM/HR.
20 3.EXPOSURE CONTROL RC TECHNICIAN TO BE DESIGNATED WHEN 20 WORKING IN AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20 30 *****HOT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH HPA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING
PASSPORT - TOTAL EXPOSURE SYSTEM
\cR1( PE111I1 111111 liii! 11111 11111IIIN 11111 11111IIIN 11111111111111111111 II1 11111 11111 11111 liii!IIII 11111 liii! 11111 III ALARA Task port ID : TIPI-1900 RWP Number: 00005519 01 Page : 3 Facility : RNP 30 W/HOOD AND DOUBLE RUBBER GLOVES AND RUBBER SHOECOVERS 30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
30 6.A PRE-JOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 E6 DPM 30 ARE PRESENT.
30 40 **** CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) ***
40 40 l.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.FULL PROTECTIVE CLOTHING W/HOOD, OREX DELUXE 40 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 40 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE, 40 IF NEEDED TO CONTAIN LIQUIDS.
40 45 ****REQUIREMENTS FOR VENTING, SAMPLING OR DRAINING****
45 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
45 45 l.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 45 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
45 50 ***********CONTAMINATED AREA ENTRIES*************
50 50 1.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK 50 OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.DOUBLE SURGEONS GLOVES MAY BE SUBSTITUTED FOR RUBBER 50 GLOVES WITH RADIATION CONTROL APPROVAL.
50 4.FULL PROTECTIVE CLOTHING, WATER RESISTANT DRESS 50 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 50 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
50 5.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 60 ************SOER 2001-1 REQUIREMENTS*************
60 60 1.PRE-JOB BRIEFING REQUIRED.
60 2.RADIATION CONTROL SUPERVISOR & WORK GROUP SUPERVISOR 60 MUST PARTICIPATE IN PRE JOB BRIEFING.
60 3.STAYTIME AND TIME KEEPING REQUIRED WITH GENERAL
PASSPORT - TOTAL EXPOSURE SYSTEM LrI3r 7OR.i( PEi.i1Ir 4
I4..DI I 1111111111 11111 111111111111111 11111 11111 11111 11111 11111 111111111111111 11111 1111111111 11111 11111 111(1 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00005519 01 Page : 4 Facility : RNP 60 AREA DOSE RATES GREATER THAN 1000 MREM/HR.
60 4.ADHERE TO WORK INSTRUCTIONS, STAY TIMES, AND SURVEY 60 REQUIREMENTS SPECIFIED IN THE PRE-JOB BRIEFING AND 60 ON ATTACHMENT 10.5 OF HPP-500-3 THAT HAS BEEN 60 PREPARED FOR THE ACTIVITY.
60 5.CONTINUOUS RADIATION CONTROL COVERAGE REQUIRED WHEN 60 THE POTENTIAL GENERAL AREA DOSE RATES OF GREATER 60 THAN 1000 MREM/HR EXIST.
60 70 ********FIRE BRIGADE ENTRY INTO CV**********
70 ***********WITH REACTOR CRITICAL*************
70 70 l.PERMISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 70 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 70 INTO THE CV WITH THE REACTOR CRITICAL.
70 2.CONTINUOUS RC COVERAGE REQUIRED.
70 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 70 ENTRY IS COMPLETE) 70 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND 70 UTILIZING TURNOUT GEAR.
70 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 70 FIRE EQUIPMENT CABINET IN THE RCA.
70 6.VERIFY THE ALARMING DOSIMETER IS ON.
70 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 70 8.ALARM SETPOINTS: DOSE ALARM 750 MREM 70 DOSE RATE ALARM 10000 MREM/HR 70 9.NO ENTRY INTO CV SUMP WITH REACTOR CRITICAL.
70
- End of Report -
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT 111111111111111)11111 11111 thu 11111 11111 11111 11111 11111 11111 NIl 11111 11111 11111 11111 11111 11111 11111 11111 III ALARA Task port ID : TIPH900 RWP Number: 00006183 00 W001849206 24 01 Page : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES & INSPECTIONS Type : HR Status: ACTIVE Date : 02/16/2011 06:51 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 02/16/2011 06:51 By: RITCHW RITCHIE WILLI T Approved Date : 02/16/2011 06:51 By: RITCHW RITCHIE WILLI T ALARA Task ALARA Task : WO 01849206 24 01 Status: READY ALARA Desc : OPERATIONS ACTIVITIES
(
Radiological Conditions ED Time Alarm: 780 (in Minutes)
Administrative Dose Limit: 30 (mrem)
ED Dose Alarm: 20 (mrem) ED Dose Rate Alarm: 2000 (mrem/hr)
Radiological Hazards Radiological Hazard I --Distance- Reading SEE SPECIAL INSTRUCT N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) Multi-Pack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT I 111111 11111 11111 11111 11111 11111 11111 11111 11111 liii! 11111 11111 liii 11111 11111 11111 11111liii! 1111111111111111111 ALARA Task port ID : TIPH900 RWP Number: 00006183 00 w001849206 24 01 Page : 2 Facility : RNP Hold Points and Special Instructions Nbr Hold Point Description 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VHRA - VERY HIGH RADIATION AREA 10 CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL (EXCEPT 10 FOR FIRE BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVE WORK IN THE 10 SFP, IE. MOVEMENT OF FUEL OR COMPONENTS.
Nbr Special Instructions 5 WORK DESCRIPTION 5 OPERATIONS ACTIVITIES & INSPECTIONS 5 NO SPENT FUEL POOL WORK ON THIS RWP.
5 5
10 1.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM-TRX DOSIMETERS.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7.TELEMETRY AND/OR PAM REQUIRED FOR WORK IN HRAS 10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2.CONTINUOUS RADIATION CONTROL COVERAGE REQUIRED 20 FOR ALL ENTRIES INTO AREAS GREATER THAN OR 20 EQUAL TO 1000 MREM/HR.
20 3.EXPOSURE CONTROL RC TECHNICIAN TO BE DESIGNATED WHEN 20 WORKING IN AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT I 1111111111111111 1111111111111111111111111111111111111111111111111 lIhi 111111111111111111111111111111111111111 ALM.A Task port ID : TIPH900 RWP Number: 00006183 00 w001849206 24 01 Page : 3 Facility : RNP 30 *****HOT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH HPA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING 30 w/HOOD AND DOUBLE RUBBER GLOVES AND RUBBER SHOECOVERS 30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
30 6.A PRE-JOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 E6 DPM 30 ARE PRESENT.
30 40 ****
CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) k 40 40 l.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.FULL PROTECTIVE CLOTHING W/HOOD, OREX DELUXE 40 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 40 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE, 40 IF NEEDED TO CONTAIN LIQUIDS.
40 45 ****REQUIREMENTS FOR VENTING, SAMPLING OR DRAINING****
45 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
45 45 1.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 45 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
45 50 ***********CONTAMINATED AREA ENTRIES*************
50 50 1.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK 50 OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.DOUBLE SURGEONS GLOVES MAY BE SUBSTITUTED FOR RUBBER 50 GLOVES WITH RADIATION CONTROL APPROVAL.
50 4.FULL PROTECTIVE CLOTHING, WATER RESISTANT DRESS 50 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 50 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
50 5.INTEPI4ITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 60 ************SOER 20011 REQUIREMENTS*************
60
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT I 111111 11111 liii! 11111 11111 11111 11111 11111 11111 11111 11111 11111 liii 11111 11111 11111 11111 11111 11111 11111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00006183 00 W001849206 24 01 Page : 4 Facility : RNP 60 1.PRE-JOB BRIEFING REQUIRED.
60 2.RADIATION CONTROL SUPERVISOR & WORK GROUP SUPERVISOR 60 MUST PARTICIPATE IN PRE JOB BRIEFING.
60 3.STAYTIME AND TIME KEEPING REQUIRED WITH GENERAL V 60 AREA DOSE RATES GREATER THAN 1000 MREM/HR.
60 4.ADHERE TO WORK INSTRUCTIONS, STAY TIMES, AND SURVEY 60 REQUIREMENTS SPECIFIED IN THE PRE-JOB BRIEFING AND 60 ON ATTACHMENT 10.5 OF HPP-500-3 THAT HAS BEEN 60 PREPARED FOR THE ACTIVITY.
60 5.CONTINUOUS RADIATION CONTROL COVERAGE REQUIRED WHEN 60 THE POTENTIAL GENERAL AREA DOSE RATES OF GREATER 60 THAN 1000 MREM/HR EXIST.
60 70 ********FIRE BRIGADE ENTRY INTO CV**********
70 ***********WITH REACTOR CRITICAL*************
70 70 1.PERMISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 70 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 70 INTO THE CV WITH THE REACTOR CRITICAL.
70 2.CONTINUOUS RC COVERAGE REQUIRED.
70 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 70 ENTRY IS COMPLETE) 70 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND 70 UTILIZING TURNOUT GEAR.
70 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 70 FIRE EQUIPMENT CABINET IN THE RCA.
70 6.VERIFY THE ALARMING DOSIMETER IS ON.
70 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 70 8.ALARN SETPOINTS: DOSE ALARM 750 MREM 70 DOSE RATE ALARM 10000 MREM/HR 70 9.NO ENTRY INTO CV SUMP WITH REACTOR CRITICAL.
70
- End of Report -
Robinson Nuclear Plant SFPF.WMF Spent Fuel Pit Filter An
- Survey # 121410- Date/Time: 12/14/2010 074 I,LD1AI 150F1 15 LHRA/HPA controlled at I locked door LHR,1 2 HPA I I!I 10 I
1+2001 1+4001 7 8
6 1+2001 4
5 12 Comments: ****Training Use Only**** Summary of Highest Readings Pre-job Survey to Support SFP Filter Replacement.
Air Sample Taken with H809V #776982. Smears Air Samples & Wipes Several Hot Particles Detected >2 E6 DPM 3) 1UUUIJU UI-MIlUU cm /y 3
1 A/ 1) <3U youIkU I-articulate Frisker Bkg. = 60 cpm 9) 60000 DPM/100 cm2 ly NS 1) <30 %DAC Iodine Tenn.#2 MDA=79dpm 7) 34000 DPM/100 cm2 ly
- 8) 33000 DPM/100 cm2 ly Wipe 3) 100,000 CCPM
- 11) 30000 DPM/100 cm2 ly Wipe 1) 20,000 CCPM
- 1) 20000 DPM/100 cm2 ly Wipe 2) 10,000 CCPM
- 10) 19000 DPM/100 cm2 ly Wipe 4) 120 CCPM Symbol Legend (for example only) Type: Job Coverage 4) 15000 DPM/100 cm2 ly
- 2) 13000 DPM/100 cm2 ly RWP: 5910 2) 10000 DPM/100 cm2 ly at. i4S-O I i-lot Spot FicJ io.Ung Reactor Power = 100% 5) 5000 DPM/100 cm2 ly Drip Sap 20 O.n.rI Sa 6) 3000 DPM/100 cm2 ly Sro.sr SrpI. l0rA ] V21p Hot Particles Detected 13) 2000 DPM/100 cm2 ly
- 14) 1200 DPM/100 cm2 ly
- 15) 1100 DPM/100 cm2 ly Unless otherwise noted, dose rates in mremlhr.
Surveyor: Wes Brand Survey printed on: 0110412011 at: 07:46
Robinson Nuclear Plant Survey 12141 0 Data Point Details - Page 1 of I Additional Information: Counted by: I Wes Brand 12/14/2010 09:00 WRiTask #: N/A Dose Rate (OR) Object Prefixes I Suffixes:
Work Area Code:I_3600
- ContaclHS Hot Spot ComponentlTag Namel_N/A + = 30 cm No prefixGeneral Area Dose RE Tag Suffix Name:I_N/A Suffixes: nNeutron, b=Beta Short Name:I N/A Unless otherwise noted, dose rates in mrem!hr.
Postings Legend:
RCA=Radiologically Controlled Area CAContamination Area RMRadiation Area HPA=Hot Particle Area HRA=High Radiation Area RMA=Radioactive Material Area LHRA=Locked High Radiation Area CRCFE=Contact Radiation Control For Entry VHRA=Very High Radiation Area CRCPEContact Radiation Control Prior To Entry ARA=Airborne Radioactivity Area Instruments Used:
Efficiency No. I Model Serial I Probe Serial I Cal Date I Type 8/v B I a 1 611 2B 776386 NA NA 03/29/2011 0O:0( D/R N/A N/A N/A 2 LM-177 776080 44-9 NA 10/12/2011_00:0( C/R N/A 0.100 N/A 3 RO-20 778069 NA NA 08/13/2011 00:0( D/R N/A N/A N/A 02 1217320 jTenn INA 106/30/2011 00:0(1 (./K N/A 0.242 10.221 No. Type Inst. Value Units Position Notes Smear N/A pi uuu uvrvl/100 cm2 Floor N/A a<MD? DPM/100 cm2 2 Smear N/A 13/y 10001 DPM/100 cm2 VaIl 3 Smear N/A 1II 100001 DPM/100 cm2 Filter Housing N/A a <MD? DPM/100 cm2 4; Smear N/A Vy 15001 DPM/100 cm2 /ent valve Smear N/A 3/y 5001 DPM/100 cm2 ransmitter Smear N/A 131y 3001 DPM/100 cm2 VaIl 7 Smear N/A y 34001 3
l DPM/100 cm2 Floor N/A DPM/100 cm2 8 Smear N/A 13/I 33001 DPM/100 cm2 Floor N/A a<MDI DPM/100 cm2 9 Smear N/A 13/y 60001 DPM/100 cm2 Floor N/A a<MD? DPM/100 cm2 10 Smear N/A 131y 19001 DPM/100 cm2 Floor 11 Smear N/A 13/y 30001 DPM/100 cm2 Flow Transmitter N/A a<MD? DPM/100 cm2 12 Smear N/A 3/y 13001 DPM/100 cm2 Fransmitter 13 Smear N/A l3y 2001 DPM/100 cm2 Floor 14 Smear N/A /i 1201 3
1 DPM/100 cm2 Floor 15 Smear N/A 1/i 1101 DPM/100 cm2 Floor Wipe 13/y 20,001 CCPM Floor 2 Wipe 31y 10,001 CCPM Floor 3 Wipe /i 100,001 3
1 CCPM Floor 4 Wipe 13/y 121 CCPM Floor AirSample %DAC Particulate General Area Air Sample
%DAC Iodine DR y N/A *1500 mRem/hr Filter Housing N/A +1000 mRem/hr DR N/A 200 mRem/hr DR I N/A +600 mRem/hr DR N/A ÷100 mRem/hr DR I N/A +50 mRem/hr I N/A +25 mRem/hr I N/A +200 mRem/hr DR I N/A +400 mRem/hr DR I N/A +200 mRem/hr Survey printed on: 0110412011 at: 07:46
Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HB ROBINSON Task No.: 01001101601 Task
Title:
Perform Shutdown Margin JPM No.: 2011 NRC JPM Admin Calculation lAW FMP-012 RO-SRO Al-i K/A
Reference:
G2.l.37 (4.3/4.6)
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 was operating at 100% RTP steady state when Control Rod M-08 dropped into the core.
- AOP-OOi, Malfunction of Reactor Control System, was implemented and the crew has reduced reactor power.
- Current plant conditions are as follows:
- Reactor Power is 68%
- RCS Tave is 565 degrees F
- RCS Boron Concentration is 138 ppm sampled today at time now.
- Control Bank D demand position is 153 steps
- Remaining Control and Shutdown Banks demand position is 225 steps Task Standard: Calculate that sufficient shutdown margin exists under the present plant conditions.
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet Required Materials: FMP-001, Core Operating Limits Report (COLR)
FMP-0i2, Manual Determination of Shutdown Margin Boron Concentration Station Curve Book, Section 1 Cycle Data Calculator Straight Edge General
References:
FMP-OOi FMP-012 Station Curve Book, Section i Cycle Data Handouts: FMP-001 FMP-01 2 ERFIS Printout GD ROD LOG Station Curve Book, Section 1 Cycle Data Calculator Straight Edge Initiating Cue: You have been assigned by the CRS to calculate the present shutdown margin lAW FMP-012.
Time Critical Task: NO Validation Time: 60 minutes 2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement i
Appendix C Job Performance Measure Form ES-C-I Worksheet SIMULATOR SETUP N/A 2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement I
Appendix C Page 4 of 13 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
General NOTE: FMP-012 Procedure Steps 6.1.1 through 6.1.14 describe the actions to be taken within the steps of Attachment 7.1.
Performance Step: I Complete Section I of Attachment 7.1 Standard: Candidate completes the information needed for Section I:
Date I Time conditions recorded [Todays Date and Time]
Reactor Power [68] % Full Power Demand D Bank Position [153] steps Demand C Bank Position [225] steps Record RPI indication for Control Bank D [All rods except for M-08 should be recorded from printout at 153 steps (within 7.5 inches of bank average)]
Record RPI indication for Control Bank C [All rods should be recorded from printout at 225 steps (within 15 inches of demand position)]
All of the values in BOLD in the standard above should be Examiners NOTE*
recorded by the candidate (See Key)
Comment:
2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 13 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 2 Complete Section II of Attachment 7.1 Based on the Power Level and using Curve Book, Table 1.9 or Curve 1.9, the RIL for Control Bank D is and Control Bank C is Standard: Candidate completes the information needed for Section II:
Control Bank D is [100] +/- 2.5 steps Control Bank C is [225] +/- 2.5 steps Examiners NOTE: Curve 1.9B should be used for MOL to EOL.
Comment:
I Performance Step: 3 Complete Section III of Attachment 7.1 Are the control rods in Control Banks C and D above the RIL, CIRCLE ONE:
YES Adequate SDM exists and no further verification is warranted, and N/A Sections IV through Xl, Attachment 7.1
[NO] Further verification of SDM is warranted, complete Sections IV through Xl, Attachment 7.1 Standard: Candidate determines that the Control Bank D rods are NOT above the Rod Insertion Limits and answers NO.
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-I NUREG 1021, Revision 9, Supplement 1
Appendix C Page 6 of 13 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 4 Complete Section IV of Attachment Ti Current Cycle exposure (from Control Room Status Board)
MWD/MTU Reactor Power Level Tavg F Latest Available RCS Boron Concentration Sample Time Date Standard: Current Cycle exposure (from Control Room Status Board)
[156971 +/- 250 MWD/MTU Reactor Power Level [68] %
Tavg [565] degrees F Latest Available RCS Boron Concentration [138] ppm Sample Time [NOW], Date [TODAY]
Examiners NOTE:
Comment:
2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement i
Appendix C Page 7 of 13 Form ES-C-i PERFORMANCE INFORMATION q Performance Step: 5 Complete Section V of Attachment 7.1 Based on the Latest Available RCS Boron Concentration, Power Level, and exposure and using Curve Book, Table 1.3 or Curve 1.3, the Total Power Defect is pcm.
Standard: Candidate determines that Total Power Defect is [1855.5] +25,
-15 pcm.
Examiners NOTE: Candidate should use Curve 1.3C or Table 1.3C based on cycle exposure time (EOL). Value read from Curve 1.3C is
-1850 pcm and extrapolated from Table 1.3C is 1855.5 pcm as follows:
50% power, 0 ppm, 1437 pcm 50% power, 200 ppm, 1398 pcm 75% power, 0 ppm, 2077 pcm 75% power, 200 ppm, 2007 pcm 75% 50% 0 ppm difference is 640 pcm I 25% = 25.6 pcm I %
25.6 pcm I % X 18% = 460.8 pcm + 1437 pcm = 1897.8 pcm © 68% power 75% 50 % 200 ppm difference is 309 pcm I 25% = 24.36 pcm I %
24.36 pcm I % X 18% = 438.5 pcm + 1398 pcm = 1836.5 pcm
@ 68% power RCS boron given was 138 ppm 1897.8 pcm 1836.5 pcm = 61.3 pcm I 200 ppm = 0.3065 pcm I ppm 0.3065 pcm I ppm X 138 ppm = 42.3 pcm 1897.8 pcm 42.3 pcm = 1855.5 pcm Comment:
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 8 of 13 Form ES-C-I PERFORMANCE INFORMATION Procedure NOTE: Data entered into the table below will be based on the lowest indicated RPI in the bank. An untrippable rod should not be counted as a misaligned rod.
q Performance Step: 6 Complete Section VI of Attachment 7.1 Determine the RPI position of the lowest rod in Control Banks D and C and enter into the table below. If a misaligned rod(s) is in CBB, CBA, SBB, SBA, or if the bank(s) are below RIL, then determine the RPI position of the lowest rod(s) within that bank and enter into the table below. N/A columns that are not applicable. Using Table 1.15 of the Station Curve Book, determine the integral bank worth of the inserted/misaligned rod(s) by filling out the table below:
Standard: Candidate determines that Control Bank D has a rod that indicates [0] steps and records [850] pcm from Table 1.15 of the Station Curve Book. This results in a Total Rod Worth of [850]
+0, -1 pcm.
Examiners NOTE: Table 1.15, Inserted I Misaligned Bank Worths (pcm) for Control Bank D.
GD ROD LOG was provided to the candidate with the recorded position for Control Rod M-08 at 1.89 inches.
0 steps, 0 inches = 850 pcm 9 steps, 6 inches = 849 pcm Due to the information provided with the control rod position at 1.89 inches, the tolerance of +0, -1 pcm was given.
Comment:
2011 NRC JPM Admin RO-SRO Al-I NUREG 1021, Revision 9, Supplement I
Appendix C Page 9 of 13 Form ES-C-i PERFORMANCE INFORMATION 1 Performance Step: 7 Complete Section VII of Attachment 7.1 Based on the current cycle exposure and using Table 1.15 of the Station Curve Book, the Total Rod Worth is pcm.
Standard: Candidate determines from Table 1.15 of the Station Curve Book that the total rod worth is [5868.5] +/- 3 pcm.
Examiners NOTE: From Table 1.15, Current Cycle Exposure was provided from the Unit 2 Status Board as 15697 MWD!MTU.
15000 MWD!MTU = 5881 pcm 16000 MWDIMTU = 5863 pcm 5881 pcm 5863 pcm = 18 pcm difference 69.7% X 18 = 12.5 pcm 5881 pcm 12.5 = 5868.5 pcm Comment:
q Performance Step: 8 Complete Section VIII of Attachment 7.1 Number of inoperable/untrippable control rods If there are inoperable/untrippable rods then obtain the Most Reactive Rod Worth from Station Curve Book Table 1.15 and calculate the worth by performing the following, otherwise N/A.
- of rods X Most Reactive Rod Worth (pcm) =
lnop./Untrip. Rod Worth (pcm)
Standard: Candidate determines that the number of inoperable rods is [0],
thus this step is [NIA]
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-I NUREG 1021, Revision 9, Supplement I
Appendix C Page 10 of 13 Form ES-C-i PERFORMANCE INFORMATION J Performance Step: 9 Complete Section IX of Attachment 7.1 The available SDM is calculated by:
Total Rod Worth (Step VII) Inserted/Misaligned Worth (Step VI) Power Defect Worth (Step V) lnop/Untrip Rod Worth (Step VIII) Available Shutdown Margin Standard: Total Rod Worth (Step VII) [5868.5] +/- 3 pcm Inserted/Misaligned Worth (Step VI) = [850] +0, -1 pcm Power Defect Worth (Step V) = [1855.5] + 25, -15 pcm Inop/Untrip Rod Worth (Step VIII) = [0] pcm Available Shutdown Margin = [3141 to 3176] pcm Examiners NOTE:
Comment:
q Performance Step: 10 Complete Section X of Attachment 7.1 Based on the Latest Available Boron Concentration and Figure 5.0 of the COLR (FMP-OOi), the required SDM is X 1000 pcm/%= pcm.
Standard: Candidate determines from FMP-001, Figure 5.0 that required SDM is [1.60]% (+/- 0.05%) and calculates [1600] pcm. This used an RCS boron concentration of 138 ppm and read Figure 5.0 for Mode 1 operation.
Examiners NOTE:
Comment:
2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 11 of 13 Form ES-C-I PERFORMANCE INFORMATION J Performance Step: 11 Complete Section Xl of Attachment 7.1 Is the available SDM greater than the required SDM?
CIRCLE ONE
[YES] Adequate Shutdown Margin Exists NO Adequate Shutdown Margin does not exist Standard: Candidate compares the [3141 to 3176] pcm available shutdown margin to the [1600 to 1650] pcm required shutdown margin and determines that [YES Adequate Shutdown Margin Exists].
Examiners NOTE:
Comment:
END OF TASK Termination Cue: Upon completion of FMP-012, Attachment 7.1, the JPM is complete.
STOP TIME:
2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Appendix C Page 12 of 13 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM Admin RO-SRO Al-i Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1
Aer ATTACHMENT 7.1 Page 1 of 3 SHUTDOWN MARGIN MODES 1,2 DATA FORM Current reactor critical conditions:
- 1. Date/Time conditions recorded \
A) 1L)
- 2. Reactor Power % Full Power
- 3. Demand D Bank Position steps
- 4. Demand C Bank Position steps
- 5. Record RPI indication for Control Bank D Rod H-04 D-08 H-12 M-08 H-08 Steps
/ /53 &
- 6. Record RPI indication for Control Bank C Rod K-04 F-04 D-06 D-1O F-12 K12 M-1O M-06 Steps II. Based on the Power Level and using Curve Book, Table 1.9 or Curve 1.9, the RlLfor Control Bank D is ic50 steps Control Bank C is steps Ill. Are the control rods in Control Banks C and D above the RIL, CIRCLE ONE YES Adequate SDM exists and no further verification is warranted, and N/A Sections IV through Xl, Attachment 7.1.
NO Further verification of SDM is warranted, complete Sections IV through Xl, Attachment 7.1.
FMP-012 Rev. 27 Page 22 of 29
ATTACHMENT 7.1 Page2of3 SHUTDOWN MARGIN MODES 1,2 DATA FORM IV. Record the following
- 1. Current Cycle exposure (from Control Room Status Board)
/5197MWD/MTu
- 2. Reactor Power Level %
- 3. Tavg degrees F
- 4. Latest Available RCS Boron Concentration /3 ppm Sample Time Aic&, Date 7 V. Based on the Latest Available RCS Boron Concentration, Power Level, and exposur nd usin Curve Book, Table 1.3 or Curve 1.3 the To)al Pow r Defect 4
is /pcm
/
NOTE: Data entered into the table below will be based on the lowest indicated RPI in the bank. An untrippable rod should not be counted as a misaligned rod.
VI. Determine the RPI position of the lowest rod in Control Banks D and C and enter into the table below. If a misaligned rod(s) is in CBB, CBA, SBB, SBA, or if the bank(s) are below RIL, then determine the RPI position of the lowest rod(s) within that bank and enter into the table below. N/A columns that are not applicable.
Using Table 1.15 of the Station Curve Book, determine the integral bank worth of the inserted/misaligned rod(s) by filling out the table below:
CBD CBC CBB CBA SBB SBA Total Worth Lowest Indicated RPI [steps]
zz ?z5:
WORTH [pcm] 0 C) C C)
VII. Based on the current cycle exposure pd using Table 1.15 of the Station Curve Book, the Total Rod Worth is pcm FMP-012 Rev. 27 Page 23 of 29
ATTACHMENT Ti Page 3 of 3 SHUTDOWN MARGIN MODES 1,2 DATA FORM Viii. Number of inoperable/untrippable control rods If there are inoperabie/untrippable rods then obtain the Most Reactive Rod Worth from Station Curve Book Table 1.15 and calculate the worth by performing the folio i g, otherwise N/A.
pcm =
- of rods Most Reactive lnop./Untrip.
Rod Worth Rod Worth IX. The available SDM is calculated by:
-_____ 0 c3/pcm Total Rod Inserted! Power Inop/Untrip Available Worth Misaligned Defect Rod Worth Shutdown Worth Worth Margin (Step VII) (Step VI) (Step V) (Step Viii)
X. Based on the Latest Available boro Co Centration and Figure .9 of the COLR (FMP-001), the required SDM is 7
CIRCLE ONE Adequate Shutdown Margin Exists NO Adequate Shutdown Margin does not exist; perform the following:
- 1) Based on the current exposure, Tavg, and latest available Boron Concentration, and yi&rg Curve Book, Table 1.5 or Curve 1.5, the Boron Worth is (-) AJ/,P pcm/ppm
- 2) Borate to restore available SDM. Need to,borate at least
( pcm - f,4 pcm/ppm =
Available SDM Required SDM Boron Worth Amount to borate (Step IX) (Step X) (Step XI. 1)
Performed By: Date:_________
Approved By: Date:
SSO or CRSS or Supervisor Reactor Systems FMP-0i2 Rev. 27 Page 24 of 29
Appendix C Page 13 of 13 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
- Plant was operating at 100% RTP steady state when Control Rod M-08 dropped into the core.
- AOP-00i, Malfunction of Reactor Control System, was implemented and the crew has reduced reactor power.
- Current plant conditions are as follows:
- Reactor Power is 68%
- RCS Tave is 565 degrees F
- RCS Boron Concentration is 138 ppm sampled today at time now.
- Control Bank D demand position is 153 steps
- Remaining Control and Shutdown Banks demand position is 225 steps INITIATING CUE: You have been assigned by the CRS to calculate the present shutdown margin lAW FMP-012.
2011 NRC JPM Admin RO-SRO Al-I NUREG 1021, Revision 9, Supplement I
Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HB ROBINSON Task No.: 02119101401 Task
Title:
Determine the Actions Necessary JPM No.: 2011 NRC JPM Admin to enter Mode 4 From Mode 5 SRO A1-2 K/A
Reference:
G2.i.23 (4.3/4.4)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinci:
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 heatup is in progress with RCS temperature at 185 degrees F.
- RCPs B and C are running.
- RHR Pump B is operating.
- OMM-001-12, Attachment 10.2 has been completed in anticipation of the mode change.
Task Standard: Identify all items NOT meeting the Mode Checklist requirements.
Required Materials: OMM-001-12 ITS General
References:
OMM-001-12, Minimum Equipment List and Shift Relief, Revision 68 ITS Handouts: Completed OMM-001-12, Attachment 10.2 ITS 2011 NRC JPM Admin SRO A1-2 NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet Initiating Cue: The Shift Manager has assigned you the task of reviewing OMM-OOi-i2, Minimum Equipment List and Shift Relief, Attachment 10.2, to determine if any actions are required before RCS temperature can be permitted to rise to Mode 4. No OMM-048 risk assessments will be accepted to allow the Mode change.
Time Critical Task: NO Validation Time: 30 minutes 2011 NRC JPM Admin SROAI-2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
START TIME:__________
Performance Step: I Compares Completed Attachment 10.2 to determine if the requirements have been met to transition the plant into Mode 4.
Standard: Candidate uses the OMM-001-12, Attachment 10.2 and the initial conditions of this JPM to determine the inoperable or out of spec equipment that would prevent a plant mode change to Mode 4.
Examiners NOTE:
Comment:
Standard: Determines that RWST boron is out of specs high at 2450 ppm boron.
Examiners NOTE: Maximum RWST boron concentration is 2400 ppm.
Comment:
- Performance Step: 3 Compare Attachment 10.2 to Initial Conditions: COMPONENT COOLING WATER (CCW) SYSTEM (ITS LCO 3.7.6)
Standard: Determines that CCW Pumps A and B do NOT meet the requirement of 2 CCW Pumps powered from emergency power sources.
Examiners NOTE: CCW Pumps B and C are powered from Emergency Busses 480V E-I and E-2. CCW Pump A is powered from 480V Bus DS.
Comment:
2011 NRC JPM Admin SROA1-2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 4 Compare Attachment 10.2 to Initial Conditions: SERVICE WATER SYSTEM (SWS) (ITS LCO 3.7.7)
Standard: Determines that the Turbine Building Loop Isolation valves do NOT meet the operability requirements.
Examiners NOTE: Turbine Building isolation valve V6-16A is inoperable.
Comment:
- Performance Step: 5 Compare Attachment 10.2 to Initial Conditions: DIESEL FUEL OIL AND STARTING AIR (ITS LCO 3.8.3)
Standard: Determines that the Diesel Fuel Oil Storage Tank (DFOST) does NOT contain the minimum level requirement of 19000 gallons.
Examiners NOTE: ITS requires a combined total fuel oil volume of 34000 gallons but specifies that 19000 gallons must be maintained in the Unit #2 Diesel Fuel Oil Storage Tank with the remainder in the Unit #1 IC Oil Tanks.
Comment:
END OF TASK Termination Cue: When Attachment 10.2 is signed and returned to the Shift Manager, inform the Candidate that evaluation of this JPM is complete. The candidate may choose to return the form unsigned since the conditions are NOT met.
STOP TIME:
2011 NRC JPM Admin SRO Al -2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 6 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM Admin SRO Ai-2 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM Admin SROAI-2 NUREG 1021, Revision 9, Supplement i
ATTACHMENT 10.2 Page 1 of 8 2000 TO 350° (MODE 4) MEL (Prior to exceeding 200°F (Entering MODE 4))
CONTINUOUS USE This revisi n has been verified to be the latest revision available.
7;21*4/
Name (Print) Initial Signature Date Date: Shift: O7-/9o-z I
1 EQUIPMEN1 REFERENCE NUMBER MINIMUM TO GO ABOVE OPERABLE 200°F (MODE 4)
RCS LOOPS ITS LCO 2 Loops or Trains (RCS/RHR) 3.4.6 OPERABLE AND RCS OPERATIONAL LEAKAGE ITS LCO f 1 Loop or Train in operation RCS Operational Leakage 3.4.13 shall be limited to:
No pressure boundary leakage Av c2 1 gpm unidentified leakage 10 gpm identified leakage 75 gpd primary to secondary leakage through any one steam generator RCS PRESSURE ISOLATION ITS LCO All VALVES (PIVs) 3.4.14 ,4 / ( (except for valves in the RHR System)
OMM-O01-12 Rev. 68 Page 17 of 63
ATTACHMENT 10.2 Page2of8 2000 TO 350° (MODE 4) MEL EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
RCS LEAKAGE DETECTION ITS LCO 2. 1 Containment Sump Level INSTRUMENTATION 3.4.15 monitor I 1 Containment Atmosphere
-// CA Radioactivity monitor 1 Containment Fan Cooler L( Condensate Flow Rate f monitor CHEMICAL AND VOLUME ITS LCO 2 Charging pumps CONTROL SYSTEM (CVCS) 3.4.17 1 c.. OPERABLE 2 Makeup Water Pathways from RWST OPERABLE RCP HAB 6 gpm Seal Injection flow to each RCP t
f% gpm RCP B gpm RCP UCII g,, / gprn ECCS ITS LCO / ij/cj I I RHR Train AND 3.5.3 0/ 1 SI Train OPERABLE RWST ITS LCO % 300,000 gallons (91%)
3.5.4 1950 ppm an I-RU 45°Fand1C r CONTAINMENT ITS LCO 3.6.1 p OPERABLE CONTAINMENT AIR LOCK ITS LCO OPERABLE 3.6.2 CONTAINMENT ISOLATION VALVES ITS LCO 3.6.3 A 1/ All CONTAINMENT PRESSURE ITS LCO 3.6.4 o psig -0.8 psig AND ÷1.0 psig CONTAINMENTAIR ITS LCO °F 120°F TEMPERATURE 3.6.5 OMM-001-12 Rev. 68 Page 18 of 63
ATTACHMENT 10.2 Page3of8 2000 TO 350° (MODE 4) MEL EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
CONTAINMENT SPRAY AND ITS LCO 2 2 CV Spray Trains COOLING SYSTEMS 3.6.6 AND
, 2 CV Cooling Trains SPRAY ADDITIVE TANK ITS LCO / /7 % - 2505 gallons (32%)
3.6.7 f2 (
L3c % - 30% NaOH ISOLATION VALVE SEAL ITS LCO psig
- 49 psig as indicated WATER (IVSW) SYSTEM 3.6.8 --- locally on P1-1910 72_- % 85 gallons (49%)
JJj) /,, j All manual valves and h11/ both automatic valves AUXILIARY FEEDWATER ITS LCO 1 AFW Flow Path (AFW) SYSTEM (when a S/G 3.7.4 AND is being used for heat removal) 1 MDAFW Pump 2_- LCO-3.0.4.b N/A CONDENSATE STORAGE ITS LCO % 35,000 gallons (26%)
TANK(CST) 3.7.5 AND (when S/G is being used for heat removal)
(
9 O/ SW Backup OPERABLE COMPONENT COOLING ITS LCO $f 2 Trains powered from WATER (CCW) SYSTEM 3.7.6 Emergency Power supplies SERVICE WATER SYSTEM ITS LCO 2 Trains (SWS) 3.7.7 AND ULTIMATE HEAT SINK (UHS) ITS kCO Z- ( ii Water level 218 ft 3.7.8 °F SWS97°F
49 psig provides for instrument uncertainties for P1-1910, and a conservative margin OMM-001-12 Rev. 68 Page 19 of 63
ATTACHMENT 10.2 Page 4 of 8 200° TO 3500 (MODE 4)
EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
CONTROL ROOM ITS LCO 2 Trains EMERGENCY FILTRATION 3.7.9 SYSTEM (CREFS)
CONTROL ROOM ITS LCO 2 WCCU Trains EMERGENCYAIR 3.7.10 TEMPERATURE CONTROL (CREATC)
SECONDARY SPECIFIC ITS LCO (uCig 0.1 tCIg DOSE EQUIVALENT ACTIVITY 3.7.15 IODINE-131 STARTUP TRANSFORMER ITS LCO ) 1 3.8.1.a (
DIESEL GENERATORS ITS LCO 2 3.8.1.b LCO-3.0.4.b N/A DIESEL FUEL OIL AND ITS LCO DFO -
STARTING AIR 383 -
from DFOStoragefnk osi; -
Unit 1 15,000 gallons available from Unit I IC Turbine Fuel Oil Storage tanks 3 £f/gaI EDG A EDG Air Receivers 210 psig 23O psig EDG B 3 psig NOTE: Bus voltages may be read locally or via ERFIS if available.
- MCC-A Voltage APV3O22A
- MCC-B Voltage APV3O23A DC SOURCES ITS LCO 3.8.4 /3 / VDC - MCC-A Voltage> 126 VDC
,-3 VDC - MCC-B Voltage> 126 VDC OMM-001-12 Rev. 68 Page 20 of 63
ATTACHMENT 10.2 Page 5 of 8 2000 TO 350° (MODE 4)
EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200° F OPERABLE (MODE 4)
AC INSTRUMENT BUS ITS LCO SOURCES 3.8.7 //9 VAC A Voltage> 114 VAC
/f VAC *lnverter B Voltage> 114 VAC
&721 5i/9 Constant Voltage Transformers (CVT) I and 2 4160V BUSSES 2 AND 3 ITS LCO 3.8.9 *4KV Bus 2 Voltage > 3.2KV
/2tVAC VAC *4KV Bus 3 Voltage > 3.2KV NOTE: Bus voltages may be read locally or via ERFIS if available.
E-1 Voltage - ELV3O2OA E-2 Voltage - ELV3O21A 480V El AND E2 ITS LCO 480V Bus E-l Voltage 3.8.9 f ( VAC (lowest phase) > 440 VAC 480V Bus E-2 Voltage iL VAC (lowest phase) > 440 VAC It is expected the Inverter AND 4KV Bus voltages will at least meet the following:
Inverter voltage between II8VAC and I22VAC 4KV Bus voltage 3.7KV IF voltages are outside of the expected range, THEN contact Engineering for further evaluation.
OMM-OO1-12 Rev.68 Page2lof63
ATTACHMENT 10.2 Page 6 of 8 2000 TO 350° (MODE 4)
EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
AC INSTRUMENT BUSSES ITS LCO Energized by normal power 3.8.9 supply Train A:
/1 9 / 480V Bus E-1 breaker, CMPT NO. 21A, FEED TO MCC-5 (NORM POWER) &
MCC-16, closed
- MCC-5 breaker, CMPT NO.
% e ci 4BL, FEED TO INSTRUMENT BUS 1, closed f Distribution Panel A, Circuit 1 1, INVERTER A, closed Instrument Bus No. 1, Circuit 10, INSTRUMENT BUS 6, closed Instrument Bus No. 2, Circuit I
11, INSTRUMENT BUS NO.
(, 7A AND 7B, closed Train B:
4;5, £ 480V Bus E-2 breaker, CMPT NO. 23C, FEED TO MCC-6, closed
- MCC-6 breaker, CMPT NO.
c./C2 ( 2FL, FEED TO INSTRUMENT BUS 4, closed Instrument Bus No. 3, Circuit 25, INSTRUMENT BUS c/ NO. 8, closed Instrument Bus No. 4, Circuit g/ 4 12, INSTRUMENT BUS NO. 9A and 9B, closed OMM-001-12 Rev. 68 Page 22 of 63
ATTACHMENT 10.2 Page7of8 2000 TO 350° (MODE 4) MEL EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERAB)E (MODE 4)
RCS VENT PATH TRMS 3.2 2 (Y4 - Reactor Head RC-567 and d7cçe RC-568 OPERABLE, 1 ,tk L( CLOSED, Power Removed Z PZR Steam Space RC-569 4,ft and RC-570 OPERABLE, 4ij4 4 CLOSED, Power Removed
,i j RCS Vent Path valve RC-571
! (Oje and RC-572 CLOSED OXYGEN (PRIMARY) TRMS 3.5.a 2( <0.1 ppm CHLORIDE (PRIMARY) TRMS 3.5.b &( // <0.15 ppm BORIC ACID PUMPS TRMS 3.6.a 2 BORIC ACID TANKS TRMS 3.6.b Tank A A and B Boric Acid Tanks 2f % together shall contain a total of a/27ppm 3080 gallons (42%)
/3/, °F AND TankB Boron Concentration 39 % 20,000 ppm and 2ppm 22,500 ppm AND 145°F
/ °F BORIC ACID TANKS HEAT TRMS 3.6.c 2 TRACING PRIMARY WATER STORAGE TRMS 3.6.d QM % 30,000 gallons (45%)
TANK (U ri))I SNUBBERS TRMS 3.18 All safety-related snubbers (34) shall be OPERABLE APPENDIX R PATHWAYS CHECKED 1 OCFR5O, Appendix R
/ AA
,,, Pathways clear (1) TRMS 3.5.a is N/A when RCS and Pressurizer temperature are both <250° F.
IF less than the above are operable, THEN the Mode Change Checklist may be considered complete WHEN risk assessments lAW OMM-048 have determined acceptability to change Modes lAW ITS LCO 3.0.4.b. Risk Assessment complete, acceptable, and entered in Autolog.
AJ/A Signature Date OMM-001-12 Rev. 68 Page 23 of 63
ATTACHMENT 10.2 Page8of8 200° TO 3500 (MODE 4) MEL List any Mode Clearances in place:_____________________
Completed by: <D 474 7t Datef Reviewed by:
Shift Manager Date OMM-001-12 Rev.68 Page24of63
Appendix C Page 6 of 6 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
- Plant heatup is in progress with RCS temperature at 185 degrees F.
- RCPs B and C are running.
- RHR Pump B is operating.
- OMM-O01-12, Attachment 10.2 has been completed in anticipation of the mode change.
INITIATING CUE: The Shift Manager has assigned you to the task of reviewing OMM-00i-12, Minimum Equipment List and Shift Relief, Attachment 10.2, to determine the actions required before RCS temperature can be permitted to rise to Mode 4. No OMM-048 risk assessments will be accepted to allow the mode change.
2011 NRC JPM Admin SRO Ai-2 NUREG 1021, Revision 9, Supplement I
ATTACHMENT 10.2 Page 1 of 8 2000 TO 350° (MODE 4) MEL (Prior to exceeding 200° F (Entering MODE 4))
CONTINUOUS USE This revisi n has been verified to be the latest revision available.
Name 1(Print) Initial Signature Date I Date: 7d4if Shift:
1 EQUIPMEN1 REFERENCE NUMBER MINIMUM TO GO ABOVE OPERABLE 200°F (MODE 4)
RCS LOOPS ITS LCO 2 Loops or Trains (RCS/RHR) 3.4.6 OPERABLE AND I Loop or Train in operation RCS OPERATIONAL LEAKAGE ITS LCO f RCS Operational Leakage 3.4.13 shall be limited to:
No pressure boundary leakage t5/1 1 gpm unidentified leakage C 10 gpm identified leakage 75 gpd primary to
ó secondary leakage through any one steam generator RCS PRESSURE ISOLATION ITS LCO A All VALVES (PIVs) 3.4.14 /1 / ( (except for valves in the RHR System)
OMM-001-12 Rev. 68 Page 17of63
ATTACHMENT 10.2 Page2of8 2000 TO 350° (MODE 4) MEL EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
RCS LEAKAGE DETECTION ITS LCO - 1 Containment Sump Level INSTRUMENTATION 3.4.15 monitor I Containment Atmosphere t3A Radioactivity monitor 1 Containment Fan Cooler Condensate Flow Rate I monitor CHEMICAL AND VOLUME ITS LCO 2 Charging pumps CONTROL SYSTEM (CVCS) 3.4.17 OPERABLE 2 Makeup Water Pathways from RWST OPERABLE RCP A 6 gpm Seal Injection flow to each RCP
,,(,t gpm RCP B gpm RCP C g, / gpm ECCS ITS LCO / 4/ç 1 1 RHR Train AND 3.5.3 1 SI Train OPERABLE RWST ITS LCO 3.5.4 Q.. % 300,000 gallons (91%)
(
2.tppm l95oppmand2400ppm
°F 45°Fand100°F CONTAINMENT ITS LCO OPERABLE 3.6.1 Or CONTAINMENT AIR LOCK ITS LCO A OPERABLE 3.6.2 (f CONTAINMENT ISOLATION ITS LCO L I f /
/I All VALVES 3.6.3 CONTAINMENT PRESSURE ITS LCO ç psig -0.8 psig AND +1.0 psig 3.6.4 LI CONTAINMENT AIR ITS LCO °F 120°F TEMPERATURE 3.6.5 0 OMM001-12 Rev. 68 Page 18 of 63
ATTACHMENT 10.2 Page 3 of 8 2000 TO 350° (MODE 4) MEL EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
CONTAINMENT SPRAY AND ITS LCO 2 CV Spray Trains COOLING SYSTEMS 3.6.6 AND
% - 2505 gallons (32%)
L.3c % - 30% NaOH ISOLATION VALVE SEAL ITS LCO psig 49 psig as indicated WATER (IVSW) SYSTEM 3.6.8 locally on P1-1910 71 % 8sgallons(49%)
jJ/) / , ,j All manual valves and I If )if/ both automatic valves AUXILIARY FEEDWATER ITS LCO 1 AFW Flow Path (AFW) SYSTEM (when a S/G 3.7.4 .. AND is being used for heat removal) 1 MDAFW Pump 1-. LCO-3.0.4.b N/A CONDENSATE STORAGE ITS LCO % 35,000 gallons (26%)
TANK (CST) 3.7.5 QA AND (when S/G is being used for heat removal)
(
fr 5
c SW Backup OPERABLE COMPONENT COOLING WATER (CCW) SYSTEM ITS LCO 3.7.6 A ,W 2 Trains powered from Emergency Power supplies 7
f4 4 1
c (B and C pumps)
SERVICE WATER SYSTEM ITS LCO 2 Trains (SWS) 3.7.7 AND Vk-/ ,j Turbine Bldg Loop Isolation L
1 9 valves OPERABLE ULTIMATE HEAT SINK (UHS) ITS LCO 12- ( ft - Water level 218 ft 3.7.8 °F SWS97°F
49 psig provides for instrument uncertainties for P1-I 91 0, and a conservative margin OMM-001-12 Rev. 68 Page 19 of 63
ATTACHMENT 10.2 Page 4 of 8 2000 TO 350° (MODE 4)
EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
CONTROL ROOM ITS LCO 2 Trains EMERGENCY FILTRATION 3.7.9 SYSTEM (CREFS)
CONTROL ROOM ITS LCO 2 WCCU Trains EMERGENCY AIR 3.7.10 TEMPERATURE CONTROL (CREATC)
SECONDARY SPECIFIC ITS LCO (itCig 0.l /C/g DOSE EQUIVALENT ACTIVITY 3.7.15 IODINE-131 STARTUP TRANSFORMER ITS LCO ) 1 3.8.1.a I DIESEL GENERATORS ITS LCO 2 3.8.1.b LCO-3.0.4.b N/A DIESEL FUEL OIL AND ITS LCO DFO 19,000 gallons available STARTING AIR 3.8.3 from DFO Storage tank
/7ooo gal Unit 1 15,000 gallons available from Unit 1 IC Turbine Fuel Oil Storage tanks 3 Wa,gal EDG A EDG Air Receivers 210 psig 3O psig EDG B 3 Z-psig NOTE: Bus voltages may be read locally or via ERFIS if available.
- MCC-A Voltage APV3O22A
- MCC-B Voltage APV3O23A DC SOURCES ITS LCO 3.8.4 /3 / VDC - MCC-AVoltage> 126 VDC
,(..3 VDC - MCC-B Voltage> 126 VDC OMM-001-12 Rev. 68 Page 20 of 63
ATTACHMENT 10.2 Page 5 of 8 2000 TO 350° (MODE 4)
EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABLE (MODE 4)
AC INSTRUMENT BUS ITS LCO SOURCES 3.8.7 1/9 VAC *InveIer A Voltage> 114 VAC
- lnveer B Voltage> 114 VAC
/f VAC 49/2 Constant Voltage Transformers (CVT) 1 and 2 4160V BUSSES 2 AND 3 ITS LCO 3.8.9 *4KV Bus 2 Voltage> 3.2KV I2tt5VAC
- 4KVBus3Voltage>32KV 12VAC NOTE: Bus voltages may be read locally or via ERFIS if available.
E-1 Voltage - ELV3O2OA E-2 Voltage - ELV3O21A 480V El AND E2 ITS LCO 480V Bus E-l Voltage 3.8.9 ( ( j VAC (lowest phase) > 440 VAC 480V Bus E-2 Voltage iL 2VAC (lowest phase) > 440 VAC It is expected the Inverter AND 4KV Bus voltages will at least meet the following:
Inverter voltage between II8VAC and 122VAC 4KV Bus voltage 3.7KV IF voltages are outside of the expected range, THEN contact Engineering for further evaluation.
OMM-001-12 Rev. 68 Page 21 of 63
ATTACHMENT 10.2 Page6of8 2000 TO 350° (MODE 4)
EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200° F OPERABLE (MODE 4)
AC INSTRUMENT BUSSES ITS LCO Energized by normal power 3.8.9 supply Train A:
A 9 / 480V Bus E-1 breaker CMPT NO. 21A, FEED TO MCC-5 (NORM POWER) &
MCC-16, closed MCC-5 breaker, CMPT NO.
c 1t1 4BL. FEED TO INSTRUMENT BUS 1, closed
, 7J Distribution Panel A, Circuit 1 1, INVERTER A, closed Instrument Bus No. 1, Circuit 10, INSTRUMENT BUS 6, closed Instrument Bus No. 2, Circuit I
11, INSTRUMENT BUS NO.
(,, 7AAND 7B, closed Train B:
£ 480V Bus E-2 breaker, CMPT NO. 23C, FEED TO MCC-6, closed
- MCC-6 breaker, CMPT NO.
2FL, FEED TO c( INSTRUMENT BUS 4, closed Instrument Bus No. 3, Circuit c/
25, INSTRUMENT BUS NO. 8, closed Instrument Bus No. 4, Circuit g/ A 12, INSTRUMENT BUS NO. 9A and 9B, closed OMM-001-12 Rev. 68 Page 22 of 63
ATTACHMENT 10.2 Page7of8 2000 TO 350° (MODE 4) MEL EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPERABjE (MODE 4)
RCS VENT PATH TRMS 3.2 2 c9if Reactor Head RC-567 and d4çe,4 RC-568 OPERABLE, Vi CLOSED, Power Removed PZR Steam Space RC-569 4,j? 6 . and RC-570 OPERABLE, 4,ii,4 j CLOSED, Power Removed
) f RCS Vent Path valve RC-571
! (&e and RC-572 CLOSED OXYGEN (PRIMARY) TRMS 3.5.a 7( <0.1 ppm CHLORIDE (PRIMARY) TRMS 3.5.b yf f/GM <0.15 ppm BORIC ACID PUMPS TRMS 3.6.a 2 BORIC ACID TANKS TRMS 3.6.b Tank A A and B Boric Acid Tanks
- 2. / % together shall contain a total of a/7ppm 3080 gallons (42%)
/-4 °F AND TankB Boron Concentration 3 % 20,000 ppm and ppm 22,500 ppm AND 145°F
/ °F BORIC ACID TANKS HEAT TRMS 3.6.c -> 2 TRACING PRIMARY WATER STORAGE TRMS 3.6.d QM % 30,000 gallons (45%)
TANK ri))/
SNUBBERS TRMS 3.18 All safety-related snubbers (34) shall be OPERABLE APPENDIX R PATHWAYS 10CFR5O, /1/,, j Pathways clear CHECKED Appendix R C (1) TRMS 3.5.a is N/A when RCS and Pressurizer temperature are both <250°F.
IF less than the above are operable, THEN the Mode Change Checklist may be considered complete WHEN risk assessments lAW OMM-048 have determined acceptability to change Modes lAW ITS LCO 3.0.4.b. Risk Assessment complete, acceptable, and entered in Autolog.
AJJA Signature Date OMM-001-12 Rev. 68 Page23of63
ATTACHMENT 10.2 Page8ofs 2000 TO 350° (MODE 4) MEL List any Mode Clearances in place:____________________
Ai/4 Completed by:
Date
/
Reviewed by:
Shift Manager Date OMM-001-12 Rev. 68 Page 24 of 63
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: HB ROBINSON Task No.: 02341100103 Task
Title:
ITS Application for Misaligned JPM No.: 2011 NRC JPM Admin Control Rod and Quadrant Power SRO A2 Tilt K/A
Reference:
G2.2.40 (3.4/4.7)
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 operating shift was raising power from 50% to 100% lAW GP 005, Power Operation.
- With Control Bank D at 192 steps, the crew identifies that Control Rod H12 is misaligned from its bank by 8.5 inches.
- Reactor power is held at 88% while technicians determine the reason for the misaligned control rod and reactor engineers assess recovery options.
- AFD is within limits.
Task Standard: Enters correct ITS Action Statements, and prioritizes actions.
Required Materials: Classroom/Simulator/Plant location with Control Room references.
General
References:
Improved Technical Specifications OMM-OOI-8, Control of System and Equipment Status, Revision 44 2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet Handouts: NONE Initiating Cue: You are the CRS:
- Evaluate the given conditions for Technical Specification Action Statement(s) applicability.
- Identify the highest priority action, including all additional actions required.
Time Critical Task: NO Validation Time: 20 minutes 2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 3 of 7 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Examiners NOTE: Performance Steps 1, 2, and 3 can be done in any order.
- Performance Step: I Review and apply the Rod Group Alignment Limits LCO.
Standard: Enters ITS 3.1.4, Condition B.
Examiners NOTE:
Comment:
- Performance Step: 2 Review and apply the QPTR LCO.
Standard: Enters ITS 3.2.4, Condition A.
Examiners NOTE:
Comment:
2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement i
Appendix C Page 4 of 7 Form ES-C-i PERFORMANCE INFORMATION Examiners NOTE: The candidate may have specified this at any point during the JPM.
- Performance Step: 3 Identify highest priority action.
Standard: B.1 Restore rod to within alignment limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (ITS 3.1.4 Condition B, Required Action B.i).
OR B.2.i.i Verify SDM is within the limits provided in the COLR within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (ITS 3.1.4 Condition B, Required Action B.2.1.1).
OR B.2. 1 .2 Initiate boration to restore SDM to within limit within I hour( ITS 3.1.4 Condition B, Required Action B.2.1.2).
AND B.2.2 Reduce thermal power to < 70% RTP within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (ITS 3.1.4 Condition B, Required Action B.2.2).
AND B.2.3 Verify SDM is within the limits provided in the COLR Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (ITS 3.1.4 Condition B, Required Action B.2.3)
Examiners NOTE: Candidate may also state that a power reduction would begin to ensure they get to < 83.5% within two hours for the QPTR exceeding 1.02.
Comment:
2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 7 Form ES-C-i PERFORMANCE INFORMATION END OF TASK Termination Cue: When the Candidate has completed review of Technical Specifications and determined first priority action, the evaluation of this JPM is complete.
STOP TIME:
2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 6 of 7 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM Admin SRO A2 Examinees Name:
Date Performed:
Facility Evaluator:
Numberof Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 7 of 7 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
- The operating shift was raising power from 50% to 100% lAW GP-005, Power Operation.
- With Control Bank D at 192 steps, the crew identifies that Control Rod H12 is misaligned from its bank by 8.5 inches.
- Reactor power is held at 88% while technicians determine the reason for the misaligned control rod and reactor engineers assess recovery options.
- AFD is within limits.
INITIATING CUE: You are the CRS:
- Evaluate the given conditions for Technical Specification Action Statement(s) applicability.
- Identify the highest priority action, including all additional actions required.
2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement I
Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HB ROBINSON Task No.:
Task
Title:
Determine the appropriate Radiation JPM No.: 2011 NRC JPM RO-SRO Work Permit for the assigned task and Admin A3 apply any limitations from the RWP K/A
Reference:
G2.3.7 (3.5/3.6)
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:
- Fuel movement in the Spent Fuel Pool has been ongoing for several weeks in support of Dry Fuel Storage campaign.
- The Spent Fuel Pit Filter has exceeded the differential pressure limit of 25 psid.
- Estimated dose for the Operations task is 29 mR.
Task Standard: Determine which RWP meets the criteria for allowing the valve operation and dose limits for the task assigned and identify any specific restrictions.
Required Materials: RWPs 5498, 5499, 5519 and 6183.
SFP Filter area survey map.
General
References:
RWPs 5498, 5499, 5519 and 6183.
SFP Filter area survey map.
Handouts: RWPs 5498, 5499, 5519 and 6183.
SFP Filter area survey map.
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet Initiating Cue: You have been assigned to hang the clearance and vent and drain the Spent Fuel Pit Filter. Select the appropriate RWP for supporting the task and identify specific restrictions for the task.
Time Critical Task: NO Validation Time: 20 minutes SIMULATOR SETUP N/A 2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
START TIME:
- Performance Step: I Determine the dose limits from the SFP Filter area survey map and select the appropriate RWP for the task.
Standard: Candidate determines the dose at the filter housing will require the use of RWP #551 9. RWP #5519 states that continuous RC coverage is required.
Examiners NOTE: 1000 mR/hr reading at 30 cm at the filter housing and the posting as a Locked High Radiation Area (LHRA) requires the use of RWP #5519 based on the ED Dose Rate Alarm setpoint.
RWPs #5498 and 5499 state that no entry allowed for> 1000 mR/hr.
RWP #6183 states that ED Dose Alarm is 20 mRem. The initial conditions state that the estimated dose for the Operations task is 29 mR.
Comment:
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 2 Determine any additional restrictions from the RWP and survey map.
Standard: Candidate determines that a Hot Particle Area exists and additional protective clothing is required.
Examiners NOTE: Hot Particle Area requires full PCs with hood, double rubber gloves and double rubber shoecovers.
Faceshield required when hot particles > 2.0 E6 dpm are present (Noted on survey map as being greater than limit).
SOER 2001-1 pre-job briefing is required.
Comment:
END OF TASK Termination Cue: When the candidate has determined the RWP restrictions from the survey map, the evaluation of this JPM is complete.
STOP TIME:
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 6 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 201 1 NRC JPM RO-SRO Admin A3 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 6 of 6 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:
- Fuel movement in the Spent Fuel Pool has been ongoing for several weeks in support of Dry Fuel Storage campaign.
- The Spent Fuel Pit Filter has exceeded the differential pressure limit of 25 psid.
- Estimated dose for the Operations task is 29 mR.
Initiating Cue: You have been assigned to hang the clearance and vent and drain the Spent Fuel Pit Filter. Select the appropriate RWP for supporting the task and identify specific restrictions for the task.
2011 NRC JPM RO-SROAdmInA3 NUREG 1021, Revision 9, Supplement 1
PASSPORT - TOTAL EXPOSURE SYSTEM Ij.nIArIor 1O1t1 PERlV1I.[
I 11111 1111111111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 111111111/11111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00005498 01 Page : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES ED SETPOINTS 10/8/120 Type : MR Status: ACTIVE Date : 08/08/2010 12:42 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 08/08/2010 12:42 By: MANNIPO1 MANNING PAUL W Approved Date : 08/08/2010 12:42 By: RITCHW RITCHIE WILLI T Radiological Conditions ED Time Alarm: 840 (in Minutes)
Administrative Dose Limit: 10 (mrem)
ED Dose Alarm: 8 (mrem) ED Dose Rate Alarm: 120 (mrem/hr)
Radiological Hazards Radiological Hazard --Distance--I Reading I SEE SPECIAL INSTRUCT N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) Multi-Pack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO Hold Points and Special Instructions Nbr Hold Point Description 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VHRA - VERY HIGH RADIATION AREA 10 CV WHEN THE REACTOR IS CRITICAL (EXCEPT FOR FIRE
PASSPORT - TOTAL EXPOSURE SYSTEM 4iR1( 1IIrv1I1 I 11111 11111111111111111111 11111 1111111111 11111 1111111111 11111 1111111111 11111 1111111111 1111111111 11111 liii! liii ALARA Task Jport ID : TIPH900 RWP Number: 00005498 01 Page : 2 Facility : RNP 10 BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVES WORK 10 IN THE SFP, IE. MOVING FUELO COMPONENTS IN SFP.
10 NO ENTRY INTO AREAS GREATE. TIANOR EQUAL TO 10 1000 MREM/HR.
Nbr Special Instructions 5 WORK DESCRIPTION ********************
5 OPERATIONS ACTIVITIES 5 NO SPENT FUEL POOL WORK ON THIS RWP.
5 5
10 1.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM-TRX DOSIMETERS.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7. PAM/TRX REQUIRED FOR WORK IN HRAS 10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2.NO ENTRY IN AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20 30 *****HOT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH HPA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING 30 W/HOOD AND DOUBLE RUBBER GLOVES AND SHOECOVERS.
30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
PASSPORT - TOTAL EXPOSURE SYSTEM 4LDIAfIJN iii 4
1{ piiiiir I 1111111111 11111 1111111111IIII1111111111 lIhi 11111 11111 11111 11111 hIll 11111111111111111111 hIll 1111111111 liii ALARA Task ort ID : TIPH900 RWP Number: 00005498 01 Page : 3 Facility : RNP 30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
30 6.A PRE-JOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 E6 DPM 30 ARE PRESENT.
30 40 **** CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) ***
40 40 1.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.OREX DELUXE WITH HOOD REQUIRED FOR 40 WET WORK AND ADDITIONAL DRESS CONTROLS 40 MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE, 40 IF NEEDED TO CONTAIN LIQUIDS.
40 50 ***********CONTAMINATED AREA ENTRIES*************
50 50 1.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK 50 OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.OREX DELUXE WITH HOOD REQUIRED FOR WET WORK 50 AND ADDITIONAL DRESS CONTROLS MAY BE REQUIRED 50 BASED ON RC INSTRUCTIONS.
50 4.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 60 ********FIRE BRIGADE ENTRY INTO CV**********
60 ***********WITH REACTOR CRITICAL*************
60 60 1.PERMISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 60 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 60 INTO THE CV WITH THE REACTOR CRITICAL.
60 2.CONTINUOUS RC COVERAGE REQUIRED.
60 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 60 ENTRY IS COMPLETE).
60 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND 60 UTILIZING TURNOUT GEAR.
60 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 60 FIRE EQUIPMENT CABINET IN THE RCA.
60 6.VERIFY THE ALARMING DOSIMETER IS ON.
60 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 60 8.ALARM SETPOINTS: DOSE ALARM 750 MREM
PASSORT - TOTAL EXPOSURE SYSTEM Tj.DIifIO?T ,oI1c pii.jiir 111101111111111111111111111111111111111111111111111111111111 1111111111 11111 111111111111111 11111 11111 11111 liii ALARA Task iport ID : TIPH900 RWP Number: 00005498 01 Page : 4 Facility : RNP 60 DOSE RATE ALARM 10000 MREM/HR 60 9.NO ENTRY INTO CV SUMP WITH REACTOR CRITICAL.
60 70 ****REQUIREMENTS FOR VENTING, SAMPLING OR DRAINING****
70 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
70 70 l.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 70 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
70
- End of Report -
PASSPORT - TOTAL EXPOSURE SYSTEM 1.1nI 4 uIcerb. 6c.R1( iiiir 1 11111 11111 11111 11111 liii!11111 11111 1111111111 1111111111 11111 1111111111 IlIN 11111 11111 liii! 1111111111 liii! liii ALARA Task sport ID : TIPH900 RWP Number: 00005499 01 Page : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES - ED SETPOINTS 20/16/400 Type : MR Status: ACTIVE Date : 08/08/2010 12:41 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 08/08/2010 12:41 By: MANNIPO1 MANNING PAUL W Approved Date : 08/08/2010 12:41 By: RITCHW RITCHIE WILLI T Radiological Conditions ED Time Alarm: 780 (in Minutes)
Administrative Dose Limit: 20 (mrem)
ED Dose Alarm: 16 (mrem) ED Dose Rate Alarm: 400 (mrem/hr)
Radiological Hazards Radiological Hazard I SEE SPECIAL INSTRUCT
--Distance--I Reading I N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) Multi-Pack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO Hold Points and Special Instructions Nbr Hold Point Description 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VHRA - VERY HIGH RADIATION AREA 10 CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL (EXCEPT
PASSPORT - TOTAL EXPOSURE SYSTEM voiic I1111111111 11111 1111111111 11111 11111 11111 11111 11111 11111liii! 1111111111 11111 1111111111 11111 1111111111 11111 liii ALARATask Jport ID : TIPH900 RWP Number: 00005499 01 Page : 2 Facility : RNP 10 FOR FIRE BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVES WORK IN THE 10 SFP, IE. MOVEMENT OF FUEL OR COMPONENTS.
Nbr Special Instructions 5 ************** WORK DESCRIPTION 5 OPERATIONS ACTIVITIES & INSPECTIONS 5 NO SPENT FUEL POOL WORK ON THIS RWP.
S 5
10 l.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM/TRx.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7. PAM/TRX REQUIRED FOR WORK IN HRAS 10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2. DO NOT ENTER ANY AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20 30 *****HOT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH IWA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING 30 W/HOOD AND DOUBLE RUBBER GLOVES AND RUBBER SHOECOVERS 30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT I1111111111 11111 111111111111111 11111 11111 11111 1111111111111111111111111111111111111111111111111111111111111111 ALARA Task
.port ID : TIPH900 RWP Number: 00005499 01 Page : 3 Facility : RNP 30 6.A PRE-JOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 E6 DPM 30 ARE PRESENT.
30 40 **** CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) ***
40 40 l.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.FULL PROTECTIVE CLOTHING W/HOOD, OREX DELUXE 40 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 40 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE, 40 IF NEEDED TO CONTAIN LIQUIDS.
40 45 ****REQUIREMENTS FOR VENTING, SAMPLING OR DRAINING****
45 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
45 45 l.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 45 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
45 50 ***********CONTAMINATED AREA ENTRIES*************
50 50 l.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK 50 OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.DOUBLE SURGEONS GLOVES MAY BE SUBSTITUTED FOR RUBBER 50 GLOVES WITH RADIATION CONTROL APPROVAL.
50 4.FULL PROTECTIVE CLOTHING, WATER RESISTANT DRESS 50 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 50 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
50 5.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 70 ********FIRE BRIGADE ENTRY INTO CV**********
70 ***********WITH REACTOR CRITICAL*************
70 70 l.PERMISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 70 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 70 INTO THE CV WITH THE REACTOR CRITICAL.
70 2.CONTINUOUS RC COVERAGE REQUIRED.
70 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 70 ENTRY IS COMPLETE) 70 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND
PASSPORT - TOTAL EXPOSURE SYSTEM IL4.phis..1Ir 1O1J( pJ,[f I 1111111111 11111 1111111111111111111111111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00005499 01 Page : 4 Facility : RNP 70 UTILIZING TURNOUT GEAR.
70 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 70 FIRE EQUIPMENT CABINET IN THE RCA.
70 6.VERIFY THE ALARMING DOSIMETER IS ON.
70 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 70 8.ALARM SETPOINTS: DOSE ALARM 750 MREM 70 DOSE RATE ALARM 10000 MREM/HR 70 9.NO ENTRY INTO CV SUNP WITH REACTOR CRITICAL.
70
- End of Report -
PASSPORT TOTAL EXPOSURE SYSTEM
.i 1 nirior \OR1C I 11111 1111111111 1111111111 11111 liii! 11111 11111 11111 11111 liii! 11111 11111 11111 111111111111111 11111 liii! 111111111 ALARA Task port ID : TIPH900 RWP Number: 00005519 01 Page : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES & INSPECTIONS
, Type : HR Status: ACTIVE Date : 08/08/2010 12:28 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 08/08/2010 12:28 By: MANNIPO1 MANNING PAUL W Approved Date : 08/08/2010 12:28 By: RITCHW RITCHIE WILLI T Radiological Conditions ED Time Alarm: 780 (in Minutes)
Administrative Dose Limit: 40 (mrern)
ED Dose Alarm: 32 (mrem) ED Dose Rate Alarm: 2000 (mrem/hr)
Radiological Hazards Radiological Hazard I--Distance--i I Reading I SEE SPECIAL INSTRUCT N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) Multi-Pack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO Hold Points and Special Instructions Nbr Hold Point Description
- c. 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VHRA - VERY HIGH RADIATION AREA 10 CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL (EXCEPT
- PASSPORT - TOTAL EXPOSURE SYSTEM 1.II4.TION 1.1C PER]N1I I 11111 11111 11111 11111 1111111111 1111111111 11111 1111111111 11111 1111111111 11111 1111111111 11111 1111111111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00005519 01 Page : 2 Facility : RNP 10 FOR FIRE BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVE WORK IN THE 10 SFP, IE. MOVEMENT OF FUEL OR COMPONENTS.
Nbr Special Instructions 5 **************
WORK DESCRIPTION 5 OPERATIONS ACTIVITIES & INSPECTIONS 5 NO SPENT FUEL POOL WORK ON THIS RWP.
5 S
10 1.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM-TRX DOSIMETERS.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7.TELEMETRY AND/OR PAM REQUIRED FOR WORK IN HRAS 10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2 CONTINUOUS RADIATION CONTROL COVERAGE REQUIRED 20 FOR ALL ENTRIES INTO AREAS GREATER THAN OR 20 EQUAL TO 1000 MREM/HR.
20 3.EXPOSURE CONTROL RC TECHNICIAN TO BE DESIGNATED WHEN 20 WORKING IN AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20 30 *****HOT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH HPA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT 1111111111111111 IIII11111 11111 IIN 11111 IIIU IIII11111 hIll 1111111111 11111 11111 lUll 11111 1111111111 111111111 ALARA Task sport ID : TIPH900 RWP Number: 00005519 01 Page : 3 Facility : RNP 30 w/H0OD AND DOUBLE RUBBER GLOVES AND RUBBER SHOECOVERS 30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
30 6.A PRE-JOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 ES DPM 30 ARE PRESENT.
30 40 **** CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) ***
40 40 l.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.FULL PROTECTIVE CLOTHING W/HOOD, OREX DELUXE 40 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 40 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE,
) 40 IF NEEDED TO CONTAIN LIQUIDS.
40 45 ****REQUIREMENT5 FOR VENTING, SAMPLING OR DRAINING****
45 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
45 45 l.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 45 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
45 50 ***********CONTAMINATED AREA ENTRIES*************
50 50 l.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK 50 OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.DOUBLE SURGEONS GLOVES MAY BE SUBSTITUTED FOR RUBBER 50 GLOVES WITH RADIATION CONTROL APPROVAL.
50 4.FULL PROTECTIVE CLOTHING, WATER RESISTANT DRESS 50 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 50 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
50 5.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 60 ************SOER 2001-1 REQUIREMENTS*************
60 60 l.PRE-JOB BRIEFING REQUIRED.
60 2.RADIATION CONTROL SUPERVISOR & WORK GROUP SUPERVISOR 60 MUST PARTICIPATE IN PRE JOB BRIEFING.
60 3.STAYTIME AND TIME KEEPING REQUIRED WITH GENERAL
PASSPORT - TOTAL EXPOSURE SYSTEM I.nIs.rIoN vopJc I 11111 11111 IIIN11111liii!11111 11111 11111 11111 1111111111 11111 11111 11111 IIlI11111 11111111111111111111 11111 liii ALAR Task Jport ID : TIPH900 RWP Number: 00005519 01 Page : 4 Facility : RNP 60 AREA DOSE RATES GREATER THAN 1000 MREM/HR.
60 4.ADHERE TO WORK INSTRUCTIONS, STAY TIMES, AND SURVEY 60 REQUIREMENTS SPECIFIED IN THE PRE-JOB BRIEFING AND 60 ON ATTACHMENT 10.5 OF HPP-500-3 THAT HAS BEEN 60 PREPARED FOR THE ACTIVITY.
60 5.CONTINUOUS RADIATION CONTROL COVERAGE REQUIRED WHEN 60 THE POTENTIAL GENERAL AREA DOSE RATES OF GREATER 60 THAN 1000 MREM/HR EXIST.
60 70 ********FIRE BRIGADE ENTRY INTO CV**********
70 ***********WITH REACTOR CRITICAL*************
70 70 1.PERMISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 70 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 70 INTO THE CV WITH THE REACTOR CRITICAL.
70 2.CONTINUOUS RC COVERAGE REQUIRED.
70 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 70 ENTRY IS COMPLETE) 70 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND 70 UTILIZING TURNOUT GEAR.
) 70 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 70 FIRE EQUIPMENT CABINET IN THE RCA.
70 6.VERIFY THE ALARMING DOSIMETER IS ON.
70 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 70 8.ALARM SETPOINTS: DOSE ALARM 750 MREM 70 DOSE RATE ALARM 10000 MREM/HR 70 9.NO ENTRY INTO CV SUMP WITH REACTOR CRITICAL.
70
- End of Report -
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT I 1111111111111111111111111111111 NIh 1111111111111111(11111111 liii 11111 11111 11111 11111 11111 11111 11111 11111 liii MJPA Task port ID : TIPH900 RWP Number: 00006183 00 W001849206 24 01 Page : 1 Facility : RNP RWP Title : OPERATIONS ACTIVITIES & INSPECTIONS Type : HR Status: ACTIVE Date : 02/16/2011 06:51 Area : GENERAL FACILITY Location:
Work Begin Date: 12/31/2009 00:00 Work End Date: 12/31/2013 23:59 Extension Date : By:
Initiated Date : 02/16/2011 06:51 By: RITCHW RITCHIE WILLI T Approved Date : 02/16/2011 06:51 By: RITCHW RITCHIE WILLI T ALARA Task ALARA Task : WO 01849206 24 01 Status: READY ALARA Desc : OPERATIONS ACTIVITIES Radiological Conditions ED Time Alarm: 780 (in Minutes)
Ackninistrative Dose Limit: 30 (mrem)
ED Dose Alarm: 20 (mrem) ED Dose Rate Alarm: 2000 (mrem/hr)
Radiological Hazards Radiological Hazard I Distance I Reading SEE SPECIAL INSTRUCT N/A N/A N/A Radiation Protection Requirements Dosimetry Type : S STANDARD (DRD/TLD) MultiPack Type:
Type Code Description Type Code Description SPCL SPCL SEE SPECIAL INSTRUCTION TRNG GNRO
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT I 11111! 11111 11111 11111 11111 11111 11111 11111 11111 11111 liii! 111111111111111111111111111111111111111111111111/1111 ALARA Task port ID : TIPH900 RWP Number: 00006183 00 wO 01849206 24 01 Page : 2 Facility : RNP Hold Points and Special Instructions Nbr Hold Point Description 10 THE FOLLOWING AREAS SHOULD NOT BE ACCESSED ON 10 THIS RWP:
10 VHRA - VERY HIGH RADIATION AREA 10 CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL (EXCEPT 10 FOR FIRE BRIGADE RESPONSE) 10 NO WORK ALLOWED ON THIS RWP WHICH INVOLVE WORK IN THE 10 SFP, IE. MOVEMENT OF FUEL OR COMPONENTS.
Nbr Special Instructions 5 WORK DESCRIPTION 5 OPERATIONS ACTIVITIES & INSPECTIONS 5 NO SPENT FUEL POOL WORK ON THIS RWP.
5 5
10 1.REVIEW AREA SURVEY MAPS AND/OR CONTACT RADIATION 10 CONTROL FOR SPECIFIC WORK AREA RADIOLOGICAL 10 CONDITIONS PRIOR TO START OF WORK.
10 2.IF RADIOLOGICAL CONDITIONS ARE SIGNIFICANTLY HIGHER 10 THAN CURRENT SURVEYS OR HISTORICAL SURVEY DATA 10 THEN WORK IS NOT ALLOWED TO CONTINUE ON THIS RWP 10 WITHOUT APPROVAL FROM RC SUPERVISION.
10 3.NOTIFY RADIATION CONTROL PRIOR TO CLIMBING IN 10 THE OVERHEAD.
10 4.FOR HIGH NOISE AREAS EVALUATE THE USE OF THE 10 PAM-TRX DOSIMETERS.
10 5.IF ACCUMULATED DOSE ALARM OR UNANTICIPATED DOSE 10 RATE ALARM SOUNDS, LEAVE THE RADIATION CONTROL AREA 10 AND CONTACT RADIATION CONTROL.
10 6.CONTACT RC PRIOR TO TRANSPORTING RADIOACTIVE MATERIAL 10 THAT COULD RESULT IN A RADIOLOGICAL POSTING CHANGE.
10 (REFERENCE NCR 236014) 10 7.TELEMETRY AND/OR PAM REQUIRED FOR WORK IN HRAS 10 AND LHRAS.
10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20 1.PRE-JOB BRIEFING REQUIRED.
20 2.CONTINUOUS RADIATION CONTROL COVERAGE REQUIRED 20 FOR ALL ENTRIES INTO AREAS GREATER THAN OR 20 EQUAL TO 1000 MREM/HR.
20 3.EXPOSURE CONTROL RC TECHNICIAN TO BE DESIGNATED WHEN 20 WORKING IN AREAS GREATER THAN OR EQUAL TO 20 1000 MREM/HR.
20
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT 1111111 11111 1(111 liii! 1111111111111111111111(11111111111111111(111111111111111111 [IN 11111 11111 11111 11111 III ALRA Task port ID : TIPH900 RWP Number: 00006183 00 w001849206 24 01 Page : 3 Facility : RNP 30 *****HQT PARTICLE AREA ENTRIES*****
30 30 1.NOTIFY RADIATION CONTROL PRIOR TO EACH HPA ENTRY.
30 2.DRESS REQUIREMENTS INCLUDE FULL PROTECTIVE CLOTHING 30 w/HO0D AND DOUBLE RUBBER GLOVES AND RUBBER SHOECOVERS 30 3.CHANGE GLOVES FREQUENTLY WHEN PERFORMING WORK.
30 4.INTERMITTENT RC COVERAGE AS MINIMUM.
30 5.HOT PARTICLE MONITORING REQUIRED UPON EXIT.
30 6.A PREJOB BRIEFING IS REQUIRED WHEN WORKING IN HOT 30 PARTICLE AREAS WHERE HOT PARTICLES ARE PRESENT.
30 7.FACESHIELD REQUIRED WHEN HOT PARTICLES > 2.0 E6 DPM 30 ARE PRESENT.
DC 40 ****
CONTAMINATED SYSTEM BREACH (LINES > 1 INCH) ***
40 40 l.CONTINUOUS RC COVERAGE REQUIRED FOR INITIAL 40 SYSTEM BREACH.
40 2.FULL PROTECTIVE CLOTHING W/HOOD, OREX DELUXE 40 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 40 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
40 3.GLOVES AND A CONTAINMENT DEVICE ARE REQUIRED AS A 40 MINIMUM IN CLEAN AREAS.
40 4.ENGINEERING CONTROLS AS PER RADIATION CONTROL.
40 5.PROVIDE PATH OR CONTAINMENT FOR SYSTEM DRAINAGE, 40 IF NEEDED TO CONTAIN LIQUIDS.
40 45 ****REQUIREMENTS FOR VENTING, SAMPLING OR DRAINING****
45 ********OF THE RCS, CVCS OR WASTE GAS SYSTEM**********
45 45 l.NOTIFY RC PRIOR TO VENTING, SAMPLING OR DRAINING 45 OF THE RCS, CVCS OR WASTE GAS SYSTEM.
45 50 ***********CONT4INATED AREA ENTRIES*************
50 50 1.GLOVES AND SHOECOVERS REQUIRED AS A MINIMUM 50 FOR INSPECTIONS ACTIVITIES.
50 2.FULL PROTECTIVE CLOTHING REQUIRED FOR HANDS ON WORK 50 OR INSPECTIONS THAT REQUIRE CLIMBING/CRAWLING.
50 3.DOUBLE SURGEONS GLOVES MAY BE SUBSTITUTED FOR RUBBER 50 GLOVES WITH RADIATION CONTROL APPROVAL.
50 4.FULL PROTECTIVE CLOTHING, WATER RESISTANT DRESS 50 REQUIRED FOR WET WORK, AND ADDITIONAL DRESS 50 CONTROLS MAY BE REQUIRED BASED ON RC INSTRUCTIONS.
50 5.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.
50 60 ************5OER 20011 REQUIREMENTS*************
60
PASSPORT - TOTAL EXPOSURE SYSTEM RADIATION WORK PERMIT 1111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 liii! 11111 liii 11111 11111 liii! 11111 11111 11111 11111 11111 liii ALARA Task port ID : TIPH900 RWP Number: 00006183 00 wo 01849206 24 01 Page : 4 Facility : RNP 60 l.PRE-JOB BRIEFING REQUIRED.
60 2.RADIATION CONTROL SUPERVISOR & WORK GROUP SUPERVISOR 60 MUST PARTICIPATE IN PRE JOB BRIEFING.
60 3.STAYTIME AND TIME KEEPING REQUIRED WITH GENERAL 60 AREA DOSE RATES GREATER THAN 1000 MREM/HR.
60 4.ADHERE TO WORK INSTRUCTIONS, STAY TIMES, AND SURVEY 60 REQUIREMENTS SPECIFIED IN THE PRE-JOB BRIEFING AND 60 ON ATTACHMENT 10.5 OF HPP-500-3 THAT HAS BEEN 60 PREPARED FOR THE ACTIVITY.
60 5.CONTINUOUS RADIATION CONTROL COVERAGE REQUIRED WHEN 60 THE POTENTIAL GENERAL AREA DOSE RATES OF GREATER 60 THAN 1000 MREM/HR EXIST.
60 70 ********FIRE BRIGADE ENTRY INTO CV**********
70 ***********WITH REACTOR CRITICAL*************
70 70 1.PERI4ISSION FROM SUPERINTENDENT OF SHIFT OPERATIONS 70 IS REQUIRED FOR AN EMERGENCY FIRE BRIGADE RESPONSE 70 INTO THE CV WITH THE REACTOR CRITICAL.
70 2.CONTINUOUS RC COVERAGE REQUIRED.
70 3.PRE-JOB BRIEFING REQUIRED (MAY BE DOCUMENTED AFTER 70 ENTRY IS COMPLETE) 70 4.FIRE BRIGADE TEAM MEMBERS SHALL RESPOND 70 UTILIZING TURNOUT GEAR.
70 5.UTILIZE ELECTRONIC ALARMING DOSIMETERS LOCATED IN 70 FIRE EQUIPMENT CABINET IN THE RCA.
70 6.VERIFY THE ALARMING DOSIMETER IS ON.
70 7.ADMINISTRATIVE DOSE LIMIT: 1000 MREM 70 8.ALARM SETPOINTS: DOSE ALARM 750 MREM 70 DOSE RATE ALARM 10000 MREM/HR 70 9.NO ENTRY INTO CV SUMP WITH REACTOR CRITICAL.
70
- End of Report -
Robinson Nuclear Plant SFPF.WMF Spent Fuel Pit Filter Ar
- Survey # 121410- DatelTime: 1211412010 07:
LOUiA
..____jsoPI LHRA/HPA controlled at locked door 1 IE1 E;J h i÷1ooL__
LHRPI 2 HPAI 10 1
9 1+6001 1+2001 V4001 7 8
\
\ 6) 1÷2001 4
5 11 12 Comments: ****Training Use Only**** Summary of Highest Readings Pre job Survey to Support SFP Filter Replacement Air Sample Taken with H809V #776982 mears ir amp es ipes Several Hot Particles Detected >2 E6 DPM 3) 100000 DPM/100 cm2 ply A/S 1) <30 %DAC Particulate Frisker Bkg. = 60 cpm 9) 60000 DPMI100 cm2 ly A/S 1) <30 %DAC Iodine Tenn. #2 MDA 79 dpm 7) 34000 DPM/100 cm2 ply
- 8) 33000 DPM/100 cm2 ly Wipe 3) 100,000 CCPM
- 11) 30000 DPM/100 cm2 ly Wipe 1) 20,000 CCPM
- 1) 20000 DPM/100 cm2 ly Wipe 2) 10,000 CCPM
- 10) 19000 DPM/100 cm2 Iy Wipe 4) 120 CCPM Symbol Legend (for example only) Type: Job Coverage 4) 15000 DPM/100 cm2 Iy
- 2) 13000 DPM/100 cm2 ly RWP. 5910 2) 10000 DPM/100 cm2 Iy 10 CORdIn Ir Reactor Power= 100% 5) 5000 DPM/100 cm2 ly
- 9. °- ------
6) 3000 DPM/100 cm2 ly (srn..r a5.r iti [jvuip Hot Particles Detected 13) 2000 DPM/100 cm2 ly
- 14) 1200 DPM/100 cm2 ly
--- 5) 1100 DPM/100 cm2 ly inIess otherwise noted, dose rates in mremlhr.
Surveyor: Wes Brand Survey printed on: 0110412011 at: 07:46
Robinson Nuclear Plant Survey 12141 0 Data Point Details - Page 1 of I Additional Information:
Counted by: I Wes Brand 12/14/2010 09:00 WRiTask #: N/A Dose Rate (DR) Object Prefixes I Suffixes:
Work Area Code:!_3600 *
= ContaciHS = Hot Spot ComponentiTag Name_N/A + = 30 cm No prefix=General Area Dose R Tag Suffix Name:!_N/A Suffixes: nNeutron, bBeta Short Name:! N/A Unless otherwise noted, dose rates in mremlhr.
Postings Legend:
RCA=Radiologically Controlled Area CAContamination Area RA=Radiation Area HPA=Hot Particle Area HRA=High Radiation Area RMA=Radioactive Material Area LHRALocked High Radiation Area CRCFEContact Radiation Control For Entry VHRMVery High Radiation Area CRCPEContact Radiation Control Prior To Entry ARA=Airborne Radioactivity Area Instruments Used:
Efficiency No. Model Serial j Probe Serial I Cal Date I Type I /v I P I I 776386 rNA NA 03/29/2011 00:0C DIR N/A N/A N/A 2 LM-177 776080 44-9 NA 10/12/2011 00:0( CIR N/A 0.100 N/A 3 RO-20 778069 NA *NA D/R 08/13/2011 00:0C N/A N/A N/A 4 TennO2 1217320 ITenn NA CIR IN/A 106/30/201100:0(I 10.242 0.221 No.1 Type Value Units Position Notes Smear N/A /i 20001 3
1 DPM/100 cm2 Floor N/A a<MDI PM/100 cm2 2 Smear N/A 13/i 10001 DPM/100 cm2 ball 3 Smear N/A /i 100001 3
1 DPM/100 cm2 Filter Housing N/A (1<MDI DPM/100 cm2 4 Smear N/A 13/y 15001 DPM/100 cm2 /ent valve 5 Smear N/A 13/i 5001 DPM/100 cm2 Fransmitter
) Smear N/A 13/i 300 DPM/100 cm2 P/all 7 Smear N/A 3/y 34001 DPM/100 cm2 Floor N/A a<MD) DPM/100 cm2 8 Smear N/A 13/y 33001 DPM/100 cm2 Floor N/A (X<MDI PM/100 cm2 9 Smear N/A 13/v 6000 PM/100 cm2 Floor N/A a <MD1 DPM/100 cm2 10 Smear N/A 13/y 1900 DPM/100 cm2 loor 11 Smear N/A 13/i 3000 DPM/100 cm2 90w Transmitter N/A a<MDI DPM/100 12 Smear N/A 13/i 1300l DPM/100 ransmitter 13 Smear N/A 13/i 200 DPM/100 :loor 14 Smear N/A 13/i 120 DPM/100 :loor 15 Smear N/A 13/i 110 DPM/100 Zloor Wipe 13/i 20,00 CCPM 9oor 2 Wipe 13/i 10,00 CCPM 900r 3 Wipe 13/i 100,00 CCPM 9oor 4 Wipe 13/y 12 CCPM 900r AirSample %DAC Particulate 3eneral Area Air Sample
%DAC Iodine DR N/A *1500 mRem/hr Zilter Housing N/A ÷1000 mRem/hr DR i N/A 200 mRem/hr DR N/A +600 mRem/hr DR N/A +100 mRem/hr DR N/A +50 mRem/hr DR N/A +25 mRem/hr
)R N/A +200 mRem/hr DR N/A +400 mRem/hr DR N/A +2001 mRem/hr Survey printed on: 0110412011 at: 07:46
Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HB ROBINSON Task No.: 02344101203 Task
Title:
Classify an Emergency Event JPM No.: 2011 NRC JPM Admin SRO A4 K/A
Reference:
G2.4.4i (2.9/4.6)
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:
- This is a DRILL.
- Reactor was shutdown on 1/7/2011 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.
- The plant is in Mode 6 with the core reload in progress.
- Due to the extended outage and support work, the core has been in the Spent Fuel Pool for 42 days.
- During fuel transfer in the SFP, an irradiated fuel assembly became dislodged from the Fuel Handling Tool, drops and rests on the fuel assembly in SFP Rack Location P-i6, leaning against the south SFP wall.
- Bubbles were noted rising from the dropped fuel assembly as the Fuel Handling Building was evacuated lAW AOP-013, Fuel Handling Accident.
- Subsequently, the Refueling SRO reports that the CV cavity level is lowering rapidly due to cavity seal failure.
- SFP Transfer Tube gate valve is bound open.
- R-5 is reading 4OmR/hr and R-14D is reading 2100 cpm.
- Weather conditions: Wind direction is from 100 degrees, Wind speed is 5 mph, Stability Class is D, Precipitation is Zero.
- You are the Shift Manager.
Task Standard: Identifies event as an ALERT per RA2.1 Required Materials: EPCLA-01, EPCLA-04, EAL Matrixes, EPNOT-01,SFP Diagram 2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Job Performance Measure Form ES-C-i Worksheet General
References:
EPCLA-Oi, EPCLA-04, EAL Matrixes, EPNOT-O1, SFP Diagram Handouts: EPCLA-O1, EPCLA-04, EAL Matrixes, EPNOT-O1, SEP Diagram Initiating Cue: Classify the event lAW the EAL matrixes. Upon completion of the event classification, inform the examiner.
This Task is TIME CRITICAL Time Critical Task: YES (15 minutes for classification AND 15 minutes for notification)
Validation Time: 24 minutes 2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 3 of 14 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk )
Start Time: Time Critical Start Time:__________
Performance Step: I Obtain the EAL ALL Conditions and COLD Conditions Matrix Standard: Candidate states where to obtain the EALs.
Examiners NOTE: Provide copies of the EAL Matrix to the candidate.
Comment:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement I
Appendix C Page 4 of 14 Form ES-C-I PERFORMANCE INFORMATION
- Performance Step: 2 Evaluate ALL Conditions EAL Matrix under all conditions. (Step 8.3.1)
Standard: Candidate reviews EAL ALL Conditions Matrix and identifies the following classification:
RA-2.1, Damage to irradiated fuel or loss of water level that has or will result in the uncovering of irradiated fuel outside the Reactor Vessel resulting in increased readings on any of the following radiation monitors:
- R-2, CV Area R-5, Spent Fuel Pit Area
- R-IIIR-12, Process Monitor CV Air and Plant Vent (when sampling CV)
R-14, Plant Vent
- R-21, Fuel Handling Building Upper Level Examiners NOTE:
Comment:
Time Critical Stop Time for EAL Classification: (15 Minutes)
Examiners CUE: Present the candidate with the second cue sheet for the JPM task of completing the Emergency Notification Form and a copy of procedure EPNOT-O1.
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 5 of 14 Form ES-C-i PERFORMANCE INFORMATION Time Critical Start Time for EAL Notification:
Performance Step: 3 Direct the Emergency Communicator to prepare for communication activities in accordance with EPNOT-0i CR/EOF Emergency Communicator. (Attachment 10.6, Step 1.1)
Standard: Candidate informs the Emergency Communicator to prepare for communication activities.
Examiners NOTE:
Examiners CUE: When the candidate has completed the EAL classification, CUE the candidate that he will manually complete an Emergency Notification Form and submit it to the SEC.
The clock starts when you have completed the classification.
Comment:
Performance Step: 4 Obtain EPNOT-01, Attachment 10.7, Nuclear Power Plant Emergency Notification Form.
Standard: Copies Attachment from procedure or pulls it from a file.
Examiners NOTE:
Examiners CUE: The Examiner will provide Attachment 10.7 after the candidate demonstrates that they know how to locate procedures.
Comment:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 6 of 14 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 5 Enter Line 1 information.
Standard: Marks DRILL and Message # 1.
Examiners NOTE: Ensure that DRILL is marked. ACTUAL EVENT is only used during a real emergency.
Comment:
- Performance Step: 6 Enter Line 2 information.
Standard: Marks INITIAL.
Examiners NOTE:
Comment:
- Performance Step: 7 Enter Line 3 information.
Standard: Enters H.B. Robinson as the Site and enters CONFIRMATION PHONE NUMBER.
Examiners NOTE: Identifying the site as H.B. Robinson is critical. Listing the proper confirmation telephone number is NOT critical.
Examiners CUE: When candidate requests the ERO phone list, tell him the Confirmation Phone Number is 843-383-3685.
Comment:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 7 of 14 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 8 Enter Line 4 information.
Standard: Marks ALERT as the Emergency Classification.
Based on EAL # RA2.1 EAL Description Damage to irradiated fuel or loss of water level that has or will result in the uncovering of irradiated fuel outside the Reactor Vessel resulting in increased readings on any of the following radiation monitors:
R-5, Spent Fuel Pit Area ANDIOR R-14, Plant Vent Examiners NOTE:
Comment:
- Performance Step: 9 Enter Line 5, Protective Action Recommendation information.
Standard: Marks NONE.
Examiners NOTE:
Comment:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 10 Enter Line 6, EMERGENCY RELEASE, information.
Standard: Marks Is Occurring.
Examiners NOTE:
Comment:
Performance Step: 11 Enter Line 7, RELEASE SIGNIFICANCE, information.
Standard: Marks Under Evaluation.
Examiners NOTE:
Examiners CUE: If candidate asks, inform him that the Dose Projection Team has NOT provided any data.
Comment:
Performance Step: 12 Enter Line 8, EVENT PROGNOSIS, information.
Standard: Marks Degrading.
Examiners NOTE:
Comment:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement I
Appendix C Page 9 of 14 Form ES-C-i PERFORMANCE INFORMATION
- Performance Step: 13 Enter Line 9, METEROLOGICAL DATA, information.
Standard: Enters data that was given in the initial conditions:
Wind Direction 100 degrees, Wind Speed 5 mph, Precipitation 0, Stability Class D.
Examiners NOTE:
Comment:
- Performance Step: 14 Enter Line 10 INFORMATION.
Standard: Marks Block A, DECLARATION: Enters applicable Date and Time.
Examiners NOTE:
Examiners CUE: Date and time should reflect present date and time.
Comment:
- Performance Step: 15 Enter Line ii information, AFFECTED UNITS.
Standard: Marks Unit 2.
Examiners NOTE:
Comment:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement I
Appendix C Page 10 of 14 Form ES-C-I PERFORMANCE INFORMATION Performance Step: 16 Enter Line 12 information UNIT STATUS.
Standard: Enters Shutdown Time: 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 11712011 Examiners NOTE: Reactor shutdown date and time was given in the initial conditions on the cue sheet.
Examiners CUE:
Comment:
Performance Step: 17 Enter Line 13 Remarks information.
Standard: Enters information describing accident from EAL matrix.
Examiners NOTE: May leave LINE 13, Remarks blank or enter EAL information.
Comment:
- Performance Step: 18 Line 17 APPROVAL by SEC.
Standard: Completes Line 17 with Signature, Title, Time, and Date.
Examiners NOTE:
Comment:
Time Critical Stop Time for EAL Notification: (15 Minutes) 2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 1 1 of 14 Form ES-C-i PERFORMANCE INFORMATION END OF TASK Termination Cue: EAL classification has been determined and notification has been made.
STOP TIME:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
Appendix C Page 12 of 14 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC JPM Admin SRO A4 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
ATTACHMENT 10.7 Pagelofil NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM I .DRlLL J ACTUAL EVENT MESSAGE #
2.INlTlAL FOLLOW-Up NOTIFICATION: TIME_______ DATE I I AUTHENTICATION #______
- 3. SITE: i{A AAJ30i Confirmation Phone #
- 4. EMERGENCY CLASSIFICATION:
UNUSUAL EVENT ALERT JJ SITE AREA EMERQENCY { GEN?AL EMERGENC ON EAL# 2- j L EgRlpTION:\J,4MA4e.
- t-Thdfh 4 LI- qjiL cJ f&
4 )BAED Of- WA1ei tewet L4r X-i Ofr / .fl,. &, t1k4iV4 c I Vli4d íA 4r L U 14tc i, k?4 d-/AJ O !J /1-A/Ii ! tLiA72 -
- 5. PROTEGKE ACTION REObMMENDATIONS:
EVACUATE SHELTER CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.
MOTHER
- 6. EMERGENCY RELEASE: None Occurring Has Occurred Not j Within normal Above normal operating Under
- 7. RELEASE SIGNIFICANCE:
applIcable operating limits limits evaluation
- 8. EVENT PROGNOSIS: Improving Stable VDegrading
- 9. METEOROLOGICAL DATA: Wind Direction* from degrees Wind Speed* - mph
(*May not be available for Initial Precipitation* 0 Stability Class*
Notifications) 1O.XDECLARATION J TERMINATION Time AiIJi) Date II. AFFECTED UNIT(S): Eli I1
- 12. UNIT STATUS: UI Power Shutdown at Time Date _I I_
(Unaffected Unit(s) Status Not Required for Initial Notifications) U2 0 Power Shutdown at Time 1.3 £70 Date .,Lí 7 1L Power Shutdown aTime Date I /
- 13. RA 4sJ4/rf1 7 J 4
/ - ,r , idq)
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
- 14. RELEASE CHARACTERIZATION: TYPE: Elevated j Mixed Ground UNITS: Ci J CiIsecj 1 iCi/sec MAGNITUDE: Noble Gases:__________ lodines:___________ Particulates:___________ Other:
FORM: Airborne Start Time Date _I I_Stop Time Date _I I..
Liquid Start Time Date _I I_Stop Time Date _I /_
j
- 15. PROJECTION PARAMETERS: Projection period: Estimated Release Duration Projection performed: Time Date _I /_._
Site boundary 2 Miles 5 Miles 10 les
(
- 17. APPROVED BY: fd(
4 (4 4L Title Time /i}ilti) t9 4
DateJ L
NOTIFIED BY:_______________ RECEIVED BY: Time Date_/ I_
EPNOT-01 Rev. 35 Page 34 of 61
Appendix C Page 13 of 14 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
- This is a DRILL.
- Reactor was shutdown on 1/7/2011 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.
- The plant is in Mode 6 with the core reload in progress.
- Due to the extended outage and support work, the core has been in the Spent Fuel Pool for 42 days.
- During fuel transfer in the SFP, an irradiated fuel assembly became dislodged from the Fuel Handling Tool, drops and rests on the fuel assembly in SFP Rack Location P-16, leaning against the south SFP wall.
- Bubbles were noted rising from the dropped fuel assembly as the Fuel Handling Building was evacuated lAW AOP-01 3, Fuel Handling Accident.
- Subsequently, the Refueling SRO reports that the CV cavity level is lowering rapidly due to cavity seal failure.
- SFP Transfer Tube gate valve is bound open.
- R-5 is reading 4OmR/hr and R-14D is reading 2100 cpm.
- Weather conditions: Wind direction is from 100 degrees, Wind speed is 5 mph, Stability Class is D, Precipitation is Zero.
- You are the Shift Manager.
INITIATING CUE: Classify the event lAW the EAL matrixes. Upon completion of the event classification, inform the examiner.
This Task is TIME CRITICAL 2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement I
Appendix C Page 14 of 14 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS: Emergency event has just been declared by the Control Room Site Emergency Coordinator (SEC).
INITIATING CUE: The Emergency Communicator is NOT available. You, as the Control Room Site Emergency Coordinator (SEC), must manually complete the Emergency Notification Form (ENF) from procedure EPNOT-O1, CR/EOF Emergency Communicator.
This task is TIME CRITICAL.
2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1
CONTAINMENT EXISt UPENDEt UPENDING FRAME WINCH WATER LEVEL SPENT FUEL STORAGE PIT PENT FUEL STORAGE RACKS A
CONVEYOR TRACKS FUEL TRANSFER TUBE FUEL TRANSFER SYSTEM
ATTACHMENT 10.3 Page 1 of I SPENT FUEL POOL STORAGE LOCATION DATA SHEET NORTH LOCKING DEVICE HANDRAIL PRSTUWX J K L M N P R S 1:
N /18 LI LI LI LI LI LI LI 1 19 CASK AREA 20 LI LI LI LI LI LI LI 2 21
/ N22 LI LI LI LI LI LI LI LI 3 23 ABCDEFGH 24 ABCDEFGH C LI LI LI LI LI LI LI LI 4 25 LI LI LI LI LI LI LI LI LI LI LI LI 5 26 27 LI LI LI LI LI LI LI LI LI LI LI LI 6 LI LI LI LI LI LI LI LI LI LI LI LI 7 31 LI LI LI LI LI LI LI LI LI LI LI LI 8 EAST LI LI LI LI LI LI LI LI LI LI LI LI 9 LI LI LI LI LI LI LI LI LI LI LI 10 36 LI LI LI LI LI LI LI LI LI LI LI 11 38 39 LI LI LI LI LI LI LI LI LI LI LI 12 40 41 LI LI LI LI LI LI LI LI LI LI LI 13 42 43 LI LI LI LI LI LI LI LI LI LI LI 14 44 45 LI LI LI LI LI LI LI LI LI LI LI 46 47 LI LI LI LI LI LI LI LI LI 48 B F G H JK L ABCDEFG :j KLM A BCDE FG] J KLM SOUTH I
FMP-021 I Rev. 18 I Page 19 of 22