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{{#Wiki_filter: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 JPMAdmin 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-012, Manual Determination of Shutdown Margin Boron Concentration Station Curve Book, Section 1 Cycle Data
 
Calculator Straight Edge General
 
==References:==
FMP-001 FMP-012 Station Curve Book, Section 1  Cycle Data Handouts:          FMP-001 FMP-0i2 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-0i2.
Time Critical Task: NO Validation Time:    60 minutes 2011 NRC JPM Admin 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 12                        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.
q  Performance Step: I      Complete Section I of Attachment 7.1 Standard:                Candidate completes the information needed for Section I:
Date / 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 12                      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:
J  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 XI, 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 12                      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)
[15697] +/- 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 1
 
Appendix C                              Page 7 of 12                      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 pcm.
Examiners NOTE:    Candidate should use Curve or Table I .3C based on cycle exposure time (EOL). Value read from curve is 1870 pcm and extrapolated from table is 1855.5 pcm.
Comment:
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.
.1 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]
pcm.
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-i                    NUREG 1021, Revision 9, Supplement 1
 
Appendix C                              Page 8 of 12                        Form ES-C-i PERFORMANCE INFORMATION J  Performance Step: 7  Complete Section VU 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] +/- 9 pcm.
Examiners NOTE:
Comment:
J  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 1
 
Appendix C                              Page 9 of 12                          Form ES-C-i PERFORMANCE INFORMATION q    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] +/- 9 pcm Inserted/Misaligned Worth (Step VI) = [850] pcm Power Defect Worth (Step V)      = [1855.5] +/- 25 pcm Inop/Untrip Rod Worth (Step VIII)      [0]
Available Shutdown Margin    =  [3162.5] +/- 16 pcm Examiners NOTE:
Comment:
..I 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-00i), the required SDM is              X 1000 pcm/%=          pcm.
Standard:            Candidate determines from FMP-OOi, Figure 5.0 that required SDM is [t60]% (+/- 0.05%) and calculates [1600] pcm. This used an RCS boron concentration of 138 ppm and read Figure 5.0 for Mode I operation.
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-i                  NUREG 1021, Revision 9, Supplement I
 
Appendix C                            Page 10 of 12                      Form ES-C-i PERFORMANCE INFORMATION J  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 3162.5 pcm available shutdown margin to the 1600 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 11 of 12                    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:
Numberof Attempts:
Time to Complete:
Question Documentation:
Question:
 
===Response===
Result:                      SAT            UNSAT Examiners Signature:                                Date:
2011 NRC JPMAdmin RO-SRO Al-i                  NUREG 1021, Revision 9, Supplement 1
 
Appendix C                          Page 12 of 12                      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-001, 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 JPMAdmin RO-SROAI-l                  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:==
G2.1.25    (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 A1-2                                NUREG 1021, Revision 9, Supplement I
 
Appendix C                    Job Performance Measure                Form ES-C-i Worksheet Time Critical Task: NO Validation Time:    12 minutes 2011 NRC JPMAdmin ROAI-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:
1 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 I  Performance Step: 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. (Step 8.4.1.4)
Standard:            Interpolates from Steam Tables and logs:
43.7/100 x (655.89649.45)    + 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:
q  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 ROA1-2                          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:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
 
===Response===
Result:                      SAT            UNSAT Examiners Signature:                                  Date:
2011 NRC JPM Admin RO Al -2                    NUREG 1021, Revision 9, Supplement 1
 
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 JPMAdmin ROA1-2                        NUREG 1021, Revision 9, Supplement 1
 
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CONTINUOUS USE                                  Section 8.4 Page 1 of 1 8.4  INFREQUENT OPERATIONS                                                        IT 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.
: 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.                                  °F Initials              Name(Print)                          Date Performed By:
Approved By:
Unit 2 Superintendent Shift Operations              Date OP-307                                    Rev. 13                          Page 15 of 18
 
4,sJvp CONTINUOUS USE                                  Section 8.4 Page 1 of 1 8.4  INFREQUENT OPERATIONS                                                        DJiT 8.4.1  Manual Calculation of Margin to Saturation
: 1. This revision has been verified to be the latest revision available.
            .
              /W Name ( rint)          Initial            Signature  (
7d Date  /
: 2. Determine primary pressure using the lowest vad pressure indication.                                        psig
: 3. Convert pressure to absolute by adding 14.7 psto value        _-y determined in Step 8.4.1.2.            Z2-47psia          (_AL
: 4. Enter, from the Saturated Steam Tables, the saturation temperature corresponding to the pressure shown in Step 8.4.1.3 to determine the correspondng temperature.                              33ZJOF
: 5. Determine primary temperature using the highest valid core exit thermocouple temperature 0  n.
9 indicati
: 6. Subtract the temperature of Step 8.4.1.5 from the temperature of Step 8.4.1.4 to determine tl)e marg)n to saturation in &deg;F.                            OF        <f/ L..
Is                  me(Print)                        Date Performed By:                                                              ct4y Approved By:
Unit 2 -  Superintendent Shift Operations            Date OP-307                                    Rev. 13                        Page 15 of 18
 
Appendix C                                      Job Performance Measure                          Form ES-C-i Worksheet 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&ID 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:              The CRS has directed you to 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 2011 NRC JPM Admin RO A2                                        NUREG 1021, Revision 9, Supplement I
 
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:
2011 NRC JPM Admin RO A2                              NUREG 1021, Revision 9, Supplement 1
 
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-29i, Charging Pump A to Seal Injection CLOSED
                                                                                -
* CVC-277C, Charging Pump A Recirc Root        CLOSED OR
* CVC-275C, Charging Pump A Recirc CLOSED -
Examiners NOTE:      Vent and drains are NOT required to be included.
Valve CVC-277C OR CVC-275C will isolate the recirc line; only I valve is required to be identified.
Comment:
* Performance Step: 3  Determine the power supply to Charging Pump A.
Standard:            Candidate determines that Charging Pump A power supply is 480V Bus DS.
Examiners NOTE:      Charging Pump A power supply is located in EDP-002, Section 7.0, 480V Bus DS.
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:
2011 NRC JPM Admin RO A2                          NUREG 1021, Revision 9, Supplement 1
 
Appendix C                              Page 4 of 6                    Form ES-C-i PERFORMANCE INFORMATION END OF TASK Terminating Cue:        Charging Pump A valve boundaries and power supply have been identified as directed.
STOP  TIME:
2011 NRC JPM Admin RO A2                        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 RO A2 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 A2                      NUREG 1021, Revision 9, Supplement 1
 
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:        The CRS has directed you to identify the pump boundary valves and motor breaker to expedite the pump isolation and termination of the leakage.
2011 NRC JPM Admin RO A2                          NUREG 1021, Revision 9, Supplement 1
 
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.
* The FIN Team has requested a clearance to change the SEP Filter.
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 and 5519.
SFP Filter area survey map.
General
 
==References:==
RWPs 5498, 5499 and 5519.
SFP Filter area survey map.
Handouts:                    RWPs 5498, 5499 and 5519.
SEP 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.
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 #5519 states that continuous RC coverage is required.
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-i pre-job briefing is required.
Comment:
END OF TASK Termination Cue:    When the candidate has determined the appropriate RWP and restrictions from the survey map, the evaluation of this JPM is complete.
STOP TIME:
201 i 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-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.
* The FIN Team has requested a clearance to change the SFP Filter.
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 AJI1C I 11111 11111 11111 11111 11111 11111 11111 liii!11111 1111111111 11111 11111 11111 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                                  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 Hold Point Description Nbr 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 RADIATION WORK PERMIT 1111111111111111111111111111111111111111111111111111111111111 1111111111111111111111111111111111111111111111111 ALARA 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 THAN OR 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 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        PAMTRX 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    l.PREJOB 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 iA7OE..1C PERJVIIr.[
11111111111 11111 11111hIll 11111 11111 11111 11111 11111 1111111111111111111111111111111111111111111111111111111111 ALARA Task 4ort 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 1 INCH)                ***
40    ****    CONTAMINATED SYSTEM BREACH              (LINES            >
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 SO        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
 
PASSPORT  - TOTAL EXPOSURE SYSTEM VO1{1( PE1.i1II I 11111 1111111111 11111 11111 11111 11111 11111 11111 1111111111 11111 1111111111 11111 11111 11111 11111 1(111 11111 11111 liii ALAR Task port ID    : TIPH900        RWP Number:              00005498                    01 Page        :      4              Facility  :        RNP 60                            DOSE RATE ALARM                                    10000 MREM/HR 60    9.NO ENTRY INTO CV StJMP WITH REACTOR CRITICAL.
60 70    ****REQUIREMENT5 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 I}II..1IOf \O11( PEIJlIf 1111111111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 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--Distance--I                                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 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 O1{J( PII1IIrr I 11111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111111111111111111111111111111111111111111111111111111111 ALARA Task port  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.
5 S
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.PREJOB 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 i).EI r
1  If V7JI{1( PER.]NIIT 111111 11111 11111 11111liii! 11111 11111 11111 11111 11111 11111 11111 liii!11111 11111 11111 I 11111 11111 11111 11111 liii 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    ****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 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 1iIIi.IIr O1{I( PIIJv1T1 111111 IIII 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 111111111 ALARA Task iport 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 SUMP WITH REACTOR CRITICAL.
70 End of Report    -
 
PASSPORT      - TOTAL EXPOSURE SYSTEM 1J4..I[I.rf[Jpb \VOII( PER.]VIIT                    11111111111111111111111111 11111 1111111111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 III!
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: MAIJNIP0l                          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              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 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 RADIATION WORK PERMIT 11111111111 IIII 1111111111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 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 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 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
.IIA1ION 1
: 1.                R1( PER.I1IrF 111111111111111111111111111111111111111111111111111 liii!11111 liii! 11111 11111 [1111111111111111111111111111 III ALARA Task port ID    : TIPH900          RWP Number:          00005519                01 Page        :        3            Facility  :      RNP 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 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    ****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    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 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 ORi( PiiiiIr 1
                \
1111111111111111111111111111111111111111111111111111111111111 11111 11111 11111 liii!11111 11111 1111111111 11111 liii ALARA Task ort ID    : T1PH900        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 PEE-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    -
 
Robinson Nuclear Plant SFPF.WMF Spent Fuel Pit Filter Ar
                    -                                                              Survey # 121410-        Date/Time: 12/1412010 07:
LHRA/HPA controlled at locked door Comments: ****Training Use OnIy****
Pre-job Survey to Support SEP Filter Replacement.
Air Sample Taken with H809V #776982.
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 DPM/100 cm2 l/i 3    A/S 1) <30 %DAC Iodine Tenn. #2 MDA 79 dpm                                                  7) 34000 DPM/100 cm2 ly
: 8) 33000 DPM/100 cm2 ly  Wipe 3) 100,000 CCPM
: 11) 30000 DPM/100 cm2 lIly Wipe 1) 20,000 CCPM
: 1) 20000 DPM/100 cm2 lIly Wipe 2) 10,000 CCPM
: 10) 19000 DPM/100 cm2 ply  Wipe 4) 120 CCPM Symbol Legend (for example only)                  Type: Job Coverage            4) 15000 DPM/100 cm2 lIly
: 12) 13000 DPM/100 cm2 ply RWP: 5910                    2) 10000 DPM/100 cm2 lIly I-iS O      1+ot fipsi 1 tLJ
        -j--- Contact Reading cm Reading nC
                                          .1 I            Reactor Power  =  100%        5) 5000 DPM/100 cm2 Iy
[2OEOencraI .cca                            liIP                                    6) 3000 DPM/100 cm2 ly i5 r Sample          RIIA          1pe  Hot Particles Detected      13) 2000 DPM/100 cm2 ly
: 14) 1200 DPM/100 cm2 ly
: 15) 1100 DPM/100 cm2 lIly Unless otherwise noted, dose rates in mremlhr.
Surveyor: Wes Brand Survey printed on: 1211512010 at: 07:47
 
Robinson Nuclear Plant Survey 121 41 0 Data Point Details Page 1 of I          -
Additional Information:                                                                Counted by:    I Wes Brand 12/14/2010 09:00 WR!Task #: j_N/A                                                              Dose Rate (DR) Object Prefixes I Suffixes:
Work Area Code:I_3600                                                            *
                                                                                                = ContaclHS = Hot Spot ComponentlTag Name_N/A                                                                  + = 30 cm No prefixGeneral Area Dose R Tag Suffix Name:I_N/A                                                                            Suffixes: nNeutron, bBeta Short Name: N/A                                                              Unless otherwise noted, dose rates in mremlhr.
Postings Legend:
RCA=Radiologically Controlled Area                                      CA=Contamination Area RMRadiation Area                                                        HPMH0t Particle Area HRAHigh Radiation Area                                                  RMA=Radioactive Material Area LHRMLocked High Radiation Area                                          CRCFEContact Radiation Control For Entry VHRA=Very High Radiation Area                                            CRCPEContact Radiation Control Prior To Entry ARA=Airborne Radioactivity Area Instruments Used:
Eftlcienc No.          Model                  Serial              Probe          I      Serial I    Cal Date    I Type I                        a I  6112B                776386              NA                          NA            03/29/2011 00:0C  DIR    N/A      N/A      IN/A 2  LM-177                776080              449                        NA            10/12/2011 00:OC  CIR    N/A      0.100    rN/A 3  RO-20                778069                NA                        NA            08/13/2011 00:0(  D/R    N/A      N/A      N/A 1217320              Tenn                        NA          106/30/201100:OCI    CIR    N/A      0.242    0.221 No.        Type    IiL      Value                    Units                        Position                                Notes Smear      NIA        /1i uvj 3                rO  cm2      Floor N/A            cL<MD)    JPM/100 cm2 2        Smear      N/A          3/y 10001    JPM/100 cm2        Nail 3        Smear      N/A      13/i 100001    JPM/100 cm2        Filter Housing N/A            a<MD)      JPM/100 cm2 4        Smear      N/A          13/i 15001  )PM/100 cm2        ent valve 5        Smear      N/A            /i 5001 3
1          JPM/100 cm2          ransmitter 6        Smear      N/A            y 3001    )PM/100 cm2        Vail 7        Smear      N/A          13/i 34001  )PM/100 cm2        Floor N/A            cL<MD      JPM/100 cm2 8        Smear      N/A          13/y 33001  JPM/100 cm2        Floor N/A                      JPM/100 cm2 9        Smear      N/A          13/i 60001  JPM/100 cm2        Floor N/A            a<MD      JPM/100 cm2 10      Smear      N/A          13/i 1900    DPM/100 cm2          loor 11      Smear      N/A          /i 3000 3
1            JPM/100 cm2        90w Transmitter N/A            o<MD      DPM/100 cm2 12      Smear      N/A          13/i 1300    DPM/100 cm2          ransmitter 13      Smear      N/A            13/i 200  DPM/100 cm2        900r 14      Smear      N/A            13/i 120  DPM/100 cm2        900r 15      Smear      N/A            13/i 110  DPM/100 cm2        900r Wipe                13/i 20,00    CCPM              Floor 2        Wipe                13/i 10,00    CCPM              Floor 3        Wipe              13/i 100,00      CCPM              Floor 4        Wipe                      13/i 12  CCPM              Floor AirSample                          <3( %DAC Particulate  Seneral Area Air Sample
                                          <3( %DAC Iodine DR          i      N/A              *1500 mRem/hr              Filter Housing N/A              +1000    mRem/hr DR          i      N/A                  200  mRem/hr DR          y      N/A                +600  mRem/hr DR                  N/A                +100  mRem/hr DR          i      N/A                  +50  mRem/hr DR          i      N/A                  +25  mRem/hr DR          i      N/A                +200  mRem/hr DR          i      N/A                +400  mRem/hr DR          i      N/A                +200  mRem/hr Survey printed on: 1211512010 at: 07:47
 
Appendix C                                Job Performance Measure                    Form ES-C-i Worksheet Facility:              HB ROBINSON                            Task No.:    01001101601 Task Title:            Perform Shutdown Margin                JPM No.:    201 1 NRC JPM Admin Calculation lAW FMP-012                              RO-SRO Al-i K/A
 
==Reference:==
G2.1.37 (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-001, 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-OOi, 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-0i2 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 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 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 12                      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.
q  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 NOTES 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 12                      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 Xl, Attachment 7.1
[NO] Further verification of SDM is warranted, complete Sections IV through XI, 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 12                    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)
[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 JPM Admin RO-SRO Al-i                  NUREG 1021, Revision 9, Supplement 1
 
Appendix C                              Page 7 of 12                      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 pcm.
Examiners NOTE:    Candidate should use Curve or Table 1.3C based on cycle exposure time (EOL). Value read from curve is -1870 pcm and extrapolated from table is 1855.5 pcm.
Comment:
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.
J  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]
pcm.
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-i                      NUREG 1021, Revision 9, Supplement 1
 
Appendix C                              Page 8 of 12                        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] +/- 9 pcm.
Examiners NOTE:
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 [NIA]
Examiners NOTE:
Comment:
2011 NRC JPM Admin RO-SRO Al-i                    NUREG 1021, Revision 9, Supplement 1
 
Appendix C                              Page 9 of 12                          Form ES-C-i PERFORMANCE INFORMATION q  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] +/- 9 pcm Inserted/Misaligned Worth (Step VI) = [850] pcm Power Defect Worth (Step V)    = [1855.5] +/- 25 pcm Inop/Untrip Rod Worth (Step VIII) = [0]
Available Shutdown Margin      [3162.5] + 16 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 10 of 12                      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 3162.5 pcm available shutdown margin to the 1600 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 corn plete.
STOP TIME:
2011 NRC JPMAdmin RO-SRO Al-i                  NUREG 1021, Revision 9, Supplement 1
 
Appendix C                            Page 11 of 12                    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
 
Appendix C                            Page 12 of 12                      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-001, 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.:  02119101401 Task Title:            Determine the Actions Necessary        JPM No.:    2011 NRC JPM Admin to enter Mode 4 From Mode 5                        SRO AI-2 K/A
 
==Reference:==
G2.1.23          (4.3/4.4)
Examinee:                                                  NRC Examiner:
Facility Evaluator:                                        Date:
Method of testing:
Simulated Performance:                                      Actual Performance:      X Classroom          X      Simulator          Plant READ TO THE EXAMINEE 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 -1 2, 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 AI-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-001-12, 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 SRO Al -2                        NUREG 1021, Revision 9, Supplement I
 
Appendix C                                    Page 3 of 7                        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:
* Performance Step: 2        Compare Attachment 10.2 to Initial Conditions: RCS LEAKAGE DETECTION INSTRUMENTATION. (ITS LCO 3.4.15)
Standard:                  Determines that there is NOT 1 Containment atmosphere radioactivity monitor operable.
Examiners NOTE:            R-11 and 12 are inoperable to replace the monitor flow meter.
Comment:
* Performance Step: 3        Compare Attachment 10.2 to Initial Conditions: RWST (ITS LCO 3.5.4)
Standard:                    Determines that RWST boron is out of specs high at 2450 ppm boron.
Examiners NOTE:            Maximum RWST boron concentration is 2400 ppm.
Comment:
2011 NRC JPM Admin SRO Al -2                            NUREG 1021, Revision 9, Supplement 1
 
Appendix C                            Page 4 of 7                        Form ES-C-I PERFORMANCE INFORMATION
* Performance Step: 4  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-1 and E-2. CCW Pump A is powered from 480V Bus DS.
Comment:
* Performance Step: 5  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: 6  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:
2011 NRC JPM Admin SRO Al -2                  NUREG 1021, Revision 9, Supplement 1
 
Appendix C                          Page 5 of 7                      Form ES-C-i PERFORMANCE INFORMATION 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 JPMAdmin SROA1-2                  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 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 SRO Al -2                    NUREG 1021, Revision 9, Supplement 1
 
Appendix C                                Page 7 of 7                      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-001-12, 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-001-12, 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 Al -2                      NUREG 1021, Revision 9, Supplement 1
 
ATTACHMENT 10.2 Page 1 of 8 2000 TO 350&deg; (MODE 4) MEL (Prior to exceeding 200&deg; F (Entering MODE 4))
CONTINUOUS USE This revis  n has been verified to be the latest revision available.
M EL Name (Print)              Initial                  Signatu&#xe7;e                    Date /
Date:  7id47                    Shift: Tc/CO EQUlPMNT                  REFERENCE          NUMBER          MINIMUM TO GO ABOVE OPERABLE                      200&deg;F (MODE 4)
RCS LOOPS                          ITS LCO                          2 Loops or Trains (RCS/RHR) 3.4.6                                        OPERABLE AND
                                                          /        1 Loop or Train in operation RCS OPERATIONAL LEAKAGE            ITS LCO                          RCS Operational Leakage 3.4.13                          shall be limited to:
No pressure boundary leakage
                                                    )/-    5fri.        1 gpm unidentified leakage 10 gpm identified leakage 75 gpd primary to t.2              secondary leakage through any one steam generator RCS PRESSURE ISOLATION            ITS LCO                  j                      All VALVES (PlVs)                      3.4.14 A  ( (        (except for valves in the RHR System)
OMM-00112                                    Rev. 68                              Page 17 of 63
 
ATTACHMENT 10.2 Page 2 of 8 2000 TO 350&deg; (MODE 4) MEL EQUIPMENT      REFERENCE        NUMBER        MINIMUM TO GO ABOVE 200&deg;F OPERABLE                  (MODE 4)
RCS LEAKAGE DETECTION    ITS LCO                      -  1 Containment Sump Level INSTRUMENTATION          3.4.15                          monitor 1 Containment Atmosphere Radioactivity monitor 1 Containment Fan Cooler
                                            &#xa3;f-/
 
Condensate Flow Rate monitor CHEMICAL AND VOLUME      ITS LCO              2      -  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
                                      ,
gpm RCP B 9,gpm RCP C
                                            /gprn ECCS                    ITS LCO 3.5.3
                                      / ,cJJ f      I RHR Train AND 1 SI Train OPERABLE RWST                    ITS LCO            .    %    300,000 gallons (91%)
3.5.4 2,/&ppm            l950ppmand2400ppm C        &deg;F    45&deg;Fand100&deg;F CONTAINMENT              ITS LCO          A                    OPERABLE 3.6.1 CONTAINMENT AIR LOCK    ITS LCO                                OPERABLE 3.6.2 CONTAINMENT ISOLATION    ITS LCO                                      All VALVES                    3.6.3          rf( ,
CONTAINMENT PRESSURE    ITS LCO                psig    -0.8 psig AND +1 .0 psig 3.6.4 CONTAINMENTAIR TEMPERATURE ITS LCO 3.6.5 QiL      &deg;F              120&deg;F OMM-001-12                      Rev. 68                              Page 18 of 63
 
ATTACHMENT 10.2 Page3of8 2000  TO 350&deg; (MODE 4) MEL EQUIPMENT                REFERENCE          NUMBER        MINIMUM TO GO ABOVE 200&deg;F OPERABLE                      (MODE 4)
CONTAINMENT SPRAY AND                ITS LCO                                2 CV Spray Trains COOLING SYSTEMS                        3.6.6                                        AND 2                2 CV Cooling Trains SPRAY ADDITIVE TANK                  ITS LCO 3.6.7
                                                          /7 W I
                                                                %    -  2505 gallons (32%)
c        %    -  30% NaOH ISOLATION VALVE SEAL                  ITS LCO                  psig
* 49 psig as indicated WATER (IVSW) SYSTEM                    3.6.8                                locally on P1-1910 2 2    %      85 gallons (49&deg;ib)
IL/i
                                                        /        /  All manual valves and I              both automatic valves AUXILIARY FEEDWATER                  ITS LCO                                  1 AFW Flow Path (AFW) SYSTEM (when a S/G                3.7.4              2                        AND is being used for heat removal)                                                1 MDAFW Pump 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)
(
SW Backup OPERABLE COMPONENT COOLING                    ITS LCO                              2 Trains powered from WATER (CCW) SYSTEM                      3.7.6      A              /  Emergency Power supplies RHV 6                        (B and C pumps)
SERVICE WATER SYSTEM                  ITS LCO                                      2 Trains (SWS)                                  3.7.7                                        AND Y&fA              Turbine Bldg Loop Isolation OiL                valves OPERABLE ULTIMATE HEAT SINK (UHS)              ITS LCO          12f      ft    Water level 218ft 3.7.8                    &deg;F    SWS97&deg;F
* Actual ITS is 46.2 psig based on containment design pressure of 42 psig per EC 3604.
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 Page4of8 2000 TO 350&deg; (MODE 4)
EQUIPMENT              REFERENCE            NUMBER      MINIMUM TO GO ABOVE 200&deg;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        ,
I,uCIg  0.1 C/g DOSE EQUIVALENT ACTIVITY                          3.7.15                                  IODINE-131 STARTUP TRANSFORMER              ITS LCO              1                        1 3.8.1.a DIESEL GENERATORS                ITS LCO                                        2 3.8.1.b                                LCO3.0.4.b N/A DIESEL FUEL OIL AND              ITS LCO                  DFO    19,000 gallons available STARTING AIR                        3.8.3                            from DFO Storage tank
                                                  / 72YOgal Unit 1  15,000 gallons available from Unit 1 IC Turbine Fuel
                                                  ,
Oil Storage tanks 3al EDG A    EDG Air Receivers 210 psig Z3(2      psig EDG B Z 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          f / VDC      -  MCC-A Voltage> 126 VDC
                                                  /o VDC        -  MCC-8 Voltage> 126 VDC OMM-001-12                                Rev. 68                                Page 20 of 63
 
ATTACHMENT 10.2 Page 5 of 8 2000 TO 350&deg; (MODE 4)
EQUIPMENT                REFERENCE        NUMBER        MINIMUM TO GO ABOVE 200&deg; F OPERABLE                    (MODE 4)
AC INSTRUMENT BUS                  ITS LCO SOURCES                              3.8.7        /f 9  VAC      *InveerA Voltage> 114 VAC
                                                    //  VAC      *Inveer B Voltage> 114 VAC Constant Voltage Transformers (CVT) I and 2 4160V BUSSES 2 AND 3              ITS LCO 3.8.9              VAC      *4KV Bus 2 Voltage  > 3.2KV 2OvAc 1
(                  *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 - ELV3O2IA 480V El AND E2                      ITS LCO                        480V Bus E-l Voltage 3.8.9              VAC        (lowest phase) > 440 VAC 19    ZVAC 480V Bus E-2 Voltage (lowest phase) > 440 VAC
* It is expected the Inverter AND 4KV Bus voltages will at least meet the following:
Inverter voltage between 118VAC 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&deg; (MODE 4)
EQUIPMENT    REFERENCE      NUMBER  MINIMUM TO GO ABOVE 200&deg;F OPERABLE              (MODE 4)
AC INSTRUMENT BUSSES  ITS LCO                  Energized by normal power 3.8.9                              supply Train A:
480V Bus E-1 breaker, CMPT NO. 21A, FEED TO MCC-5 (NORM POWER) &
MCC-16, closed MCC-5 breaker, CMPT NO.
4BL, FEED TO INSTRUMENT BUS 1, closed Distribution Panel A, Circuit y
1 1, INVERTER A, closed Instrument Bus No. 1, Circuit 10, INSTRUMENT BUS 6,
                                  /d          closed Instrument Bus No. 2, Circuit 11, INSTRUMENT BUS NO.
(/          7A AND 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 INSTRUMENT BUS 4,
                                  /(            closed Instrument Bus No. 3, Circuit 25, INSTRUMENT BUS (A
NO. 8, closed Instrument Bus No. 4, Circuit 12, INSTRUMENT BUS NO. 9A and 9B, closed OMM-001-12                    Rev.68                        Page22of63
 
ATTACHMENT 10.2 Page7of8 2000 TO 350&deg; (MODE 4) MEL EQUIPMENT                REFERENCE        NUMBER      MINIMUM TO GO ABOVE 200&deg;F OPER,BLE                    (MODE 4)
RCS VENT PATH                        TRMS 3.2    2 dt        -    Reactor Head RC-567 and
                                                                                      -
                                                    /pe L              RC-568 OPERABLE,
                                                  ,&A                CLOSED, Power Removed 2_ / j            PZR Steam Space RC-569 cfc.cc
                                                                  -                        -
and RC-570 OPERABLE,
                                                  ,4i,f, /&n e    &#xa3;CLOSED, Power Removed RCS Vent Path valve RC-571 and RC-572 CLOSED OXYGEN (PRIMARY)                    TRMS 3.5.a  5if ,4S                  <0.1 ppm CHLORIDE (PRIMARY)                  TRMS 3.5.b  52( M/2f                    <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
                                                      .  (    %  together shall contain a total of Z/,r7ppm              3080 gallons (42%)
                                                              &deg;F                  AND Tank B          Boron Concentration 3q-      %          20,000 ppm and i.,O97ppm          22,500 ppm AND 145&deg;F
                                                        /4&deg;F BORIC ACID TANKS HEAT              TRMS 3.6.c                                      2 TRACING PRIMARY WATER STORAGE              TRMS 3.6.d                %        30,000 gallons (45%)
TANK SNUBBERS                          TRMS 3.18            //        All safety-related snubbers (34)
                                                      /17 1                shall be OPERABLE APPENDIX R PATHWAYS                1OCFR5O,            /                    Pathways clear CHECKED                            Appendix R (1) TRMS 3.5.a is N/A when RCS and Pressurizer temperature are both <250&deg; 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 c9mplete, acceptable, and entered in Autolog.
                                                                        /4 Signature                    Date E1M-001-12                                  Rev. 68                              Page 23 of 63
 
ATTACHMENT 10.2 Page8of8 2000 TO 350&deg; (MODE 4) MEL List any Mode Clearances in place:
thA Completed by:                                      2 7L4 Date
                                                                  /
Reviewed by:
Shift Manager        Date OMM-001-12                                Rev. 68              Page 24 of 631
 
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.
* The RO has completed QPTR calculation. The highest quadrant power tilt value is 1.055.
* AFD is within limits.
* AUTOLOG is NOT available.
Task Standard:              Enters correct ITS Action Statements, makes log entry, and prioritizes actions.
Required Materials:        Classroom/Simulator/Plant location with Control Room references General
 
==References:==
Improved Technical Specifications OMM-001-8, Control of System and Equipment Status, Revision 44 OMM-001 -11, Logkeeping, Revision 46 2011 NRC JPM Admin SRO A2                                    NUREG 1021, Revision 9, Supplement I
 
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.
* Make any necessary log entries.
* Identify the highest priority action.
Time Critical Task: NO Validation Time:    20 minutes 2011 NRC JPM Admin SRO A2                            NUREG 1021, Revision 9, Supplement I
 
Appendix C                                    Page 3 of 7                      Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Examiners NOTE:          Performance Steps 1, 2, 3, and 4 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 1
 
Appendix C                                Page 4 of 7                        Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3  Make handwritten log entry for misaligned rod lAW OMM-001 -11.
Standard:
* ITS 3.1.4 Condition B Brief description of event, required action and associated time limit: Control rod is misaligned from bank by> 7.5 inches. [Align rod to bank within one hour from discovery time or carry out actions beginning with Condition B, B.2.1.1]
Examiners NOTE:    Examiner can have candidate describe the brief description of event information rather than to copy required actions from Technical Specifications into the log.
Comment:
Performance Step: 4  Make handwritten log entry for QPTR exceeding 1.02.
Standard:
* ITS 3.2.4 Condition A Brief description of event, required action and associated time limit.
* Misaligned control rod caused QPTR to exceed 1.02 (1.055).
[Reduce thermal power to 83.5% within 2 hours]
* Determine QPTR and reduce thermal power> 3% from RTP for each 1% of QPTR> 1.00 once per 12 hours.
* Perform SR 3.2.1.1 and SR 3.2.2.1 within 24 hours and every 7 days thereafter.
Examiners NOTE:      Examiner can have candidate describe the brief description of event information rather than to copy required actions from Technical Specifications into the log.
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 Examiners NOTE:    The candidate may have specified this at any point during the JPM.
* Performance Step: 5  Identify highest priority action.
Standard:
* Restore rod to within alignment limits within 1 hour (ITS 3.1.4 Condition B, Required Action B.l).
OR
* Verify SDM is within the limits provided in the COLR within 1 hour (ITS 3.1.4 Condition B, Required Action B.2.I.I).
OR
* Initiate boration to restore SDM to within limit within I hour (ITS 3.1.4 Condition B, Required Action B.2.1.2).
AND
* Reduce thermal power to < 70% RTP within 2 hours (ITS 3.1.4 Condition B, Required Action B.2.2).
AND
* Verify SDM is within the limits provided in the COLR Once per 12 hours (ITS 3.1.4 Condition B, Required Action B.2.3)
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.
Examiners NOTE:
Comment:
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:
Number of 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.
* The RO has completed QPTR calculation. The highest quadrant power tilt value is 1.055.
* AFD is within limits.
* AUTOLOG is NOT available.
INITIATING CUE:        You are the CR5:
* Evaluate the given conditions for Technical Specification Action Statement(s) applicability.
* Make any necessary log entries.
* Identify the highest priority action.
2011 NRC JPM Admin SRO A2                        NUREG 1021, Revision 9, Supplement I
 
Appendix C                                    Job Performance Measure                          Form ESC-1 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.
* The FIN Team has requested a clearance to change the SFP Filter.
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 and 5519.
SFP Filter area survey map.
General
 
==References:==
RWPs 5498, 5499 and 5519.
SFP Filter area survey map.
Handouts:                    RWPs 5498, 5499 and 5519.
SFP Filter area survey map.
2011 NRC JPM RO-SRO Admin A3                                    NUREG 1021, Revision 9, Supplement I
 
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 TJME:_______
* Performance Step: I        Determine the dose limits from the SEP 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.
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 #5519 states that continuous RC coverage is required.
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-i pre-job briefing is required.
Comment:
END OF TASK Termination Cue:    When the candidate has determined the appropriate RWP and 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-C-1 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.
* The FIN Team has requested a clearance to change the SFP Filter.
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 1iDIiEI3IW 31{1( P1RJ1IF hhuhh1 11111 11111 1111111111 11111 1111111111 11111 11111 11111 11111 1111111111 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 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 I4.IIj%.FIOI VVOI.1( PEI{I1II 111111 11111 11111 11111 11111 11111 1111111111 11111 liii! 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 liii!liii ALARA 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 THAN OR EQUAL TO 10    1000 MREM/HR.
Nbr                      Special Instructions 5                      WORK DESCRIPTION ********************
S    OPERATIONS ACTIVITIES 5    NO SPENT FUEL POOL WORK ON THIS RWP.
S 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 LHRA S.
T 10 20    ********LOCKED HIGH RADIATION AREA ENTRIES*****
20 20    l.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 IJLBE1fION t    7O1{K I1I.rviIrr 111111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 IIIN 11111 11111 11111 11111 11111 1111111111 11111 liii ALARA Task port 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    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 SO        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
 
PASSPORT    - TOTAL EXPOSURE SYSTEM Ii.DIL4.rIorT 1 s o  Ic 11111111111111111111111111111111111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 III!
ALARA Task port ID    : T1PH900        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 I IhI 111111111111111111111111111111hIll 11111 11111 liii!11111 liii!11111 11111 11111 11111 11111 11111liii!11111 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              --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    CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL                                            (EXCEPT
 
PASSPORT    - TOTAL EXPOSURE SYSTEM
                  /OR1C p1J1 I liii hIll 11111111111111111111111111111111111hIll 11111 11111 IlI lihI 11111 11111 11111 11111 11111 11111 11111 III ALARA Task port  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.
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.
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. PAN/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 VVO1I( PEIIV1II 11111111111ll 11111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 liii 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 SO        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    1.PERMIS5ION 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 4
1 I
  \ rIcN
    .nT VJR.I( PER11IT 1111111111111111111111111111111111111111111111111111111111111 11111 111111111111111111 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 SUMP WITH REACTOR CRITICAL.
70
- End of Report    -
 
PASSPORT    - TOTAL EXPOSURE SYSTEM 1z\JI.6rIo1N /JR1( Piiiiir 111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 liii 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: MANNIP01                                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            j--Distance--J            I                    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 Hold Points and Special Instructions 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 4/O1J( Piiiiii 11111111111111111111111111111111111111111111111111111111 1111111111 IIII11111 11111 11111 IlII 11111 11111 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 S    **************  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 ACCtJNULATED 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 111111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 liii!11111 11111 liii!11111 hIll 11111 11111 11111 liii ALARA Task port  ID    : T1PH900          RWP Number:          00005519                      01 Page        :        3            Facility  :      RNP 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 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      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.
SO    5.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50        INSTRUCTED.
50 50    ************5OER 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 V7ORI( PE1]v1IT I 1111111111 11111 11111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 111111111
;                                                                                                                    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    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.PREJOB 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 An
              -                                                        Survey # 121410-          DatelTime: 12/1412010 07:A ISOPI                ia LOiAI LHRA/HPA controlled at locked door 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                          innnnn flPM/lnfl nm2 RI,  A/
                                                                                                          .i1)  <fl &deg;%flAfl Prtit-iiItc.l Frisker Bkg. = 60 cpm                                          9) 60000 DPM/1 00 cm2 /y      AIS 1) <30 %DAC Iodine Tenn. #2 MDA 79 dpm                                            7) 34000 DPM/100 cm2 ly
: 8) 33000 DPM/100 cm2 /y      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
: 12) 13000 DPMI100 cm2 ly RWP: 5910                    2) 10000 DPM/100 cm2 ly I I1r Spar R eactor Power =  100%        5) 5000 DPM/100 cm2 ly
- 2OJOenerI Area Lrl Drip S  9
: 6) 3000 DPM/100 cm2 /y Ci)sr.ear        san,pte ii        jipeIF -lot  Particles Detected      13) 2000 DPM/100 cm2 ly
: 14) 1200 DPM/100 cm2 ly
: 15) I100DPM/lOOcm2 ly Unless otherwise noted, dose rates in mremlhr.
Surveyor: Wes Brand Survey printed on: 1211512010 at: 07:47
 
Robinson Nuclear Plant Survey 12141 0 Data Point Details Page 1 of I        -
Additional Information:                                                            Counted by:    Wes Brand 12/14/2010 09:00 WRITask #: N/A Dose Rate (DR) Object Prefixes I Suffixes:
Work Area Code 4_3600                                                        *
                                                                                            = ContaclHS = Hot Spot ComponentITag Namel_N/A                                                              + = 30 cm No prefixGeneral Area Dose RE Tag Suffix Name:[_N/A                                                                      Suffixes: nNeutron, bBeta Short Name:J N/A                                                        Unless otherwise noted, dose rates in mremlhr.
Postings Legend:
RCA=Radiologically Controlled Area                                    CMContamination Area RMRadiation Area                                                      HPA=Hot Particle Area HRA=High Radiation Area                                                RMARadioactive Material Area LHRA=Locked High Radiation Area                                        CRCFE=Contact Radiation Control For Entry VHRA=Very High Radiation Area                                          CRCPE=Contact Radiation Control Prior To Entry ARAAirborne Radioactivity Area Instruments Used:
Efficienc No. I        Model                  Serial    I        Probe                Serial      Cal Date      Type      /y        p        a 1    61128                776386                NA                    NA          03/29/2011 00:0C  DIR  N/A      N/A      N/A 2    LM-177              776080                44-9                  NA          10/12/2011 00:0C  C/R  N/A      0.100    N/A 3    RO-20                778069                NA                    NA          08/13/2011 00:0(  DIR  N/A      N/A      N/A 4    TennO2              1217320              !Tenn                  INA          06/30/2011 00:OCj CIR  IN/A      0.242    0.221 No.        Type    Inst. Value                    Units                    Position                              Notes Smear    N/A          /y 20001 3          DPM/100 cm2        Floor N/A          o<MDI      DPM/100 cm2 2        Smear    N/A        131y 10001  DPM/100 cm2        vaIl 3        Smear    N/A      /i 100001 3
1              DPM/100 cm2        Filter Housing N/A              <MDI    DPM/100 cm2 4        Smear    N/A        ply 15001    DPM/100 cm2        /ent valve 5        Smear    N/A          131y 5001  DPM/100 cm2        rransmitter 6        Smear    N/A          ?y 3001 3
1          DPM/100 cm2        Vail 7        Smear    N/A        ply 34001    DPM/100 cm2        Floor N/A          ci<MDI    DPM/100 cm2 8        Smear    N/A        /i 33001 3
1            DPM/100 cm2        Floor N/A          a<MDI      DPM/100 cm2 9        Smear    N/A        j3/y 60001  DPM/100 cm2        Floor N/A          cx<MDI    DPM/100 cm2 10        Smear    N/A        ly 19001 3
I            DPM/100 cm2        Floor 11        Smear    N/A        30001 13/i        DPM/100 cm2        Flow Transmitter N/A            i<MDI    DPM/100 cm2 12        Smear    N/A        13/y 13001  DPM/100 cm2        rransmitter 13        Smear    N/A          131y 2001  DPM/100 cm2        Floor 14        Smear    N/A          ply 1201  DPM/100 cm2        Floor 15        Smear    N/A          13ly 1101  DPM/100 cm2        Floor Wipe                ly 20,001 3
l            CCPM              :loor 2          Wipe                ly 10,001 3
l            CCPM              900r 3          Wipe              /i 100,001 3
1              CCPM              :loor 4          Wipe                    13/y 121 CCPM              :loor AirSample                        <31 %DAC Particulate  3eneral Area Air Sample
                                          <31 %DAC Iodine DR                    N/A            *1500 iRem/hr              :ilter Housing N/A            +1000    iRem/hr DR                    N/A                200  Rem/hr DR            I      N/A              +600    iRem/hr DR            1      N/A              +100    Rem/hr DR            1      N/A                +50    nRem/hr DR            1      N/A                +25  TiRem/hr DR            I      N/A              +200    nRem/hr DR            I      N/A              +400    nRem/hr DR                    N/A              +200    iRem/hr Survey printed on: 1211 5/2010 at: 07:47
 
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 SROA4 K/A
 
==Reference:==
G2.4.41 (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:
* Reactor was shutdown on 1/7/2011 at 2300 hours.
* 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.
* SEP 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-0i, 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-01, SEP Diagram Handouts:          EPCLA-Oi, EPCLA-04, EAL Matrixes, EPNOT-Oi, SFP 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 I
 
Appendix C                                    Page 3 of 13                      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 EAL5.
Examiners NOTE:            Provide copies of the EAL Matrix to the candidate.
Comment:
* 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.I, 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:
2011 NRC JPM Admin SRO A4                                NUREG 1021, Revision 9, Supplement 1
 
Appendix C                            Page 4 of 13                        Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3  If Reactor Coolant temperature is < 200 degrees F, Then evaluate COLD conditions EAL Matrix. (Step 8.3.3)
Standard:            Candidate reviews EAL COLD Conditions Matrix and does NOT identify any EALs that have been exceeded on this matrix.
Examiners NOTE:
Comment:
Performance Step: 4  Announce to Control Room or TSC personnel that you are assuming the position of SEC. (Step 8.3.4)
Standard:            Candidate makes announcement that he has assumed the duties of the Site Emergency Coordinator (SEC).
Examiners NOTE:
Examiners CUE:      Acknowledge the announcement of the SEC if necessary.
Comment:
Performance Step: 5  If an ALERT has been declared, Then proceed to Attachment 10.6 for an ALERT. (Step 8.3.6)
Standard:            Candidate proceeds to Attachment 10.6 for the declaration of an ALERT.
Examiners NOTE:
Comment:
2011 NRC JPM Admin SRO A4                      NUREG 1021, Revision 9, Supplement 1
 
Appendix C                                  Page 5 of 13                          Form ES-C-i PERFORMANCE INFORMATION
* Performance Step: 6        Declares the highest EAL classification identified within 15 minutes.
Standard:                  Candidate declares ALERT based on RA 2.1 within 15 minutes of Start Time.
Examiners NOTE:
Examiners CUE:            Acknowledge classification from Shift Manager.
Comment:
Time Critical Stop Time for EAL Classification:                      (15 Minutes)
Time Critical Start Time for EAL Notification:
Performance Step: 7        Direct the Emergency Communicator to prepare for communication activities in accordance with EPNOT-01, 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:
2011 NRC JPM Admin SRO A4                            NUREG 1021, Revision 9, Supplement 1
 
Appendix C                            Page 6 of 13                        Form ES-C-i PERFORMANCE INFORMATION Performance Step: 8  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:
* Performance Step: 9  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: 10 Enter Line 2 information.
Standard:            Marks INITIAL.
Examiners NOTE:
Comment:
2011 NRC JPM Admin SRO A4                      NUREG 1021, Revision 9, Supplement 1
 
Appendix C                            Page 7 of 13                        Form ES-C-i PERFORMANCE INFORMATION
* Performance Step: 11 Enter Line 3 information.
Standard:            Enters H.B. Robinson as the Site and enters CONFIRMATION PHONE NUMBER.
Examiners NOTE:
Examiners CUE:      When candidate requests the ERO phone list, tell him the Confirmation Phone Number is 843-383-3685.
Comment:
* Performance Step: 12 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-2, CV Area R-5, Spent Fuel Pit Area R-1 hR-I 2, Process Monitor CV Air and Plant Vent (when sampling CV)
R-14, Plant Vent R-21, Fuel Handling Building Upper Level Examiners NOTE:
Comment:
2011 NRC JPM Admin SRO A4                        NUREG 1021, Revision 9, Supplement 1
 
Appendix C                            Page 8 of 13                      Form ES-C-i PERFORMANCE INFORMATION
* Performance Step: 13 Enter Line 5, Protective Action Recommendation information.
Standard:            Marks NONE.
Examiners NOTE:
Comment:
* Performance Step: 14 Enter Line 6, EMERGENCY RELEASE, information.
Standard:            Marks Is Occurring.
Examiners NOTE:
Comment:
Performance Step: 15 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:
2011 NRC JPM Admin SRO A4                        NUREG 1021, Revision 9, Supplement 1
 
Appendix C                              Page 9 of 13                        Form ES-C-i PERFORMANCE INFORMATION Performance Step: 16 Enter Line 8, EVENT PROGNOSIS, information.
Standard:            Marks Degrading.
Examiners NOTE:
Comment:
* Performance Step: 17 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 0.
Examiners NOTE:
Comment:
* Performance Step: 18 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:
2011 NRC JPM Admin SRO A4                        NUREG 1021, Revision 9, Supplement 1
 
Appendix C                            Page 10 of 13                    Form ES-C-I PERFORMANCE INFORMATION
* Performance Step: 19 Enter Line 11 information, AFFECTED UNITS.
Standard:            Marks Unit 2.
Examiners NOTE:
Comment:
Performance Step: 20 Enter Line 12 information UNIT STATUS.
Standard:            Enters Shutdown Time: 2300 hours on 11712011 Examiners NOTE:
Examiners CUE:      Provide unit shutdown Time and Date as 2300 hours on 11712011.
Comment:
2011 NRC JPM Admin SRO A4                      NUREG 1021, Revision 9, Supplement 1
 
Appendix C                                Page 1 1 of 13                      Form ES-C-i PERFORMANCE INFORMATION Performance Step: 21      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: 22      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)
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 13                    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
 
Appendix C                              Page 13 of 13                          Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
* Reactor was shutdown on 1/7/2011 at 2300 hours.
* 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 1
 
ATT%1Ei1O.7                              MAf5&e4 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM 1.XDRILL                ACTUAL EVENT                                                                                            MESSAGE #
: 2. INITIAL          FOLLOW-UP                NOTIFICATION: TIME______ DATE                        I      I        AUTHENTICATION#
: 3. SITE:        A                                                                                      Confirmation Phone #                    c.tS
: 4. EMERGENCY                    F1                EVENT        ALERT              SITE AREA EMERGENCY                      GENAL EMERGENCY CLASSIFICATION: A                                                                                                              1
                                                                                                  *        --1 fSqL
                                        ...
/BED              EAL#/<I/
q EAL,          M 1
                                                                  ,RIPONJ 5
L 1
fi                              i4(/ci                    (/e L-              1-tt(h;41                --.
/?t    d-j..iq      e.V    /LJt;
: 5. PROTEQiE ACTION REJOMMENDATIONS:
d NNE I      &
2 L/              nt.:
EVACUATE j  SHELTER CoNsIDE THE USE OF      KI  (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.
j  OTHER
: 6. EMERGENCY RELEASE:                              None          Is Occurring                        Has Occurred Not              Within normal                      Above normal operating      Under
: 7. RELEASE SIGNIFICANCE:
applicable        operating limits                  limits                          evaluation
: 8. EVENT PROGNOSIS:                                Improving      J Stable                        I    Degrading
: 9. METEOROLOGICAL DATA:                            Wind Direction* from            degrees          Wind Speed*      -      mph
(*May not be available for Initial Notifications)
Precipitation*  0                                Stability Class*
: 10. DECLARATION                  TERMINATION                    Time    AItii)                Date 11.AFFECTEDUNIT(S):              Lii            I1    EI
: 12. UNIT STATUS:                                              Ui          Power    Shutdown at Time                          Date _I          /
(Unaffected Unit(s) Status Not Required for Initial Notifications)                                  U2  O      Power    Shutdown at Time            23 OC        Date _/.j 7 IlL
: 13. RC4J(
7                      4& /efl /k.Y              eL 1
Power    Shgown a Time 4                          Dates    L.    /
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
: 14. RELEASE CHARACTERIZATION:                        TYPE:    Elevated j Mixed            Ground        UNITS:    Ci      Cl/sec    ItCi/sec MAGNITUDE:          Noble Gases:___________ lodines:____________ Particulates:___________ Other:
FORM: Airborne              Start Time                Date _/            /Stop Time                      Date _I          /
Liquid          Start Time                Date _I            I...Stop Time                    Date _I          I..._
: 15. PROJECTION PARAMETERS:                    Projection period:                              Estimated Release Duration Projection performed:        Time                Date _I          I...._......
: 16. PROJECTED DOSE:                            DISTANCE                        TEDE (mRem)                          Adult Thyroid CDE (mRem)
Site boundary 2 Miles 5 Miles 10 Miles
: 17. APPROVED BY:            tJd(cIAf4L                          Title_________                          Time  AAIfl)    L 4
DatjtL9 NOTIFIED BY:_____                                    RECEIVED BY:                                      Time              Date_I____
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ATTACHMENT 10.7 Page 2 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM GOVERNMENT AGENCIES NOTIFIED NOTIFICATION: TIME    DATE      Get Time/Date I AUTHENTICATION#        Get Authentication Codel 10.1.1.1    Name:                            Date/Time:                Agency: Chesterfield County EOC 10.1.1.2    Name:                            Date/Time:                Agency: Chesterfield County WP 10.1.1.3    Name:                            Date/Time:                Agency: Darlington County EOC 10.1.1.4    Name:                            Date/Time:                Agency: Darlington County WP 10.1.1.5    Name:                            Date/Time:                Agency: Lee County EOC 10.1.1.6    Name:                            Date/Time:                Agency: Lee County WP 10.1.1.7    Name:                            Date/Time:                Agency: NRC (via ETS or Bell Phone) 10.1.1.8    Name:                            Date/Time:                Agency: NRC Resident Inspector 1O.i.1.9    Name:                            Date/Time:                Agency: State of SC BWP 10.1.1.10  Name:                          Date/Time:                Agency: State of SC WP Ii1 ISend Form!
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ATTACHMENT 10.7 Page 3 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION CAUTION Initial notifications are to be made within 15 minutes of the declaration of an emergency.
Follow up notifications shall be made within 60 minutes from the completion of the previous notification. The earliest time indicated for any agency will be the start time for the follow up notification for all agencies.
All efforts should be expended to obtain information required for the Electronic Emergency Notification Form. IF an upgrade in classification occurs when the follow-up message is due, THEN upgraded ENF forthcoming should be annotated in Remarks. This information is to be promptly transmitted to the State and County agencies, as soon as it is available.
Messages should include an up-to-date description of what is happening at the plant within the constraints of timely notifications. To ensure messages contain adequate and accurate information about current plant conditions, messages should be developed as promptly as possible. ENF reviews will be conducted by EOF Facility personnel, if available. It may be necessary to determine a cut off time for new message information so that these reviews can be made. The ERM will direct EOF personnel through the ENF line by line and the POA, TAM and RCM will verify the accuracy of the ENF using the following guidance:
Lines 1, 2, 3, 4 POA verifies accuracy
 
Lines 5, 6, 7 RCM verifies accuracy
 
Line 8 TAM verifies accuracy
 
Line 9 RCM verifies accuracy
 
Lines 10, 11, 12 POA verifies accuracy
 
Line 13 POA verifies accuracy
 
Lines 14, 15, 16 RCM verifies accuracy (reference the Rascal Source Term Summary sheet)
Line 17 ERM approves Lines 1 through 13 AND Line 17 MUST BE COMPLETED on an INITIAL Electronic Emergency Notification Form. Information for Line 9 may not be available for the initial notification. If met data is not available, then state this in the Remarks (Line 13) and provide the data on a follow-up notification, as soon as the data is available. For TERMINATION messages, only Lines 1 through 4, 10, and 17 are required.
Information included on the initial form AND Lines 14 through 16 MUST BE COMPLETED on a FOLLOW-UP Electronic Emergency Notification Form.
An electronic emergency notification form is available and can be accessed through the NGG Standard Desktop.
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ATTACHMENT 10.7 Page 4 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Item                                Instructions Line 1:
NOTE: When DRILL is selected, the Electronic Emergency Notification Form will display, This is a drill.
INDICATE whether the message is a DRILL OR an ACTUAL EVENT.
ENTERIVERIFY the MESSAGE NUMBER.
The message number is consecutive from the initial notification message to the termination notification message. It does not begin again at I for any reason during the course of an emergency event.
Line 2:
NOTE:    Messages that contain a change in emergency classification, a termination, OR a change in Protective Action Recommendations (PAR) are INITIAL notifications. All other messages are considered FOLLOW-UP notifications.
INDICATE whether the message is an INITIAL notification OR a FOLLOW-UP notification.
NOTIFICATION TIME!DATE: The Notification Time/Date is completed when first voice contact is made during offsite agency notification. It will be entered after the completion of Line 17. Additional information is provided at the next reference to Line 2.
Line 3:
NOTE:    Confirmation phone numbers are provided in a drop-down menu box.
ENTER H. B. Robinson.
Confirmation Phone #: ENTER the number that any offsite agency can call to verify the message is authentic. Ensure the number given is a location where the phone will be answered. DHEC is required to verify the message by their procedure within 15 minutes.
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ATTACHMENT 10.7 Page 5 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION NOTE:  A change in PARs must be an initial notification. However, the declaration time does not change and the time for the change in PARs needs to be recorded in the Remarks section.
Line 4:    INDICATE the EMERGENCY CLASSIFICATION that is being declared.
IF this is an initial message, THEN INDICATE the current emergency classification.
IF this is a follow-up message OR a termination message, THEN INDICATE the same emergency classification as the previous notification.
EAL DESCRIPTION should contain a short narrative of the emergency classification. The narrative should be in laymans terms and not include any slang or acronyms, i.e., ATWS, RCP, WGDT, that are commonly used at the plant. This description must be easily understood by individuals without nuclear industry experience.
Line 5:    INDICATE the appropriate PROTECTIVE ACTION RECOMMENDATIONS.
IF the emergency classification is a GENERAL EMERGENCY, THEN ENTER the sectors for which the recommendations (evacuate or shelter) are applicable.
IF the projected dose to the thyroid is 5 Rem or greater at the site boundary, THEN the consideration of Potassium Iodide (KI) must be included as a PAR.
Line 6:    INDICATE whether OR not an EMERGENCY RELEASE is occurring OR has occurred. Emergency Releases affect or have the potential to affect offsite environments. (The SEC makes the determination on Emergency Release, reference EPCLA-01 for additional guidance). A gaseous Emergency Release is any of the following:
: 1.      An approved monitored release was occurring and the reading on the radiation monitor designated to monitor this release increases due to the event.
: 2.      Any release due to the event that was not previously approved.
: 3.      Anytime a primary to secondary leak causes an emergency declaration, a release should be considered is occurring.
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ATTACHMENT 10]
Page 6 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION A liquid Emergency Release is any of the following:
: 1. An approved monitored release was in progress and the reading on the radiation monitor designated to monitor this release increases but does not isolate on an alarm signal.
: 2. The rupture of a system which releases radioactive liquids into an area that affects or has the potential to affect an offsite environment.
Line 7: INDICATE the RELEASE SIGNIFICANCE.
IF NO Emergency Release has occurred, THEN SELECT not applicable.
IF an emergency release is in progress or has occurred AND the release significance has NOT been determined, THEN SELECT Under Evaluation.
IF the release significance has been determined, THEN INDICATE whether or not the release is Within Normal Operating Limits OR Above Normal Operating Limits.
IF the projected dose at the site boundary is below 25 mRem TEDE AND 75 mRem Thyroid CDE, THEN MARK Line 7 as Within Normal Operating Limits.
Otherwise, MARK Line 7 as Above Normal Operating Limits.
Line 8: INDICATE whether the EVENT PROGNOSIS is Improving, Stable, or Degrading. The Site Emergency Coordinator OR the Plant Operations Advisor AND the Technical Analysis Manager should be consulted, if assistance is needed, in making this determination.
EXAMPLES IF there is a probable escalation of Emergency Classification, continued deterioration of plant conditions OR an increase in Protective Action Recommendations (PARs), THEN indicate the prognosis as Degrading.
IF there are no expected changes in Emergency Classifications, plant conditions OR Protective Action Recommendations (PARs), THEN the event prognosis should be considered Stable.
IF there is a probable downgrade in Emergency Classification, plant systems are being returned to service OR a reduction in Protective Action Recommendations (PARs), THEN the event prognosis should be considered Improving.
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ATTACHMENT 10.7 Page 7 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 9:
NOTE:    Meteorological and % power data is auto-populated from ERFIS in the electronic Emergency Notification Form, by selecting Import Plant/MET Data at Line 9 of the electronic ENF.
CAUTION The wind direction is recorded as the from direction, if it is obtained from a source other than ERFIS, it may need to be verified/changed.
NOTE:    For all releases not via the plant stack, ground wind direction should be used.
Elevated wind direction is taken from the lOOm height on the Met Tower. Ground wind direction is from the 32m height.
NOTE:  Ground wind direction should be used if a release is not in progress.
RECORD the METEOROLOGICAL DATA from ERFIS.
IF ERFIS is unavailable, THEN OBTAIN Meteorological Data from the National Weather Service Office (see ERO Telephone Book), as available. ENTER the Stability Class from procedure EPRAD-03 for dose projection.
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ATTACHMENT 10.7 Page 8 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 10:
CAUTION Chronological order of the times recorded on the form is critical. The time listed on Line 10 (DECLARATION TIME) should be the first time entered on the form. The times on the Electronic Emergency Notification Form should be completed as follows: first- Line 10 (DECLARATION TIME), second- Line 17 (APPROVAL TIME), and last- Line 2 (NOTIFICATION TIME). For example Line 10 at 12:00 and Line 17 at 12:10 and Line 2 at 12:14. The first voice contact (NOTIFICATION TIME) time should not be documented until an approved form is available.
NOTE:    A change in PARs must be an initial notification. However, the declaration time does not change and the time for the change in PARs needs to be recorded in the Remarks section.
INDICATE whether the notification is for an event DECLARATION or TERMINATION. ENTER the time AND date the emergency classification in Line 4 was declared. This time should not change unless the emergency classification has changed OR the event has been terminated.
Line 11:      INDICATE 2 as the AFFECTED UNIT. Unit 2 is the default value for the H.B.
Robinson site.
Line 12:
NOTE:    Meteorological and % power data is auto-populated from ERFIS in the electronic Emergency Notification Form, by selecting Import Plant/MET Data at Line 9 of the electronic ENF.
ENTER the UNIT STATUS.
IF the reactor is at power, THEN ENTER the current reactor power.
IF the reactor is shutdown, THEN ENTER the time AND date of the shutdown.
Line 13:      Additional information may be entered in the REMARKS.
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ATTACHMENT 10.7 Page 9 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 14:
NOTE:    Dose data is auto-populated in the electronic Emergency Notification Form, by selecting Import Dose Projection Data at Line 14 of the electronic ENF. Dose data is populated from saved dose projection files created in RASCAL.
NOTE:    Dose data will only be imported if Line 6 has a release occurring or has occurred and Line 7 is within or above the normal operating limits.
NOTE:    Lines 14 through 16 are not required on an initial ENF. However, if either within normal operating limits or above normal operating limits is selected for Line 7, then lines 14 through 16 are to be completed and included in the initial ENF.
NOTE:    Lines 14 through 16 are not required if line 6 has none selected. If Line 7 has under evaluation selected, then the development of dose projections is to become a priority and once completed, included on a follow-up ENF.
ENTER the EMERGENCY RELEASE DATA provided by Dose Projections on Lines 14 through 16. IF None has been selected for Emergency Release (Line 6), THEN Line 14 is not required to be completed.
NOTE:    RNP cannot have an Elevated release.
INDICATE the RELEASE TYPE: Mixed or Ground 1
For RELEASE MAGNITUDE, ENTER the Noble Gas and Iodine Activity in Curies (Ci).
For FORM, SELECT Airborne AND ENTER the Release Start Time/Date AND Stop Time/Date.
Line 15:    Projection period is not applicable for RNP and can be left blank. For PROJECTION PARAMETERS: ENTER the estimated release duration in hours AND ENTER the time AND date the projection was performed.
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ATTACHMENT 10.7 Page 10 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 16:
NOTE:      The minimum value for doses to be entered on the electronic emergency notification form is 0.1 mRem. Any dose values below 0.1 mRem should entered as <0.1 mRem.
NOTE:      When a release is in progress, the dose projection data will be auto-populated in the electronic emergency notification form from RASCAL.
For PROJECTED DOSE, RECORD the TEDE dose in mRem AND the THYROID CDE in mRem for each distance away from the site in the dose columns provided. ENSURE that the units are recorded in mRem.
Line 17:
CAUTION Chronological order of the times recorded on the form is critical. The time listed on Line 17 (APPROVAL TIME) should be the second time entered on the form. The times on the Electronic Emergency Notification Form should be completed as follows: first- Line 10 (DECLARATION TIME), second- Line 17 (APPROVAL TIME), and last- Line 2 (NOTIFICATION TIME). For example Line 10 at 12:00 and Line 17 at 12:10 and Line 2 at 12:14. The first voice contact (NOTIFICATION TIME) time should not be documented until an approved form is available.
COMPLETE the APPROVED BY section. IF the message is to be transmitted from the Control Room, THEN it must be approved and signed by the SEC. IF the message is to be transmitted from the EOF, THEN it must be approved by the ERM prior to transmitting the notification to the State and County agencies.
Any changes made between this signature AND the release of the message must be initialed/approved by the SEC OR ERM.
NOTE:      Once the ENF is approved, changes cannot be made.
The individual who makes first voice contact with the offsite agencies is responsible for entering his/her name in the blank marked NOTIFIED BY upon completion of the message.
The RECEIVED BY blank will be completed by the offsite agencies.
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ATTACHMENT 10.7 Page 11 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 2:
CAUTION Chronological order of the times recorded on the form is critical. The time listed on Line 2 (NOTIFICATION TIME) should be the last time entered on the form. The times on the Electronic Emergency Notification Form should be completed as follows: first- Line 10 (DECLARATION TIME), second- Line 17 (APPROVAL TIME), and last- Line 2 (NOTIFICATION TIME). For example Line 10 at 12:00 and Line 17 at 12:10 and Line 2 at 12:14. The first voice contact (NOTIFICATION TIME) time should not be documented until an approved form is available.
NOTIFICATION TIMEIDATE: The Notification Time/Date is completed when first voice contact is made during offsite agency notification. First voice contact will be considered complete after site identification, type of message and emergency classification is provided to the offsite agency.
RECORD the time of first voice contact with any offsite agency as verified on the phone by roll call.
AUTHENTICATION #: ENTER the AUTHENTICATION number in the space provided on the Electronic Emergency Notification Form. This information will be entered after the form is initially developed and transmitted to offsite agencies. Authentication is not required but the State/County representatives should be asked, Would anyone like to authenticate this message? IF yes, THEN they will pick a number AND you respond with the corresponding word (see the authentication code list or select the authentication code button on the electronic emergency notification log).
GOVERNMENT AGENCIES NOTIFIED After review of the ENF, RECORD the name of the individual from each agency and the date/time the information was provided.
Upon completion, transmit the information electronically using the Send Form button. This will also automatically update the ENF with the earliest notification time.
EPNOT-01                                  Rev. 35                            Page 44 of 61}}

Revision as of 08:00, 31 October 2019

Initial Exam 2011-301 Draft Admin Jpm'S
ML15245A551
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 09/02/2015
From:
Division of Reactor Safety II
To:
Progress Energy Carolinas
References
Download: ML15245A551 (83)
v • d • e


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.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 JPMAdmin 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-012, Manual Determination of Shutdown Margin Boron Concentration Station Curve Book, Section 1 Cycle Data

Calculator Straight Edge General

References:

FMP-001 FMP-012 Station Curve Book, Section 1 Cycle Data Handouts: FMP-001 FMP-0i2 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-0i2.

Time Critical Task: NO Validation Time: 60 minutes 2011 NRC JPM Admin 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 12 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.

q Performance Step: I Complete Section I of Attachment 7.1 Standard: Candidate completes the information needed for Section I:

Date / 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 12 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:

J 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 XI, 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 12 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)

[15697] +/- 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 1

Appendix C Page 7 of 12 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 pcm.

Examiners NOTE: Candidate should use Curve or Table I .3C based on cycle exposure time (EOL). Value read from curve is 1870 pcm and extrapolated from table is 1855.5 pcm.

Comment:

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.

.1 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]

pcm.

Examiners NOTE:

Comment:

2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 12 Form ES-C-i PERFORMANCE INFORMATION J Performance Step: 7 Complete Section VU 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] +/- 9 pcm.

Examiners NOTE:

Comment:

J 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.

  1. 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 1

Appendix C Page 9 of 12 Form ES-C-i PERFORMANCE INFORMATION q 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] +/- 9 pcm Inserted/Misaligned Worth (Step VI) = [850] pcm Power Defect Worth (Step V) = [1855.5] +/- 25 pcm Inop/Untrip Rod Worth (Step VIII) [0]

Available Shutdown Margin = [3162.5] +/- 16 pcm Examiners NOTE:

Comment:

..I 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-00i), the required SDM is X 1000 pcm/%= pcm.

Standard: Candidate determines from FMP-OOi, Figure 5.0 that required SDM is [t60]% (+/- 0.05%) and calculates [1600] pcm. This used an RCS boron concentration of 138 ppm and read Figure 5.0 for Mode I operation.

Examiners NOTE:

Comment:

2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement I

Appendix C Page 10 of 12 Form ES-C-i PERFORMANCE INFORMATION J 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 3162.5 pcm available shutdown margin to the 1600 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 11 of 12 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:

Numberof Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 12 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-001, 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 JPMAdmin RO-SROAI-l 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:

G2.1.25 (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 A1-2 NUREG 1021, Revision 9, Supplement I

Appendix C Job Performance Measure Form ES-C-i Worksheet Time Critical Task: NO Validation Time: 12 minutes 2011 NRC JPMAdmin ROAI-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:

1 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 I Performance Step: 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. (Step 8.4.1.4)

Standard: Interpolates from Steam Tables and logs:

43.7/100 x (655.89649.45) + 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:

q 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 ROA1-2 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:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2011 NRC JPM Admin RO Al -2 NUREG 1021, Revision 9, Supplement 1

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 JPMAdmin ROA1-2 NUREG 1021, Revision 9, Supplement 1

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CONTINUOUS USE Section 8.4 Page 1 of 1 8.4 INFREQUENT OPERATIONS IT 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.
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. °F Initials Name(Print) Date Performed By:

Approved By:

Unit 2 Superintendent Shift Operations Date OP-307 Rev. 13 Page 15 of 18

4,sJvp CONTINUOUS USE Section 8.4 Page 1 of 1 8.4 INFREQUENT OPERATIONS DJiT 8.4.1 Manual Calculation of Margin to Saturation

1. This revision has been verified to be the latest revision available.

.

/W Name ( rint) Initial Signature (

7d Date /

2. Determine primary pressure using the lowest vad pressure indication. psig
3. Convert pressure to absolute by adding 14.7 psto value _-y determined in Step 8.4.1.2. Z2-47psia (_AL
4. Enter, from the Saturated Steam Tables, the saturation temperature corresponding to the pressure shown in Step 8.4.1.3 to determine the correspondng temperature. 33ZJOF
5. Determine primary temperature using the highest valid core exit thermocouple temperature 0 n.

9 indicati

6. Subtract the temperature of Step 8.4.1.5 from the temperature of Step 8.4.1.4 to determine tl)e marg)n to saturation in °F. OF <f/ L..

Is me(Print) Date Performed By: ct4y Approved By:

Unit 2 - Superintendent Shift Operations Date OP-307 Rev. 13 Page 15 of 18

Appendix C Job Performance Measure Form ES-C-i Worksheet 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&ID 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: The CRS has directed you to 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 2011 NRC JPM Admin RO A2 NUREG 1021, Revision 9, Supplement I

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:

2011 NRC JPM Admin RO A2 NUREG 1021, Revision 9, Supplement 1

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-29i, Charging Pump A to Seal Injection CLOSED

-

  • CVC-277C, Charging Pump A Recirc Root CLOSED OR
  • CVC-275C, Charging Pump A Recirc CLOSED -

Examiners NOTE: Vent and drains are NOT required to be included.

Valve CVC-277C OR CVC-275C will isolate the recirc line; only I valve is required to be identified.

Comment:

  • Performance Step: 3 Determine the power supply to Charging Pump A.

Standard: Candidate determines that Charging Pump A power supply is 480V Bus DS.

Examiners NOTE: Charging Pump A power supply is located in EDP-002, Section 7.0, 480V Bus DS.

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:

2011 NRC JPM Admin RO A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE INFORMATION END OF TASK Terminating Cue: Charging Pump A valve boundaries and power supply have been identified as directed.

STOP TIME:

2011 NRC JPM Admin RO A2 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 RO A2 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 A2 NUREG 1021, Revision 9, Supplement 1

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: The CRS has directed you to identify the pump boundary valves and motor breaker to expedite the pump isolation and termination of the leakage.

2011 NRC JPM Admin RO A2 NUREG 1021, Revision 9, Supplement 1

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.
  • The FIN Team has requested a clearance to change the SEP Filter.

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 and 5519.

SFP Filter area survey map.

General

References:

RWPs 5498, 5499 and 5519.

SFP Filter area survey map.

Handouts: RWPs 5498, 5499 and 5519.

SEP 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.

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 #5519 states that continuous RC coverage is required.

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-i pre-job briefing is required.

Comment:

END OF TASK Termination Cue: When the candidate has determined the appropriate RWP and restrictions from the survey map, the evaluation of this JPM is complete.

STOP TIME:

201 i 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-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.
  • The FIN Team has requested a clearance to change the SFP Filter.

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 AJI1C I 11111 11111 11111 11111 11111 11111 11111 liii!11111 1111111111 11111 11111 11111 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 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 Hold Point Description Nbr 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 RADIATION WORK PERMIT 1111111111111111111111111111111111111111111111111111111111111 1111111111111111111111111111111111111111111111111 ALARA 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 THAN OR 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 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 PAMTRX 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 l.PREJOB 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 iA7OE..1C PERJVIIr.[

11111111111 11111 11111hIll 11111 11111 11111 11111 11111 1111111111111111111111111111111111111111111111111111111111 ALARA Task 4ort 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 1 INCH) ***

40 **** CONTAMINATED SYSTEM BREACH (LINES >

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 SO 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

PASSPORT - TOTAL EXPOSURE SYSTEM VO1{1( PE1.i1II I 11111 1111111111 11111 11111 11111 11111 11111 11111 1111111111 11111 1111111111 11111 11111 11111 11111 1(111 11111 11111 liii ALAR Task port ID  : TIPH900 RWP Number: 00005498 01 Page  : 4 Facility  : RNP 60 DOSE RATE ALARM 10000 MREM/HR 60 9.NO ENTRY INTO CV StJMP WITH REACTOR CRITICAL.

60 70 ****REQUIREMENT5 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 I}II..1IOf \O11( PEIJlIf 1111111111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 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--Distance--I 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 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 O1{J( PII1IIrr I 11111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111111111111111111111111111111111111111111111111111111111 ALARA Task port 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.

5 S

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.PREJOB 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 i).EI r

1 If V7JI{1( PER.]NIIT 111111 11111 11111 11111liii! 11111 11111 11111 11111 11111 11111 11111 liii!11111 11111 11111 I 11111 11111 11111 11111 liii 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 ****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 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 1iIIi.IIr O1{I( PIIJv1T1 111111 IIII 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 111111111 ALARA Task iport 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 SUMP WITH REACTOR CRITICAL.

70 End of Report -

PASSPORT - TOTAL EXPOSURE SYSTEM 1J4..I[I.rf[Jpb \VOII( PER.]VIIT 11111111111111111111111111 11111 1111111111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 III!

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: MAIJNIP0l 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 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 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 RADIATION WORK PERMIT 11111111111 IIII 1111111111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 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 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 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

.IIA1ION 1

1. R1( PER.I1IrF 111111111111111111111111111111111111111111111111111 liii!11111 liii! 11111 11111 [1111111111111111111111111111 III ALARA Task port ID  : TIPH900 RWP Number: 00005519 01 Page  : 3 Facility  : RNP 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 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 ****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 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 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 ORi( PiiiiIr 1

\

1111111111111111111111111111111111111111111111111111111111111 11111 11111 11111 liii!11111 11111 1111111111 11111 liii ALARA Task ort ID  : T1PH900 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 PEE-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 -

Robinson Nuclear Plant SFPF.WMF Spent Fuel Pit Filter Ar

- Survey # 121410- Date/Time: 12/1412010 07:

LHRA/HPA controlled at locked door Comments: ****Training Use OnIy****

Pre-job Survey to Support SEP Filter Replacement.

Air Sample Taken with H809V #776982.

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 DPM/100 cm2 l/i 3 A/S 1) <30 %DAC Iodine Tenn. #2 MDA 79 dpm 7) 34000 DPM/100 cm2 ly

8) 33000 DPM/100 cm2 ly Wipe 3) 100,000 CCPM
11) 30000 DPM/100 cm2 lIly Wipe 1) 20,000 CCPM
1) 20000 DPM/100 cm2 lIly Wipe 2) 10,000 CCPM
10) 19000 DPM/100 cm2 ply Wipe 4) 120 CCPM Symbol Legend (for example only) Type: Job Coverage 4) 15000 DPM/100 cm2 lIly
12) 13000 DPM/100 cm2 ply RWP: 5910 2) 10000 DPM/100 cm2 lIly I-iS O 1+ot fipsi 1 tLJ

-j--- Contact Reading cm Reading nC

.1 I Reactor Power = 100% 5) 5000 DPM/100 cm2 Iy

[2OEOencraI .cca liIP 6) 3000 DPM/100 cm2 ly i5 r Sample RIIA 1pe Hot Particles Detected 13) 2000 DPM/100 cm2 ly

14) 1200 DPM/100 cm2 ly
15) 1100 DPM/100 cm2 lIly Unless otherwise noted, dose rates in mremlhr.

Surveyor: Wes Brand Survey printed on: 1211512010 at: 07:47

Robinson Nuclear Plant Survey 121 41 0 Data Point Details Page 1 of I -

Additional Information: Counted by: I Wes Brand 12/14/2010 09:00 WR!Task #: j_N/A Dose Rate (DR) Object Prefixes I Suffixes:

Work Area Code:I_3600 *

= ContaclHS = Hot Spot ComponentlTag Name_N/A + = 30 cm No prefixGeneral Area Dose R Tag Suffix Name:I_N/A Suffixes: nNeutron, bBeta Short Name: N/A Unless otherwise noted, dose rates in mremlhr.

Postings Legend:

RCA=Radiologically Controlled Area CA=Contamination Area RMRadiation Area HPMH0t Particle Area HRAHigh Radiation Area RMA=Radioactive Material Area LHRMLocked High Radiation Area CRCFEContact Radiation Control For Entry VHRA=Very High Radiation Area CRCPEContact Radiation Control Prior To Entry ARA=Airborne Radioactivity Area Instruments Used:

Eftlcienc No. Model Serial Probe I Serial I Cal Date I Type I a I 6112B 776386 NA NA 03/29/2011 00:0C DIR N/A N/A IN/A 2 LM-177 776080 449 NA 10/12/2011 00:OC CIR N/A 0.100 rN/A 3 RO-20 778069 NA NA 08/13/2011 00:0( D/R N/A N/A N/A 1217320 Tenn NA 106/30/201100:OCI CIR N/A 0.242 0.221 No. Type IiL Value Units Position Notes Smear NIA /1i uvj 3 rO cm2 Floor N/A cL<MD) JPM/100 cm2 2 Smear N/A 3/y 10001 JPM/100 cm2 Nail 3 Smear N/A 13/i 100001 JPM/100 cm2 Filter Housing N/A a<MD) JPM/100 cm2 4 Smear N/A 13/i 15001 )PM/100 cm2 ent valve 5 Smear N/A /i 5001 3

1 JPM/100 cm2 ransmitter 6 Smear N/A y 3001 )PM/100 cm2 Vail 7 Smear N/A 13/i 34001 )PM/100 cm2 Floor N/A cL<MD JPM/100 cm2 8 Smear N/A 13/y 33001 JPM/100 cm2 Floor N/A JPM/100 cm2 9 Smear N/A 13/i 60001 JPM/100 cm2 Floor N/A a<MD JPM/100 cm2 10 Smear N/A 13/i 1900 DPM/100 cm2 loor 11 Smear N/A /i 3000 3

1 JPM/100 cm2 90w Transmitter N/A o<MD DPM/100 cm2 12 Smear N/A 13/i 1300 DPM/100 cm2 ransmitter 13 Smear N/A 13/i 200 DPM/100 cm2 900r 14 Smear N/A 13/i 120 DPM/100 cm2 900r 15 Smear N/A 13/i 110 DPM/100 cm2 900r Wipe 13/i 20,00 CCPM Floor 2 Wipe 13/i 10,00 CCPM Floor 3 Wipe 13/i 100,00 CCPM Floor 4 Wipe 13/i 12 CCPM Floor AirSample <3( %DAC Particulate Seneral Area Air Sample

<3( %DAC Iodine DR i N/A *1500 mRem/hr Filter Housing N/A +1000 mRem/hr DR i N/A 200 mRem/hr DR y N/A +600 mRem/hr DR N/A +100 mRem/hr DR i N/A +50 mRem/hr DR i N/A +25 mRem/hr DR i N/A +200 mRem/hr DR i N/A +400 mRem/hr DR i N/A +200 mRem/hr Survey printed on: 1211512010 at: 07:47

Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HB ROBINSON Task No.: 01001101601 Task Title: Perform Shutdown Margin JPM No.: 201 1 NRC JPM Admin Calculation lAW FMP-012 RO-SRO Al-i K/A

Reference:

G2.1.37 (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-001, 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-OOi, 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-0i2 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 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 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 12 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.

q 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 NOTES 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 12 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 Xl, Attachment 7.1

[NO] Further verification of SDM is warranted, complete Sections IV through XI, 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 12 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)

[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 JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 12 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 pcm.

Examiners NOTE: Candidate should use Curve or Table 1.3C based on cycle exposure time (EOL). Value read from curve is -1870 pcm and extrapolated from table is 1855.5 pcm.

Comment:

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.

J 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]

pcm.

Examiners NOTE:

Comment:

2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 12 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] +/- 9 pcm.

Examiners NOTE:

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.

  1. 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 [NIA]

Examiners NOTE:

Comment:

2011 NRC JPM Admin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 12 Form ES-C-i PERFORMANCE INFORMATION q 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] +/- 9 pcm Inserted/Misaligned Worth (Step VI) = [850] pcm Power Defect Worth (Step V) = [1855.5] +/- 25 pcm Inop/Untrip Rod Worth (Step VIII) = [0]

Available Shutdown Margin [3162.5] + 16 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 10 of 12 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 3162.5 pcm available shutdown margin to the 1600 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 corn plete.

STOP TIME:

2011 NRC JPMAdmin RO-SRO Al-i NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 12 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

Appendix C Page 12 of 12 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-001, 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.: 02119101401 Task Title: Determine the Actions Necessary JPM No.: 2011 NRC JPM Admin to enter Mode 4 From Mode 5 SRO AI-2 K/A

Reference:

G2.1.23 (4.3/4.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE 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 -1 2, 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 AI-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-001-12, 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 SRO Al -2 NUREG 1021, Revision 9, Supplement I

Appendix C Page 3 of 7 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:

  • Performance Step: 2 Compare Attachment 10.2 to Initial Conditions: RCS LEAKAGE DETECTION INSTRUMENTATION. (ITS LCO 3.4.15)

Standard: Determines that there is NOT 1 Containment atmosphere radioactivity monitor operable.

Examiners NOTE: R-11 and 12 are inoperable to replace the monitor flow meter.

Comment:

  • Performance Step: 3 Compare Attachment 10.2 to Initial Conditions: RWST (ITS LCO 3.5.4)

Standard: Determines that RWST boron is out of specs high at 2450 ppm boron.

Examiners NOTE: Maximum RWST boron concentration is 2400 ppm.

Comment:

2011 NRC JPM Admin SRO Al -2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 7 Form ES-C-I PERFORMANCE INFORMATION

  • Performance Step: 4 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-1 and E-2. CCW Pump A is powered from 480V Bus DS.

Comment:

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: 6 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:

2011 NRC JPM Admin SRO Al -2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 7 Form ES-C-i PERFORMANCE INFORMATION 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 JPMAdmin SROA1-2 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 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 SRO Al -2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 7 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-001-12, 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-001-12, 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 Al -2 NUREG 1021, Revision 9, Supplement 1

ATTACHMENT 10.2 Page 1 of 8 2000 TO 350° (MODE 4) MEL (Prior to exceeding 200° F (Entering MODE 4))

CONTINUOUS USE This revis n has been verified to be the latest revision available.

M EL Name (Print) Initial Signatuçe Date /

Date: 7id47 Shift: Tc/CO EQUlPMNT 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

/ 1 Loop or Train in operation RCS OPERATIONAL LEAKAGE ITS LCO RCS Operational Leakage 3.4.13 shall be limited to:

No pressure boundary leakage

)/- 5fri. 1 gpm unidentified leakage 10 gpm identified leakage 75 gpd primary to t.2 secondary leakage through any one steam generator RCS PRESSURE ISOLATION ITS LCO j All VALVES (PlVs) 3.4.14 A ( ( (except for valves in the RHR System)

OMM-00112 Rev. 68 Page 17 of 63

ATTACHMENT 10.2 Page 2 of 8 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 1 Containment Atmosphere Radioactivity monitor 1 Containment Fan Cooler

£f-/

Condensate Flow Rate monitor CHEMICAL AND VOLUME ITS LCO 2 - 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

,

gpm RCP B 9,gpm RCP C

/gprn ECCS ITS LCO 3.5.3

/ ,cJJ f I RHR Train AND 1 SI Train OPERABLE RWST ITS LCO .  % 300,000 gallons (91%)

3.5.4 2,/&ppm l950ppmand2400ppm C °F 45°Fand100°F CONTAINMENT ITS LCO A OPERABLE 3.6.1 CONTAINMENT AIR LOCK ITS LCO OPERABLE 3.6.2 CONTAINMENT ISOLATION ITS LCO All VALVES 3.6.3 rf( ,

CONTAINMENT PRESSURE ITS LCO psig -0.8 psig AND +1 .0 psig 3.6.4 CONTAINMENTAIR TEMPERATURE ITS LCO 3.6.5 QiL °F 120°F 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 CV Spray Trains COOLING SYSTEMS 3.6.6 AND 2 2 CV Cooling Trains SPRAY ADDITIVE TANK ITS LCO 3.6.7

/7 W I

% - 2505 gallons (32%)

c  % - 30% NaOH ISOLATION VALVE SEAL ITS LCO psig

  • 49 psig as indicated WATER (IVSW) SYSTEM 3.6.8 locally on P1-1910 2 2  % 85 gallons (49°ib)

IL/i

/ / All manual valves and I both automatic valves AUXILIARY FEEDWATER ITS LCO 1 AFW Flow Path (AFW) SYSTEM (when a S/G 3.7.4 2 AND is being used for heat removal) 1 MDAFW Pump 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)

(

SW Backup OPERABLE COMPONENT COOLING ITS LCO 2 Trains powered from WATER (CCW) SYSTEM 3.7.6 A / Emergency Power supplies RHV 6 (B and C pumps)

SERVICE WATER SYSTEM ITS LCO 2 Trains (SWS) 3.7.7 AND Y&fA Turbine Bldg Loop Isolation OiL valves OPERABLE ULTIMATE HEAT SINK (UHS) ITS LCO 12f ft Water level 218ft 3.7.8 °F SWS97°F

  • Actual ITS is 46.2 psig based on containment design pressure of 42 psig per EC 3604.

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 Page4of8 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 EMERGENCYAIR 3.7.10 TEMPERATURE CONTROL (CREATC)

SECONDARY SPECIFIC ITS LCO ,

I,uCIg 0.1 C/g DOSE EQUIVALENT ACTIVITY 3.7.15 IODINE-131 STARTUP TRANSFORMER ITS LCO 1 1 3.8.1.a DIESEL GENERATORS ITS LCO 2 3.8.1.b LCO3.0.4.b N/A DIESEL FUEL OIL AND ITS LCO DFO 19,000 gallons available STARTING AIR 3.8.3 from DFO Storage tank

/ 72YOgal Unit 1 15,000 gallons available from Unit 1 IC Turbine Fuel

,

Oil Storage tanks 3al EDG A EDG Air Receivers 210 psig Z3(2 psig EDG B Z 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 f / VDC - MCC-A Voltage> 126 VDC

/o VDC - MCC-8 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 /f 9 VAC *InveerA Voltage> 114 VAC

// VAC *Inveer B Voltage> 114 VAC Constant Voltage Transformers (CVT) I and 2 4160V BUSSES 2 AND 3 ITS LCO 3.8.9 VAC *4KV Bus 2 Voltage > 3.2KV 2OvAc 1

( *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 - ELV3O2IA 480V El AND E2 ITS LCO 480V Bus E-l Voltage 3.8.9 VAC (lowest phase) > 440 VAC 19 ZVAC 480V Bus E-2 Voltage (lowest phase) > 440 VAC

  • It is expected the Inverter AND 4KV Bus voltages will at least meet the following:

Inverter voltage between 118VAC 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:

480V Bus E-1 breaker, CMPT NO. 21A, FEED TO MCC-5 (NORM POWER) &

MCC-16, closed MCC-5 breaker, CMPT NO.

4BL, FEED TO INSTRUMENT BUS 1, closed Distribution Panel A, Circuit y

1 1, INVERTER A, closed Instrument Bus No. 1, Circuit 10, INSTRUMENT BUS 6,

/d closed Instrument Bus No. 2, Circuit 11, INSTRUMENT BUS NO.

(/ 7A AND 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 INSTRUMENT BUS 4,

/( closed Instrument Bus No. 3, Circuit 25, INSTRUMENT BUS (A

NO. 8, closed Instrument Bus No. 4, Circuit 12, INSTRUMENT BUS NO. 9A and 9B, closed OMM-001-12 Rev.68 Page22of63

ATTACHMENT 10.2 Page7of8 2000 TO 350° (MODE 4) MEL EQUIPMENT REFERENCE NUMBER MINIMUM TO GO ABOVE 200°F OPER,BLE (MODE 4)

RCS VENT PATH TRMS 3.2 2 dt - Reactor Head RC-567 and

-

/pe L RC-568 OPERABLE,

,&A CLOSED, Power Removed 2_ / j PZR Steam Space RC-569 cfc.cc

- -

and RC-570 OPERABLE,

,4i,f, /&n e £CLOSED, Power Removed RCS Vent Path valve RC-571 and RC-572 CLOSED OXYGEN (PRIMARY) TRMS 3.5.a 5if ,4S <0.1 ppm CHLORIDE (PRIMARY) TRMS 3.5.b 52( M/2f <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

. (  % together shall contain a total of Z/,r7ppm 3080 gallons (42%)

°F AND Tank B Boron Concentration 3q-  % 20,000 ppm and i.,O97ppm 22,500 ppm AND 145°F

/4°F BORIC ACID TANKS HEAT TRMS 3.6.c 2 TRACING PRIMARY WATER STORAGE TRMS 3.6.d  % 30,000 gallons (45%)

TANK SNUBBERS TRMS 3.18 // All safety-related snubbers (34)

/17 1 shall be OPERABLE APPENDIX R PATHWAYS 1OCFR5O, / Pathways clear CHECKED Appendix R (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 c9mplete, acceptable, and entered in Autolog.

/4 Signature Date E1M-001-12 Rev. 68 Page 23 of 63

ATTACHMENT 10.2 Page8of8 2000 TO 350° (MODE 4) MEL List any Mode Clearances in place:

thA Completed by: 2 7L4 Date

/

Reviewed by:

Shift Manager Date OMM-001-12 Rev. 68 Page 24 of 631

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.
  • The RO has completed QPTR calculation. The highest quadrant power tilt value is 1.055.
  • AFD is within limits.
  • AUTOLOG is NOT available.

Task Standard: Enters correct ITS Action Statements, makes log entry, and prioritizes actions.

Required Materials: Classroom/Simulator/Plant location with Control Room references General

References:

Improved Technical Specifications OMM-001-8, Control of System and Equipment Status, Revision 44 OMM-001 -11, Logkeeping, Revision 46 2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement I

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.
  • Make any necessary log entries.
  • Identify the highest priority action.

Time Critical Task: NO Validation Time: 20 minutes 2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement I

Appendix C Page 3 of 7 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Examiners NOTE: Performance Steps 1, 2, 3, and 4 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 1

Appendix C Page 4 of 7 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 Make handwritten log entry for misaligned rod lAW OMM-001 -11.

Standard:

  • ITS 3.1.4 Condition B Brief description of event, required action and associated time limit: Control rod is misaligned from bank by> 7.5 inches. [Align rod to bank within one hour from discovery time or carry out actions beginning with Condition B, B.2.1.1]

Examiners NOTE: Examiner can have candidate describe the brief description of event information rather than to copy required actions from Technical Specifications into the log.

Comment:

Performance Step: 4 Make handwritten log entry for QPTR exceeding 1.02.

Standard:

  • ITS 3.2.4 Condition A Brief description of event, required action and associated time limit.

[Reduce thermal power to 83.5% within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s]

  • Determine QPTR and reduce thermal power> 3% from RTP for each 1% of QPTR> 1.00 once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
  • Perform SR 3.2.1.1 and SR 3.2.2.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and every 7 days thereafter.

Examiners NOTE: Examiner can have candidate describe the brief description of event information rather than to copy required actions from Technical Specifications into the log.

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 Examiners NOTE: The candidate may have specified this at any point during the JPM.

  • Performance Step: 5 Identify highest priority action.

Standard:

  • 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.l).

OR

  • 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.I.I).

OR

  • Initiate boration to restore SDM to within limit within I hour (ITS 3.1.4 Condition B, Required Action B.2.1.2).

AND

  • 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

  • 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)

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.

Examiners NOTE:

Comment:

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:

Number of 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.
  • The RO has completed QPTR calculation. The highest quadrant power tilt value is 1.055.
  • AFD is within limits.
  • AUTOLOG is NOT available.

INITIATING CUE: You are the CR5:

  • Evaluate the given conditions for Technical Specification Action Statement(s) applicability.
  • Make any necessary log entries.
  • Identify the highest priority action.

2011 NRC JPM Admin SRO A2 NUREG 1021, Revision 9, Supplement I

Appendix C Job Performance Measure Form ESC-1 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.
  • The FIN Team has requested a clearance to change the SFP Filter.

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 and 5519.

SFP Filter area survey map.

General

References:

RWPs 5498, 5499 and 5519.

SFP Filter area survey map.

Handouts: RWPs 5498, 5499 and 5519.

SFP Filter area survey map.

2011 NRC JPM RO-SRO Admin A3 NUREG 1021, Revision 9, Supplement I

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 TJME:_______

  • Performance Step: I Determine the dose limits from the SEP 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.

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 #5519 states that continuous RC coverage is required.

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-i pre-job briefing is required.

Comment:

END OF TASK Termination Cue: When the candidate has determined the appropriate RWP and 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-C-1 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.
  • The FIN Team has requested a clearance to change the SFP Filter.

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 1iDIiEI3IW 31{1( P1RJ1IF hhuhh1 11111 11111 1111111111 11111 1111111111 11111 11111 11111 11111 1111111111 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 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 I4.IIj%.FIOI VVOI.1( PEI{I1II 111111 11111 11111 11111 11111 11111 1111111111 11111 liii! 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 liii!liii ALARA 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 THAN OR EQUAL TO 10 1000 MREM/HR.

Nbr Special Instructions 5 WORK DESCRIPTION ********************

S OPERATIONS ACTIVITIES 5 NO SPENT FUEL POOL WORK ON THIS RWP.

S 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 LHRA S.

T 10 20 ********LOCKED HIGH RADIATION AREA ENTRIES*****

20 20 l.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 IJLBE1fION t 7O1{K I1I.rviIrr 111111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 IIIN 11111 11111 11111 11111 11111 1111111111 11111 liii ALARA Task port 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 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 SO 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

PASSPORT - TOTAL EXPOSURE SYSTEM Ii.DIL4.rIorT 1 s o Ic 11111111111111111111111111111111111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 III!

ALARA Task port ID  : T1PH900 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 I IhI 111111111111111111111111111111hIll 11111 11111 liii!11111 liii!11111 11111 11111 11111 11111 11111liii!11111 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 --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 CONTAINMENT VESSEL WHEN THE REACTOR IS CRITICAL (EXCEPT

PASSPORT - TOTAL EXPOSURE SYSTEM

/OR1C p1J1 I liii hIll 11111111111111111111111111111111111hIll 11111 11111 IlI lihI 11111 11111 11111 11111 11111 11111 11111 III ALARA Task port 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.

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.

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. PAN/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 VVO1I( PEIIV1II 11111111111ll 11111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 liii 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 SO 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 1.PERMIS5ION 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 4

1 I

\ rIcN

.nT VJR.I( PER11IT 1111111111111111111111111111111111111111111111111111111111111 11111 111111111111111111 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 SUMP WITH REACTOR CRITICAL.

70

- End of Report -

PASSPORT - TOTAL EXPOSURE SYSTEM 1z\JI.6rIo1N /JR1( Piiiiir 111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 liii 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: MANNIP01 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 j--Distance--J I 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 Hold Points and Special Instructions 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 4/O1J( Piiiiii 11111111111111111111111111111111111111111111111111111111 1111111111 IIII11111 11111 11111 IlII 11111 11111 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 S ************** 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 ACCtJNULATED 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 111111 11111 11111 11111 11111 11111 11111 11111 11111 1111111111 11111 liii!11111 11111 liii!11111 hIll 11111 11111 11111 liii ALARA Task port ID  : T1PH900 RWP Number: 00005519 01 Page  : 3 Facility  : RNP 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 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 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.

SO 5.INTERMITTENT RC COVERAGE, UNLESS OTHERWISE 50 INSTRUCTED.

50 50 ************5OER 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 V7ORI( PE1]v1IT I 1111111111 11111 11111 11111 11111 1111111111 11111 11111 11111 11111 11111 11111 11111 11111 11111 11111 111111111

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 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.PREJOB 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 An

- Survey # 121410- DatelTime: 12/1412010 07:A ISOPI ia LOiAI LHRA/HPA controlled at locked door 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 innnnn flPM/lnfl nm2 RI, A/

.i1) <fl °%flAfl Prtit-iiItc.l Frisker Bkg. = 60 cpm 9) 60000 DPM/1 00 cm2 /y AIS 1) <30 %DAC Iodine Tenn. #2 MDA 79 dpm 7) 34000 DPM/100 cm2 ly

8) 33000 DPM/100 cm2 /y 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
12) 13000 DPMI100 cm2 ly RWP: 5910 2) 10000 DPM/100 cm2 ly I I1r Spar R eactor Power = 100% 5) 5000 DPM/100 cm2 ly

- 2OJOenerI Area Lrl Drip S 9

6) 3000 DPM/100 cm2 /y Ci)sr.ear san,pte ii jipeIF -lot Particles Detected 13) 2000 DPM/100 cm2 ly
14) 1200 DPM/100 cm2 ly
15) I100DPM/lOOcm2 ly Unless otherwise noted, dose rates in mremlhr.

Surveyor: Wes Brand Survey printed on: 1211512010 at: 07:47

Robinson Nuclear Plant Survey 12141 0 Data Point Details Page 1 of I -

Additional Information: Counted by: Wes Brand 12/14/2010 09:00 WRITask #: N/A Dose Rate (DR) Object Prefixes I Suffixes:

Work Area Code 4_3600 *

= ContaclHS = Hot Spot ComponentITag Namel_N/A + = 30 cm No prefixGeneral Area Dose RE Tag Suffix Name:[_N/A Suffixes: nNeutron, bBeta Short Name:J N/A Unless otherwise noted, dose rates in mremlhr.

Postings Legend:

RCA=Radiologically Controlled Area CMContamination Area RMRadiation Area HPA=Hot Particle Area HRA=High Radiation Area RMARadioactive Material Area LHRA=Locked High Radiation Area CRCFE=Contact Radiation Control For Entry VHRA=Very High Radiation Area CRCPE=Contact Radiation Control Prior To Entry ARAAirborne Radioactivity Area Instruments Used:

Efficienc No. I Model Serial I Probe Serial Cal Date Type /y p a 1 61128 776386 NA NA 03/29/2011 00:0C DIR N/A N/A N/A 2 LM-177 776080 44-9 NA 10/12/2011 00:0C C/R N/A 0.100 N/A 3 RO-20 778069 NA NA 08/13/2011 00:0( DIR N/A N/A N/A 4 TennO2 1217320 !Tenn INA 06/30/2011 00:OCj CIR IN/A 0.242 0.221 No. Type Inst. Value Units Position Notes Smear N/A /y 20001 3 DPM/100 cm2 Floor N/A o<MDI DPM/100 cm2 2 Smear N/A 131y 10001 DPM/100 cm2 vaIl 3 Smear N/A /i 100001 3

1 DPM/100 cm2 Filter Housing N/A <MDI DPM/100 cm2 4 Smear N/A ply 15001 DPM/100 cm2 /ent valve 5 Smear N/A 131y 5001 DPM/100 cm2 rransmitter 6 Smear N/A ?y 3001 3

1 DPM/100 cm2 Vail 7 Smear N/A ply 34001 DPM/100 cm2 Floor N/A ci<MDI DPM/100 cm2 8 Smear N/A /i 33001 3

1 DPM/100 cm2 Floor N/A a<MDI DPM/100 cm2 9 Smear N/A j3/y 60001 DPM/100 cm2 Floor N/A cx<MDI DPM/100 cm2 10 Smear N/A ly 19001 3

I DPM/100 cm2 Floor 11 Smear N/A 30001 13/i DPM/100 cm2 Flow Transmitter N/A i<MDI DPM/100 cm2 12 Smear N/A 13/y 13001 DPM/100 cm2 rransmitter 13 Smear N/A 131y 2001 DPM/100 cm2 Floor 14 Smear N/A ply 1201 DPM/100 cm2 Floor 15 Smear N/A 13ly 1101 DPM/100 cm2 Floor Wipe ly 20,001 3

l CCPM :loor 2 Wipe ly 10,001 3

l CCPM 900r 3 Wipe /i 100,001 3

1 CCPM :loor 4 Wipe 13/y 121 CCPM :loor AirSample <31 %DAC Particulate 3eneral Area Air Sample

<31 %DAC Iodine DR N/A *1500 iRem/hr :ilter Housing N/A +1000 iRem/hr DR N/A 200 Rem/hr DR I N/A +600 iRem/hr DR 1 N/A +100 Rem/hr DR 1 N/A +50 nRem/hr DR 1 N/A +25 TiRem/hr DR I N/A +200 nRem/hr DR I N/A +400 nRem/hr DR N/A +200 iRem/hr Survey printed on: 1211 5/2010 at: 07:47

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 SROA4 K/A

Reference:

G2.4.41 (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:

  • 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.
  • SEP 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-0i, 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-01, SEP Diagram Handouts: EPCLA-Oi, EPCLA-04, EAL Matrixes, EPNOT-Oi, SFP 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 I

Appendix C Page 3 of 13 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 EAL5.

Examiners NOTE: Provide copies of the EAL Matrix to the candidate.

Comment:

  • 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.I, 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:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 13 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 If Reactor Coolant temperature is < 200 degrees F, Then evaluate COLD conditions EAL Matrix. (Step 8.3.3)

Standard: Candidate reviews EAL COLD Conditions Matrix and does NOT identify any EALs that have been exceeded on this matrix.

Examiners NOTE:

Comment:

Performance Step: 4 Announce to Control Room or TSC personnel that you are assuming the position of SEC. (Step 8.3.4)

Standard: Candidate makes announcement that he has assumed the duties of the Site Emergency Coordinator (SEC).

Examiners NOTE:

Examiners CUE: Acknowledge the announcement of the SEC if necessary.

Comment:

Performance Step: 5 If an ALERT has been declared, Then proceed to Attachment 10.6 for an ALERT. (Step 8.3.6)

Standard: Candidate proceeds to Attachment 10.6 for the declaration of an ALERT.

Examiners NOTE:

Comment:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 13 Form ES-C-i PERFORMANCE INFORMATION

  • Performance Step: 6 Declares the highest EAL classification identified within 15 minutes.

Standard: Candidate declares ALERT based on RA 2.1 within 15 minutes of Start Time.

Examiners NOTE:

Examiners CUE: Acknowledge classification from Shift Manager.

Comment:

Time Critical Stop Time for EAL Classification: (15 Minutes)

Time Critical Start Time for EAL Notification:

Performance Step: 7 Direct the Emergency Communicator to prepare for communication activities in accordance with EPNOT-01, 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:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 13 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 8 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:

  • Performance Step: 9 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: 10 Enter Line 2 information.

Standard: Marks INITIAL.

Examiners NOTE:

Comment:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 13 Form ES-C-i PERFORMANCE INFORMATION

  • Performance Step: 11 Enter Line 3 information.

Standard: Enters H.B. Robinson as the Site and enters CONFIRMATION PHONE NUMBER.

Examiners NOTE:

Examiners CUE: When candidate requests the ERO phone list, tell him the Confirmation Phone Number is 843-383-3685.

Comment:

  • Performance Step: 12 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-2, CV Area R-5, Spent Fuel Pit Area R-1 hR-I 2, Process Monitor CV Air and Plant Vent (when sampling CV)

R-14, Plant Vent R-21, Fuel Handling Building Upper Level Examiners NOTE:

Comment:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 13 Form ES-C-i PERFORMANCE INFORMATION

  • Performance Step: 13 Enter Line 5, Protective Action Recommendation information.

Standard: Marks NONE.

Examiners NOTE:

Comment:

  • Performance Step: 14 Enter Line 6, EMERGENCY RELEASE, information.

Standard: Marks Is Occurring.

Examiners NOTE:

Comment:

Performance Step: 15 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:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 13 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 16 Enter Line 8, EVENT PROGNOSIS, information.

Standard: Marks Degrading.

Examiners NOTE:

Comment:

  • Performance Step: 17 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 0.

Examiners NOTE:

Comment:

  • Performance Step: 18 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:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 13 Form ES-C-I PERFORMANCE INFORMATION

  • Performance Step: 19 Enter Line 11 information, AFFECTED UNITS.

Standard: Marks Unit 2.

Examiners NOTE:

Comment:

Performance Step: 20 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:

Examiners CUE: Provide unit shutdown Time and Date as 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 11712011.

Comment:

2011 NRC JPM Admin SRO A4 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 1 1 of 13 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 21 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: 22 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)

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 13 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

Appendix C Page 13 of 13 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

  • 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 1

ATT%1Ei1O.7 MAf5&e4 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM 1.XDRILL ACTUAL EVENT MESSAGE #

2. INITIAL FOLLOW-UP NOTIFICATION: TIME______ DATE I I AUTHENTICATION#
3. SITE: A Confirmation Phone # c.tS
4. EMERGENCY F1 EVENT ALERT SITE AREA EMERGENCY GENAL EMERGENCY CLASSIFICATION: A 1
  • --1 fSqL

...

/BED EAL#/<I/

q EAL, M 1

,RIPONJ 5

L 1

fi i4(/ci (/e L- 1-tt(h;41 --.

/?t d-j..iq e.V /LJt;

5. PROTEQiE ACTION REJOMMENDATIONS:

d NNE I &

2 L/ nt.:

EVACUATE j SHELTER CoNsIDE THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.

j OTHER

6. EMERGENCY RELEASE: None Is Occurring Has Occurred Not Within normal Above normal operating Under
7. RELEASE SIGNIFICANCE:

applicable operating limits limits evaluation

8. EVENT PROGNOSIS: Improving J Stable I Degrading
9. METEOROLOGICAL DATA: Wind Direction* from degrees Wind Speed* - mph

(*May not be available for Initial Notifications)

Precipitation* 0 Stability Class*

10. DECLARATION TERMINATION Time AItii) Date 11.AFFECTEDUNIT(S): Lii I1 EI
12. UNIT STATUS: Ui Power Shutdown at Time Date _I /

(Unaffected Unit(s) Status Not Required for Initial Notifications) U2 O Power Shutdown at Time 23 OC Date _/.j 7 IlL

13. RC4J(

7 4& /efl /k.Y eL 1

Power Shgown a Time 4 Dates L. /

EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.

14. RELEASE CHARACTERIZATION: TYPE: Elevated j Mixed Ground UNITS: Ci Cl/sec ItCi/sec MAGNITUDE: Noble Gases:___________ lodines:____________ Particulates:___________ Other:

FORM: Airborne Start Time Date _/ /Stop Time Date _I /

Liquid Start Time Date _I I...Stop Time Date _I I..._

15. PROJECTION PARAMETERS: Projection period: Estimated Release Duration Projection performed: Time Date _I I...._......
16. PROJECTED DOSE: DISTANCE TEDE (mRem) Adult Thyroid CDE (mRem)

Site boundary 2 Miles 5 Miles 10 Miles

17. APPROVED BY: tJd(cIAf4L Title_________ Time AAIfl) L 4

DatjtL9 NOTIFIED BY:_____ RECEIVED BY: Time Date_I____

EPNOT-O1 Rev. 35 Page 34 of 61

ATTACHMENT 10.7 Page 2 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM GOVERNMENT AGENCIES NOTIFIED NOTIFICATION: TIME DATE Get Time/Date I AUTHENTICATION# Get Authentication Codel 10.1.1.1 Name: Date/Time: Agency: Chesterfield County EOC 10.1.1.2 Name: Date/Time: Agency: Chesterfield County WP 10.1.1.3 Name: Date/Time: Agency: Darlington County EOC 10.1.1.4 Name: Date/Time: Agency: Darlington County WP 10.1.1.5 Name: Date/Time: Agency: Lee County EOC 10.1.1.6 Name: Date/Time: Agency: Lee County WP 10.1.1.7 Name: Date/Time: Agency: NRC (via ETS or Bell Phone) 10.1.1.8 Name: Date/Time: Agency: NRC Resident Inspector 1O.i.1.9 Name: Date/Time: Agency: State of SC BWP 10.1.1.10 Name: Date/Time: Agency: State of SC WP Ii1 ISend Form!

EPNOT-01 Rev. 35 Page 35 of 61

ATTACHMENT 10.7 Page 3 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION CAUTION Initial notifications are to be made within 15 minutes of the declaration of an emergency.

Follow up notifications shall be made within 60 minutes from the completion of the previous notification. The earliest time indicated for any agency will be the start time for the follow up notification for all agencies.

All efforts should be expended to obtain information required for the Electronic Emergency Notification Form. IF an upgrade in classification occurs when the follow-up message is due, THEN upgraded ENF forthcoming should be annotated in Remarks. This information is to be promptly transmitted to the State and County agencies, as soon as it is available.

Messages should include an up-to-date description of what is happening at the plant within the constraints of timely notifications. To ensure messages contain adequate and accurate information about current plant conditions, messages should be developed as promptly as possible. ENF reviews will be conducted by EOF Facility personnel, if available. It may be necessary to determine a cut off time for new message information so that these reviews can be made. The ERM will direct EOF personnel through the ENF line by line and the POA, TAM and RCM will verify the accuracy of the ENF using the following guidance:

Lines 1, 2, 3, 4 POA verifies accuracy

Lines 5, 6, 7 RCM verifies accuracy

Line 8 TAM verifies accuracy

Line 9 RCM verifies accuracy

Lines 10, 11, 12 POA verifies accuracy

Line 13 POA verifies accuracy

Lines 14, 15, 16 RCM verifies accuracy (reference the Rascal Source Term Summary sheet)

Line 17 ERM approves Lines 1 through 13 AND Line 17 MUST BE COMPLETED on an INITIAL Electronic Emergency Notification Form. Information for Line 9 may not be available for the initial notification. If met data is not available, then state this in the Remarks (Line 13) and provide the data on a follow-up notification, as soon as the data is available. For TERMINATION messages, only Lines 1 through 4, 10, and 17 are required.

Information included on the initial form AND Lines 14 through 16 MUST BE COMPLETED on a FOLLOW-UP Electronic Emergency Notification Form.

An electronic emergency notification form is available and can be accessed through the NGG Standard Desktop.

EPNOT-01 Rev. 35 Page 36 of 61

ATTACHMENT 10.7 Page 4 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Item Instructions Line 1:

NOTE: When DRILL is selected, the Electronic Emergency Notification Form will display, This is a drill.

INDICATE whether the message is a DRILL OR an ACTUAL EVENT.

ENTERIVERIFY the MESSAGE NUMBER.

The message number is consecutive from the initial notification message to the termination notification message. It does not begin again at I for any reason during the course of an emergency event.

Line 2:

NOTE: Messages that contain a change in emergency classification, a termination, OR a change in Protective Action Recommendations (PAR) are INITIAL notifications. All other messages are considered FOLLOW-UP notifications.

INDICATE whether the message is an INITIAL notification OR a FOLLOW-UP notification.

NOTIFICATION TIME!DATE: The Notification Time/Date is completed when first voice contact is made during offsite agency notification. It will be entered after the completion of Line 17. Additional information is provided at the next reference to Line 2.

Line 3:

NOTE: Confirmation phone numbers are provided in a drop-down menu box.

ENTER H. B. Robinson.

Confirmation Phone #: ENTER the number that any offsite agency can call to verify the message is authentic. Ensure the number given is a location where the phone will be answered. DHEC is required to verify the message by their procedure within 15 minutes.

EPNOT-01 Rev. 35 Page37of6l

ATTACHMENT 10.7 Page 5 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION NOTE: A change in PARs must be an initial notification. However, the declaration time does not change and the time for the change in PARs needs to be recorded in the Remarks section.

Line 4: INDICATE the EMERGENCY CLASSIFICATION that is being declared.

IF this is an initial message, THEN INDICATE the current emergency classification.

IF this is a follow-up message OR a termination message, THEN INDICATE the same emergency classification as the previous notification.

EAL DESCRIPTION should contain a short narrative of the emergency classification. The narrative should be in laymans terms and not include any slang or acronyms, i.e., ATWS, RCP, WGDT, that are commonly used at the plant. This description must be easily understood by individuals without nuclear industry experience.

Line 5: INDICATE the appropriate PROTECTIVE ACTION RECOMMENDATIONS.

IF the emergency classification is a GENERAL EMERGENCY, THEN ENTER the sectors for which the recommendations (evacuate or shelter) are applicable.

IF the projected dose to the thyroid is 5 Rem or greater at the site boundary, THEN the consideration of Potassium Iodide (KI) must be included as a PAR.

Line 6: INDICATE whether OR not an EMERGENCY RELEASE is occurring OR has occurred. Emergency Releases affect or have the potential to affect offsite environments. (The SEC makes the determination on Emergency Release, reference EPCLA-01 for additional guidance). A gaseous Emergency Release is any of the following:

1. An approved monitored release was occurring and the reading on the radiation monitor designated to monitor this release increases due to the event.
2. Any release due to the event that was not previously approved.
3. Anytime a primary to secondary leak causes an emergency declaration, a release should be considered is occurring.

EPNOT-01 Rev.35 Page38of6l

ATTACHMENT 10]

Page 6 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION A liquid Emergency Release is any of the following:

1. An approved monitored release was in progress and the reading on the radiation monitor designated to monitor this release increases but does not isolate on an alarm signal.
2. The rupture of a system which releases radioactive liquids into an area that affects or has the potential to affect an offsite environment.

Line 7: INDICATE the RELEASE SIGNIFICANCE.

IF NO Emergency Release has occurred, THEN SELECT not applicable.

IF an emergency release is in progress or has occurred AND the release significance has NOT been determined, THEN SELECT Under Evaluation.

IF the release significance has been determined, THEN INDICATE whether or not the release is Within Normal Operating Limits OR Above Normal Operating Limits.

IF the projected dose at the site boundary is below 25 mRem TEDE AND 75 mRem Thyroid CDE, THEN MARK Line 7 as Within Normal Operating Limits.

Otherwise, MARK Line 7 as Above Normal Operating Limits.

Line 8: INDICATE whether the EVENT PROGNOSIS is Improving, Stable, or Degrading. The Site Emergency Coordinator OR the Plant Operations Advisor AND the Technical Analysis Manager should be consulted, if assistance is needed, in making this determination.

EXAMPLES IF there is a probable escalation of Emergency Classification, continued deterioration of plant conditions OR an increase in Protective Action Recommendations (PARs), THEN indicate the prognosis as Degrading.

IF there are no expected changes in Emergency Classifications, plant conditions OR Protective Action Recommendations (PARs), THEN the event prognosis should be considered Stable.

IF there is a probable downgrade in Emergency Classification, plant systems are being returned to service OR a reduction in Protective Action Recommendations (PARs), THEN the event prognosis should be considered Improving.

EPNOT-01 Rev. 35 Page 39 of 61

ATTACHMENT 10.7 Page 7 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 9:

NOTE: Meteorological and % power data is auto-populated from ERFIS in the electronic Emergency Notification Form, by selecting Import Plant/MET Data at Line 9 of the electronic ENF.

CAUTION The wind direction is recorded as the from direction, if it is obtained from a source other than ERFIS, it may need to be verified/changed.

NOTE: For all releases not via the plant stack, ground wind direction should be used.

Elevated wind direction is taken from the lOOm height on the Met Tower. Ground wind direction is from the 32m height.

NOTE: Ground wind direction should be used if a release is not in progress.

RECORD the METEOROLOGICAL DATA from ERFIS.

IF ERFIS is unavailable, THEN OBTAIN Meteorological Data from the National Weather Service Office (see ERO Telephone Book), as available. ENTER the Stability Class from procedure EPRAD-03 for dose projection.

EPNOT-Ol Rev. 35 Page 40 of 61

ATTACHMENT 10.7 Page 8 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 10:

CAUTION Chronological order of the times recorded on the form is critical. The time listed on Line 10 (DECLARATION TIME) should be the first time entered on the form. The times on the Electronic Emergency Notification Form should be completed as follows: first- Line 10 (DECLARATION TIME), second- Line 17 (APPROVAL TIME), and last- Line 2 (NOTIFICATION TIME). For example Line 10 at 12:00 and Line 17 at 12:10 and Line 2 at 12:14. The first voice contact (NOTIFICATION TIME) time should not be documented until an approved form is available.

NOTE: A change in PARs must be an initial notification. However, the declaration time does not change and the time for the change in PARs needs to be recorded in the Remarks section.

INDICATE whether the notification is for an event DECLARATION or TERMINATION. ENTER the time AND date the emergency classification in Line 4 was declared. This time should not change unless the emergency classification has changed OR the event has been terminated.

Line 11: INDICATE 2 as the AFFECTED UNIT. Unit 2 is the default value for the H.B.

Robinson site.

Line 12:

NOTE: Meteorological and % power data is auto-populated from ERFIS in the electronic Emergency Notification Form, by selecting Import Plant/MET Data at Line 9 of the electronic ENF.

ENTER the UNIT STATUS.

IF the reactor is at power, THEN ENTER the current reactor power.

IF the reactor is shutdown, THEN ENTER the time AND date of the shutdown.

Line 13: Additional information may be entered in the REMARKS.

EPNOT-01 Rev. 35 Page 41 of 611

ATTACHMENT 10.7 Page 9 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 14:

NOTE: Dose data is auto-populated in the electronic Emergency Notification Form, by selecting Import Dose Projection Data at Line 14 of the electronic ENF. Dose data is populated from saved dose projection files created in RASCAL.

NOTE: Dose data will only be imported if Line 6 has a release occurring or has occurred and Line 7 is within or above the normal operating limits.

NOTE: Lines 14 through 16 are not required on an initial ENF. However, if either within normal operating limits or above normal operating limits is selected for Line 7, then lines 14 through 16 are to be completed and included in the initial ENF.

NOTE: Lines 14 through 16 are not required if line 6 has none selected. If Line 7 has under evaluation selected, then the development of dose projections is to become a priority and once completed, included on a follow-up ENF.

ENTER the EMERGENCY RELEASE DATA provided by Dose Projections on Lines 14 through 16. IF None has been selected for Emergency Release (Line 6), THEN Line 14 is not required to be completed.

NOTE: RNP cannot have an Elevated release.

INDICATE the RELEASE TYPE: Mixed or Ground 1

For RELEASE MAGNITUDE, ENTER the Noble Gas and Iodine Activity in Curies (Ci).

For FORM, SELECT Airborne AND ENTER the Release Start Time/Date AND Stop Time/Date.

Line 15: Projection period is not applicable for RNP and can be left blank. For PROJECTION PARAMETERS: ENTER the estimated release duration in hours AND ENTER the time AND date the projection was performed.

EPNOT-01 Rev. 35 Page 42 of 6

ATTACHMENT 10.7 Page 10 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 16:

NOTE: The minimum value for doses to be entered on the electronic emergency notification form is 0.1 mRem. Any dose values below 0.1 mRem should entered as <0.1 mRem.

NOTE: When a release is in progress, the dose projection data will be auto-populated in the electronic emergency notification form from RASCAL.

For PROJECTED DOSE, RECORD the TEDE dose in mRem AND the THYROID CDE in mRem for each distance away from the site in the dose columns provided. ENSURE that the units are recorded in mRem.

Line 17:

CAUTION Chronological order of the times recorded on the form is critical. The time listed on Line 17 (APPROVAL TIME) should be the second time entered on the form. The times on the Electronic Emergency Notification Form should be completed as follows: first- Line 10 (DECLARATION TIME), second- Line 17 (APPROVAL TIME), and last- Line 2 (NOTIFICATION TIME). For example Line 10 at 12:00 and Line 17 at 12:10 and Line 2 at 12:14. The first voice contact (NOTIFICATION TIME) time should not be documented until an approved form is available.

COMPLETE the APPROVED BY section. IF the message is to be transmitted from the Control Room, THEN it must be approved and signed by the SEC. IF the message is to be transmitted from the EOF, THEN it must be approved by the ERM prior to transmitting the notification to the State and County agencies.

Any changes made between this signature AND the release of the message must be initialed/approved by the SEC OR ERM.

NOTE: Once the ENF is approved, changes cannot be made.

The individual who makes first voice contact with the offsite agencies is responsible for entering his/her name in the blank marked NOTIFIED BY upon completion of the message.

The RECEIVED BY blank will be completed by the offsite agencies.

EPNOT-01 Rev. 35 Page 43 of 61

ATTACHMENT 10.7 Page 11 of 11 NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM INSTRUCTIONS FOR COMPLETION Line 2:

CAUTION Chronological order of the times recorded on the form is critical. The time listed on Line 2 (NOTIFICATION TIME) should be the last time entered on the form. The times on the Electronic Emergency Notification Form should be completed as follows: first- Line 10 (DECLARATION TIME), second- Line 17 (APPROVAL TIME), and last- Line 2 (NOTIFICATION TIME). For example Line 10 at 12:00 and Line 17 at 12:10 and Line 2 at 12:14. The first voice contact (NOTIFICATION TIME) time should not be documented until an approved form is available.

NOTIFICATION TIMEIDATE: The Notification Time/Date is completed when first voice contact is made during offsite agency notification. First voice contact will be considered complete after site identification, type of message and emergency classification is provided to the offsite agency.

RECORD the time of first voice contact with any offsite agency as verified on the phone by roll call.

AUTHENTICATION #: ENTER the AUTHENTICATION number in the space provided on the Electronic Emergency Notification Form. This information will be entered after the form is initially developed and transmitted to offsite agencies. Authentication is not required but the State/County representatives should be asked, Would anyone like to authenticate this message? IF yes, THEN they will pick a number AND you respond with the corresponding word (see the authentication code list or select the authentication code button on the electronic emergency notification log).

GOVERNMENT AGENCIES NOTIFIED After review of the ENF, RECORD the name of the individual from each agency and the date/time the information was provided.

Upon completion, transmit the information electronically using the Send Form button. This will also automatically update the ENF with the earliest notification time.

EPNOT-01 Rev. 35 Page 44 of 61

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