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| {{#Wiki_filter:2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-Admin-l | | {{#Wiki_filter:}} |
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| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-Admin-l Task Title: Respond to a complete loss of SDC with the Refueling Pool available; (Estimate Time to Boiling and Core Uncovery)
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| Task Number: 202.023 KIA
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| ==Reference:==
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| 2.1.20 (4.6, 4.6)
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| Method of testing:
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| Simulated Performance: 0 Actual Performance: r8J Classroom: r8J Simulator: 0 Plant: 0 READ TO THE APPLICANT:
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| Initial Conditions:
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| : 1. Unit-2 RCS is drained to 39 feet.
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| : 2. Nozzle Dams are not installed
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| : 3. RCS temperature is 120 OF.
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| : 4. The reactor was shut down 20 days ago after an extended period of full power operation.
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| : 5. Refueling operations, replacing 91 fuel assemblies with fresh assemblies, were completed 30 hours ago.
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| : 6. A loss of shutdown cooling has occurred.
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| : 7. You are performing the duties of an extra CRO.
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| Initiating Cue:
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| The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, Step IV.B.S. Are there any questions? You may begin.
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| Task Standard:
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| Terminating Cue: This JPM is complete when the AOP-3B, ATTACHMENT (11),
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| CALCULATION OF TIME TO BOIL OR CORE UNCOVERY, worksheet has been completed. No further actions are required.
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| Evaluation Criteria:
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| : 1. All critical steps completed (denoted by shading).
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| : 2. All sequential steps completed in order.
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| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
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| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
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| Required Materials:
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| : 1. Procedures and manuals normally available in the plant General
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| ==References:==
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| AOP-3B, ABNORMAL SHUTDOWN COOLING CONDITIONS, ATTACHMENTS 8 thru 13 Time critical task:
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| No Validation Time:
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| 20 minutes Simulator Setup:
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| : 1. None required
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| ELEMENT STANDARD
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| (* = CRITICAL STEP)
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| Time Start: - - -
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| o Locates AOP-3B, Step IV.B.5 Same as element i CUE:
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| : 1. Calculate Time To Boil.
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| : a. Determine the Time To Boil at 24 hours after shutdown from the appropriate figure, based on RCS level and RCS temperature:
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| Note to evaluator:
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| Completion of this JPM requires interpreting graphs that have the potential to induce minor variations in calculated results.
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| TIME TO START .... Determines TTB @ 24 hrs is
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| ;LJ'..JJ,;l'_~."'''' HOURS}\~.~~* approximately 11.3 minutes (11 to 11.5 minutes) o ATTACHMENT (9), TIME TO START BOILING AFTER LOSDC 24 HOURS Determines this step is NIA AFTER SHUTDOWN SG U-TUBES FULL o b. Obtain themDJtipJierfrom Al1t\tHMEN!(rO),¥U~TIPLIER ON~IME Using ATTACHMENT (10),
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| TO~SWMTBQILINGi;OrucoRE UNCOVERY determines multiplier of 3.08 b *~ontitne*~i shrltdoWn.*
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| i
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| .. . . *
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| : c. Multiply the Time To Boil at 24 hours after shutdown by the multiplier.
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| Using ATTACHMENT (10), page 1, determines the Post Refueling multiplier is applicable with a value of 1.4 X post refueling Performs calculation 11.3 X 3.08 X 1.4 = 48.7 mins o d. Independently verify the calculation. Requests independent verification
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| : 2. Calculate Time To Core Uncovery:
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| ELEMENT STANDARD
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| (* = CRITICAL STEP)
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| : a. Determine the Time To Core Uncovery at 24 hours after shutdown from the appropriate figure, based on RCS level and RCS temperature:
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| Note to evaluator:
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| Completion of this JPM requires interpreting graphs that have the potential to induce minor variations in calculated results.
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| : Cl ATrJ\.cIW~r(12),TIMl3:TO CORE UNCOVERYAFfll!ERLOSD~:~4l:10URS Determines Time to Core Uncovery
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| @ 24 hrs is approximately 128 AF'tERSHUTDdWNNO%Nh~nE;DAMS, minutes (126 - 130 mins)
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| NuiN'mcTloN, NUCO:{:,;DLE~#OLE Cl ATTACHMENT(13), TIME TO CORE UNCOVERY AFTER LOSDC 24 HOURS AFTER SHUTDOWN WITH NOZZLE Determines this step is NIA DAMS, NO INJECTION, NO COLD LEG HOLE Cl b. Obtain the multiplier from ATTACHMENT(10), MULTIPLIER ON TIME Using ATTACHMENT (10),
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| TO START BOILING OR CORE Ul'lCOVERY, determines multiplier of 3.08 based on time after shutdown.
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| : c. Multiply the Time To Core Uncovery at 24 hours after shutdown by the multiplier.
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| Using ATTACHMENT (10), page 1, determines the Post Refueling Cl Obtain value for Post Refueling Multiplier multiplier is applicable with a value of 1.4 Performs calculation 128 X 3.08 X 1.4 552 mins or 9.2 hrs Cl d. Independently verify the calculation. Requests independent verification Terminating Cue: This JPM is complete when the AOP-3B, ATTACHMENT (11),
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| CALCULATION OF TIME TO BOIL OR CORE UNCOVERY, worksheet has been completed. No further actions are required.
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| ~--------------------------------------------------------------.
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| Verification of Completion Job Performance Measure Number: RO-ADMIN-l Applicant:
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| NRC Examiner:
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| Date Performed:
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| Facility Evaluator:
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| Number of Attempts:
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| Time to Complete:
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| Follow up Question: _____________________________________
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| Applicant Response: ___________________________
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| Result: SAT _ _ _ _ __ UNSAT - - - - - - - - -
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| Examiner's Signature and Date: ______________________
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| APPLICANT'S CUE SHEET Initial Conditions:
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| : 1. Unit-2 RCS is drained to 39 feet.
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| : 2. Nozzle Darns are not installed
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| : 3. RCS temperature is 120 OF.
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| : 4. The reactor was shut down 20 days ago after an extended period of full power operation.
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| S. Refueling operations, replacing 91 fuel assemblies with fresh assemblies, were completed 30 hours ago.
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| : 6. A loss of shutdown cooling has occurred.
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| : 7. You are performing the duties of an extra CRO.
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| Initiating Cue:
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| The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, Step IV.B.S. Are there any questions? You may begin.
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| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-Admin-2
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| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-Admin-2 Task Title: Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Instrumentation Task Number: 204.129 KIA
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| ==Reference:==
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| 2.1.25 (3.9, 4.2)
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| Method of testing:
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| Simulated Performance: D Actual Performance: [;g]
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| Classroom: [;g] Simulator: D Plant: D READ TO THE APPLICANT:
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| 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.
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| Initial Conditions:
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| : 1. Unit-1 power was recently reduced to 70% power to facilitate repairs to 11 SGFP.
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| : 2. CEAs are currently inserted to lOS inches on Group 5.
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| : 3. Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.1.A and 3.3.1.D have been entered.
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| : 4. The plant computer has "crashed" and is inoperable.
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| : 5. You are performing the duties of the CRO.
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| : 6. NI Readings are as follows:
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| Channel Lower Upper A 69.9 70.9 i
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| B 67.3 6S.3 C 6S.7 69.7 D 0 0 Initiating Cue:
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| AOP-7H has been implemented and the CRS directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per Section IV.E. Are there any questions? You may begin.
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| Task Standard:
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| This JPM is complete when calculated azimuthal power tilt (Tq) is determined to be outside acceptable limits.
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| Evaluation Criteria:
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| : 1. All critical steps completed (denoted by shading).
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| : 2. All sequential steps completed in order.
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| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
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| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
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| Required Materials:
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| : 1. Procedures and manuals normally available in the plant General
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| ==References:==
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| : 1. AOP-7H, Loss of Plant Computer in Mode One or Two.
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| : 2. T.S. 3.2.4 Azimuthal Power Tilt - Tq Time Critical Task:
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| No Validation Time:
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| 20 minutes Simulator Setup:
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| - - 1. None
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| ELEMENT STANDARD
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| (* = CRITICAL STEP)
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| Time Start: - - -
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| , CUE: Shift Manager directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per AOP-7H, Section IV.E.
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| 1:1 Locates AOP-7H, Section IV.E. - IF Greater than Same as element.
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| 50% Rated Thermal Power, Monitor Tq.
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| , I:J 1. Calculate upper AND lower Tq using ANY of
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| ~h=£_o_ll_o_w_in_g_:_ _ _ _ _ _ - - -_ _ _ _-+-_ _ _ _ _ _ _ _ _ _ _ _- - - 1 1:1 IF ALL four Linear Power Channels are operable, Determines Step is N/A THEN perform EITHER of the following:
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| NOTE to Evaluator: If Opscalc is used then steps under a are critical, if Manual Calc is performed then step under b is critical.
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| CUE: Opscalc is available to use OR NOTE A total of 3 upper and 3 lower Linear detectors are required to be operable. The failed detectors can be on different channels. Determines Step is applicable I:J IF only 3 Linear Power Channels are operable AND Reactor Power is less than 75%,THEN perform EITHER of the following:
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| Records NI values on Attachment 5 Same as element.
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| Same as element.
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| ELEMENT STANDARD
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| (* = CRITICAL STEP)
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| ;Se~~ct~"112 Tq~\ .* lation"from Same as element.
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| drdptIOWh me}ili>\ .
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| =~- , Enters data from Attachment 5.
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| Enrls data and$el~~t§\ Calculates Upper Tq .03013
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| ""Calculate" Calculates Lower Tq .02970 CUE: Manual Calc is acceptable o b. Calculate Tq using the method in ATTACHMENT 5), Tq CALCULATION USING EXCORE DETECTORS
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| <~, " Records Readings on Attachment 5 g.Ji.;Cor~.thi readi~gs 011 ATTA~Nr and performs calculations per formula on Attachment 5
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| '~~), T~CALCUL~TION USING'
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| .ni:D$::cOREDI¥TE~TORS\ Calculates Upper Tq .03013 Calculates Lower Tq .02970 OR o
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| * Notify the Reactor Engineering Work Determines Step is NtA Group to provide an alternate method to monitor Tq.
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| o Once every 12 hours, recalculate the Azimuthal Determines step is NtA at this time Power Tilt using the Excore Detectors PER Step E.l, OR Informs CRO to add note to Shift Page 11. Turnover rD~. .q is greater than 0.03, THEN perform the Determines Tq is greater than 0.03
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| ~wing actions: and escalates issue to CRS Terminating Cue: This JPM is complete when calculated azimuthal power tilt (Tq) is determined to be outside acceptable limits. No further actions are required.
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| Appendix C Job Perfonnance Measure Fonn ES-C-l Verification of Completion Job Perfonnance Measure Number: RO-Admin-2 Applicant:
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| NRC Examiner:
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| Date Perfonned:
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| Facility Evaluator:
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| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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| Time to Complete:
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| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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| - -.....- - - - - - - - - - - - - - - - - - - - - - - - - -
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| Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
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| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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| AOP-7H Rev 23 ATTACHMENT (2)
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| Page 1 of2 EXCORE LHR MONITORING WHEN THE DAS IS OUT OF SERVICE UNIT 1:
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| Date/Time Measured FxyT Assumed FxyT from NEOP-l3.
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| Figure 1 IV.A.I Maximum Allowed Thermal Power from NEOP-l3, Figure I-IV.A.l Thermal Power limit from NEOP-l3.
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| Figure 1 IV.A.2 Actual Thermal Power Level Complete the following verifications:
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| ALL CEAs are above long term steady state insertion limits Power Ratio Recorder is correctly adjusted Thermal Power is NOT greater than the maximum allowed power Initials Second Check Initials
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| Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
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| Initial Conditions:
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| : 1) Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.
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| : 2) CEAs are currently inserted to 108 inches on Group 5.
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| : 3) Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.l.A and 3.3.l.D have been entered.
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| : 4) The plant computer has "crashed" and is inoperable.
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| : 5) You are performing the duties of the CRO.
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| : 6) NI Readings are as follows:
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| Channel Lower Upper A 69.9 70.9 B 67.3 68.3 C 68.7 69.7 D 0 0 Initiating Cue:
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| AOP-7H, LOSS OF PLANT COMPUTER, has been implemented and the CRS directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per Section IV.E.
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| Are there any questions? You may begin.
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| J 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-Admin-3 I
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| Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: RO-Admin-3 Task Title: Verify CC system valve operability Task Number: 015.004 KiA
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| ==Reference:==
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| 2.2.21 (2.9,4.1)
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| Method of testing:
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| Simulated Perfonnance: D Actual Perfonnance: [8J Classroom: [8J Simulator: 0 Plant: 0 READ TO THE APPLICANT:
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| 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.
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| Initial Conditions:
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| : 1) Unit-l is at 100% power
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| : 2) Maintenance has just been completed with repacking 11 SDC HX CC DISCH valve 1 CC-3828-CV. The appropriate TS LCOs are in effect.
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| : 3) The valve has been stroked and the limit switches adjusted for PMT with all local observations by the Mechanics and 1M satisfactory.
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| : 4) The CV has been turned over to Operations for PMOT.
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| : 5) You are performing the duties of the CRO.
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| Initiating Cue:
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| The CRS has directed you to complete PMOT testing requirements for l-CC-3828-CV under Work Order C90811426. The CRS has also provided EN-4-108 Attachment (7) and STP-O-65G-l, Component Cooling Valve Quarterly Operability Test. Are there any questions? You may begin.
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| Task Standard:
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| This JPM is complete when the CRO has determined that the stroke times for l-CC-3828 CV are outside of the allowable PMOT deviation, are repeatable, and must be evaluated by the 1ST Engineer prior to declaring the CV operable. No further actions are required.
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| Evaluation Criteria:
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| : 1. All critical steps completed (denoted by shading).
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| : 2. All sequential steps completed in order.
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| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
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| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
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| Required Materials:
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| : 1. Procedures and manuals normally available in the plant General
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| ==References:==
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| : 1. STP-O-65G-I, Component Cooling Valve Quarterly Operability Test
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| : 2. EN-4-108, ASME In-service Testing of Power Operated Valves and Manual Valves Time Critical Task:
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| No Validation Time:
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| 20 minutes Simulator Setup:
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| : a. None
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| ELEMENT STANDARD
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| (* = CRITICAL STEP)
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| Time Start:
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| CUE: Provide the candidate EN-4-108 Attachment (7) and STP-O-65G-l o Locates EN-4-1 08 Attachment (7) Same as element.
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| Determines that maintenance performed could affect the stroke time and that Section 1 and Section 2 o Reviews PMOT Test Requirements must be completed and SectIon 3 may need to be completed based on PMOT stroke results.
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| CUE: Local observations were completed during PMT by both the Mechanics and 1M, with satisfactory results.
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| This section may not be referenced if o Reviews Local/Remote Observations to Assess Valve candidate determines observations Performance/Condition During Stroke-Time Baseline were performed by Mechanical and Tests 1M during PMT. If section is referenced, same as element.
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| Section 1.0 Determine Allowable PMOT Deviation Uses STP 0-65G-I Section 6.3 to determine RV OPEN=23.8 sees, and calculates:
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| PMOT Deviation OPEN= sees OR +/-2.4 sees (depending on how value was truncated Uses STP 0-65G-l to determine RV o PMOT Deviation CLOSED CLOSED=N/A and calculates:
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| PMOT Deviation CLOSED=N/A Uses STP 0-65G-l Section 6.3 to determine LVFST OPEN=35.7 sees and completes OPEN Acceptance Criteria table using a combination of STP 0-65G-l values and calculations to determine:
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| * LVFSTmax=35.7
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| * PMOTmax=26.1 OR 26.2 sees
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| * RV=23.8 secs
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| * PMOTmin=21.5 OR 21.4 sees
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| * LVFSTmin=N/A
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| Uses STP 0-65G-l Section 6.3 t 0 determine RV LVFST CLOSED=N/A, and calculates completes CLOSED Acceptance I Criteria table using a combinatio nof o CLOSED Stroke PMOT Deviation Table , STP 0-65G-l values and calculations to determine:
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| * LVFSTmax=N/A
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| * PMOTmax=N/A
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| * RV=N/A
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| * PMOTmin= NIA
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| * LVFSTmin=N/A
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| ! CUE: When candidate requests l-CC-3828-CV stroke times or is referring to STP 0-65G-l to perform the valve strokes, provide the following information: Valve opened in 26.4 se cs, closed in 26.3 sees, and all local observations and indications were satisfactory.
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| I Section 2.0 Validate Existing Reference Valu_e_ _ _--.-_ i o Record PMOT Stroke Time (both directions Records OPEN stroke as 26.4 sec s I
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| required) and CLOSED stroke as 26.3 secs Determines stroke time did not fa11 o Did each PMOTstroke,tinre fall within theaUowable PMOW~d "',c,. ,
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| within the PMOT deviation. Circ les
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| , ' M N for Open Stroke and NIA for Closed Stroke Determines stroke time did not fa11
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| , I:]IfthtrPMQ1.~tro~etimesCs) fall within the P¥ctT: within the PMOT deviation.
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| I~~;yiatio~~en:m' c,_~-,,-,-_**'-'----<-"- - '- - ''-'-:-"-"-'----'-_~_:_~:_ir:_n_i_~~_~_~_t~_~_t_i~_~_~_~_e_a~_~_rt_~_~_ed
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| , Section 3.0 Baseline Stroke-Time Tests o Perform at least three baseline stroke tests in each Determines that at least 3 more direction (in addition to the PMOT strokes), I strokes in each direction are required regardless of the valves safety function(s) ....
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| CUE: When candidate requests l-CC-3828-CV stroke times or is referring to STP 0-65G-l to perform the additional valve strokes, provide the following information: First Baseline
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| ! Stroke-Valve opened in 26.5 sees, and valve closed in 26.2 sees. All local observations and indications were satisfactory.
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| f - - - - - - - - - - - - - - - - - - - - - - - - , - - -....- - - - - - - -
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| Records:
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| 'I' I:] Baseline Stroke #. . . _1_ _ _ _ _ _ _ _ _ _ _---.J~ Open=26.5,
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| ____ Closed=26.2
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| _ _ _._ __
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| I I CUE: When candidate requests l-CC-3828-CV stroke times or is referring to STP 0-65G-l to perform the additional valve strokes, provide the following information: Second Baseline!
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| Stroke-Valve opened in 26.3 sees, and valve closed in 26.3 sees. All local observations and indications were satisfactory.
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| Records:
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| , D Baseline Stroke #2 Open=26.3, Closed=26.3
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| CUE: When candidate requests l-CC-3828-CV stroke times or is referring to STP 0-65G-l I to perform the additional valve strokes, provide the following information: Third Baseline
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| . Stroke-Valve opened in 26.3 sees, and valve closed in 26.3 sees. All local observations and indications were satisfactory.
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| Records:
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| I 0 Baseline Stroke #3 Open=26.3, Closed=26.3 CUE: Only if an additional stroke was performed, when candidate requests l-CC-3828-CV stroke times or is referring to STP 0-65G-l to perform the additional valve strokes, i provide the following information: Additional Baseline Stroke-Valve opened in 26.4 sees, i and valve closed in 26.3 sees. All local observations and indications were satisfactory.
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| If performed, records:
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| I0 Additional Strokes Open=26.4, Closed=26.2 Regardless of number of strokes, o Baseline Stroke Time Average records:
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| Open=26.4, Closed=26.3 Determines that both OPEN and o . CLOSED strokes are repeatable and circles Y for both OPEN and CLOSED References Section 2.0 or STP 0 65G-I Section 6.3 and determines OAr~:anstr6k~ftimes,~tHfnthe*.litfil!~t~tftblished that only the LVFST in the OPEN the L VFST valJ~s?t:/~, . . direction applies and that the valve strokes were within the LVFST
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| ! values. Circles Y for OPEN and NIA for CLOSED i 0 Observations!Assessment (include any new May note that conditions locally Condition Reports) were sat CUE: If candidate does not indicate that valve is still inoperable, ask "Can l-CC-3828-CV now be declared operable?"
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| 0/id i 0 Jjete~es tl#1f 1ST En eetmllSt~view ;. Same as element I Attac~ent(7) results fore decliningCV..()p_e=ra~b_le,-,-
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| . ~ --'--_ _ _ _ _ _ _ _ _ _ _ _----'
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| Terminating Cue: This lPM is complete when it is determined that the 1ST Engineer must evaluate the PMOT results in order to declare l-CC-3828-CV operable. No further actions are required. The evaluator is expected to end the lPM.
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| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: RO-Admin-3 Applicant:
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| NRC Examiner:
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| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UNSAT Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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| | |
| EN-4-108 ASME Inservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 83 of 86 Attachment 7, Evaluation/Documentation of Stroke-Time Test Results During PMOT (Page 1 of 4)
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| PMOT Test Requirements When maintenance is performed on power-operated valves that could affect the stroke-time, must be completed as follows:
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| * Complete Section 1, Determine Allowable PMOT Deviation.
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| * Complete Section 2, Validate Existing Reference Value.
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| o If the stroke-time is within the deviation determined in Section 1, no abnormal valve operation was observed, and the maintenance was NOT intended to change the valve stroke time (e.g. replacing solenoid valve with one having a different venting capacity),
| |
| no further testing or evaluation is required and the valve may be declared operable.
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| NOTE Performance of Section 3 requires that the 1ST Engineer evaluate the stroke time tests PRIOR to declaring the valve operable.
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| * Complete Section 3, Baseline Stroke-Time Tests for the following conditions:
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| o Section 2 stroke time was outside of the allowable deviation determined in Section 1.
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| o The maintenance was intended to change the valve stroke time (i.e. modification)
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| Local/Remote Observations to Assess Valve Performance/Condition Durinq Stroke-Time Baseline Tests Observe the performance/condition of the valve, actuator, and associated subcomponents/support systems locally (if accessible) and remotely during at least one of the PMT/Baseline strokes. Look for typical symptoms of improper operation or degradation. If none are noted, the possibility that the maintenance may have created any new issues, or that there was any previously unidentified degradation, is reduced. Ensure components that were disturbed by the maintenance are specifically assessed, but do not focus exclusively on only those components:
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| : a. Verify the valve strokes smoothly with no binding or scoring on stem. Document any flow noises heard.
| |
| : b. Verify the actuator operates smoothly with no air leaks or binding.
| |
| : c. Verify limit switches function properly and appear to be properly set and secure.
| |
| : d. Verify the air system solenoid valve, the pressure regulator, and other SUbcomponents appear to operate properly with no air leaks. Verify the air pressure regulator appears to be set and operating properly.
| |
| : e. Verify the control system appears to be set up and working properly.
| |
| : f. Verify the stroke times collected are repeatable, random (Le. not aU rapidly increasing or decreasing), and appear to be representative of valve performance.
| |
| | |
| EN-4-108 ASME Inservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 84 of 86 Attachment 7, Evaluation/Documentation of Stroke-Time Test Results During PMOT (Page 2 of 4)
| |
| Valve: _ _ _ __ STP: Maintenance Order(s): _ _ _ _ _ __
| |
| -----
| |
| 1.0 Determine Allowable PMOT Deviation Enter Reference Value(s) from associated STP for valve being tested in spaces below.
| |
| Calculate PMOT Deviation as follows:
| |
| For Reference Values (RV) S 10 seconds: PMOT Deviation 1 second =
| |
| For Reference Values (RV) > 10 seconds: PMOT Deviation = 0.1 X RV = second PMOT Deviation OPEN = 0.1 X - - - - =+/ _ _ seconds (N/A if no OPEN Reference Value) RV PMOT Deviation CLOSED = 0.1 X
| |
| - - - - =+1- - - - seconds (N/A if no CLOSED Reference Value) RV Enter PMOT Max and PMOT Min Deviations in spaces below.
| |
| Enter LVFST(s) from associated STP for valve being tested in spaces below.
| |
| OPEN Stroke (seconds) CLOSED Stroke (seconds)
| |
| (N/A if OPEN Reference Value not (N/A if CLOSED Reference Value not assigned) assigned)
| |
| LVFST = LVFST =
| |
| PMOT Max = RV + PMOT Dev. PMOT = RV + PMOT Dev.
| |
| RV = RV =
| |
| PMOT Min = RV - PMOT Dev. PMOT Min = RV - PMOT Dev.
| |
| ---
| |
| LVFST Min = LVFST =
| |
| (N/A if not assigned) (N/A if not assigned) 2.0 Validate Existing Reference Value Record PMOT Stroke Time (both directions required)
| |
| OPEN stroke CLOSED stroke Did each PMOT stroke time fall within the allowable PMOT deviation?
| |
| OPEN stroke: Y N N/A (Circle one)
| |
| CLOSED stroke: Y N N/A (Circle one)
| |
| If the PMOT stroke time(s) fall within the PMOT Deviation, then
| |
| * The Reference Value has been reconfirmed.
| |
| * If no other immediate operability concerns were identified, then the PMOT is satisfactory and the valve may be returned to an Operable status.
| |
| Performed By: _ _ _ _ _ _ _ __ Date: _ _ _ __
| |
| Approved By: _ _ _ _ _ _ _ __ Date: _ _ _ __
| |
| | |
| EN-4-108 ASME Inservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 85 of 86 Attachment 7, Evaluation/Documentation of Stroke-Time Test Results During PMOT (Page 3 of 4) 3.0 Baseline Stroke-Time Tests NOTE Performance of this Section requires that the 1ST Engineer evaluate the stroke time tests PRIOR to declaring the valve operable.
| |
| PERFORM at least three baseline stroke tests in each direction (in addition to the PMOT strokes), regardless of the valve's safety function(s). Allow the valve/actuator to reach equilibrium conditions between each stroke/direction and RECORD the times below.
| |
| Open Strokes (sec) Closed Strokes (sec)
| |
| Baseline Stroke #1 (required)
| |
| Baseline Stroke #2 (required)
| |
| Baseline Stroke #3 (required)
| |
| Additional Strokes (optional)
| |
| Baseline Stroke Time Average (sec)
| |
| Repeatabilitv A minimum of three stroke times in both directions is required. The stroke times should be reasonably repeatable and deviations should appear to be random. If they do not, then additional stroke-time data should be collected and documented. A good rule of thumb to assess stroke time repeatability for most valves is that each stroke time should be within approximately .:t,1 0% or .:t, 1 second, whichever is greater, of the average of the stroke times.
| |
| Are the stroke times in each direction adequately repeatable?
| |
| OPEN stroke: Y N (Circle one)
| |
| CLOSED stroke: Y N (Circle one)
| |
| Are all stroke times within the limits established by the LVFST value(s)?
| |
| OPEN stroke: Y N N/A (Circle one)
| |
| CLOSED stroke: Y N N/A (Circle one)
| |
| Observations/Assessment (include any new Condition Reports):
| |
| Performed By: _ _ _ _ _ _ _ __ Date: _ _ _ __
| |
| Approved By: _ _ _ _ _ _ _ __ Date: _ _ _ __
| |
| Notification and Disposition
| |
| * Notify the 1ST Program implementerlDesignee that a Post-Performance Evaluation is required prior to restoring the valve to service.
| |
| * Attach the completed form to the STP used for PMOT.
| |
| Performed By: _ _ _ _ _ _ _ __ Date: _ _ _ __
| |
| Reviewed By (CRS): Date: _ _ _ __
| |
| | |
| EN-4-108 ASME Inservice Testing of Power-Operated Valves & Manual Valves Revision 00300 Page 86 of 86 Attachment 7, EvaluationIDocumentation of Stroke-Time Test Results During PMOT (Page 4 of4) 4.0 1ST Proqram Requirements:
| |
| The 1ST Program Implementer/Designee is required to perform a Post-Performance Evaluation of this attachment. The evaluation will be done either in support of an impending reference value re-baseline prior to declaring the power-operated valve operable or as a subsequent task following reconfirmation of an existing reference value.
| |
| 5.0 Post-Performance Evaluation:
| |
| Date:
| |
| 1ST Engineer
| |
| * Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1) Unit-l is at 100% power
| |
| : 2) Maintenance has just been completed with repacking 11 SDC HX CC DISCH valve l-CC-3828-CV. The appropriate TS LCOs are in effect.
| |
| : 3) The valve has been stroked and the limit switches adjusted for PMT with all local observations by the Mechanics and 1M satisfactory.
| |
| : 4) The CV has been turned over to Operations for PMOT.
| |
| : 5) You are performing the duties of the CRO.
| |
| Initiating Cue:
| |
| The CRS has directed you to complete PMOT testing requirements for l-CC-3828 CV under Work Order C90811426. The CRS has also provided EN-4-108 Attachment (7) and STP-O-65G-l, Component Cooling Valve Quarterly Operability Test. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-Admin-4
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-Admin-4 Task Title: Recall Emergency Response Organization Task Number: 204.138 KJ A
| |
| | |
| ==Reference:==
| |
| 2.4.39 (3.9,3.8)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: ~
| |
| Classroom: 0 Simulator: ~ Plant: 0 READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit-2 tripped from 100% power
| |
| : 2. EOP-S, Loss of Coolant Accident, has been implemented
| |
| : 3. The SM has declared an Alert Condition on Unit 2.
| |
| : 4. You are performing the duties of an extra licensed operator.
| |
| Initiating Cue:
| |
| You are directed to recall the Emergency Response Organization according to Step B.l of 1. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when the candidate has completed the recall of the Emergency Response Organization per ATTACHMENT 11 ofERPIP 3.0.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant
| |
| : 2. Completed ERPIP 3.0 Attachment 3
| |
| : 3. ERPIP 3.0, Attachment 11, pages 2 and 3.
| |
| General
| |
| | |
| ==References:==
| |
| : 1. ERPIP 3.0, Immediate Actions
| |
| : 2. ERPIP 105, Control Room Communicator, Attachment 1 Time critical task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. Simulator not required, however, access to a PC is required
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start: - - -
| |
| CUE: Provide Candidate with completed ATTACHMENT 3, Initial Notification Form and copy of ATTACHMENT 11, Step B.l.
| |
| Cl Locates ERPIP 3.0 Attachment 11, Alert Actions, Step B.1 OR Same as element Locates ERPIP 105 Attachment 1, Personnel Notification, Step 1 Cl a. HAVE the Initial Notification Form immediately available for reference.
| |
| Cl b.;,ACCESS a~'Comp!Ite~ with Internet capability Same as element Cl 1. IF at any time the Internet cannot be accessed, THEN IMMEDIATELY GO TO step B.2 of this Determines step is NIA attachment.
| |
| Same as element CAUTION Username, CCNPP Trainer, and password, Train6 A now, MUST be entered as specified.
| |
| Failure to do so may result in activation of the Emergency Response Organization NOTE The user name and password are case sensitive Same as element Same as element Same as element Same as element
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Determines Drill is correct event CI 2. SELECT the "Unit" indicated on the Initial Determines Calvert Cliffs is Notification Form (Section B) applicable Unit Determines Alert is applicable Reason for Notification Determines Staff Normal Emergency Facilities for Emergency is correct Action CI 5. VERIFY that the message in the "Message Text" box is correct. Same as element CI 6. UTILIZE the "Back" button as required to correct errors NOTE The selection under "Polling Options" and "Security Options" are pre-populated and should not be altered.
| |
| Same as element CAUTION Failure to select "Simulator Test" may result in activation of the Emergency Response Organization Same as element Same as element
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP) 1:1 1. RECORD the time sent from the Track Delivery Summary page: (Time) Same as element D 1. CHECK Status is "Delivery in Progress" from the Track Delivery Summary page. Same as element 1:1 m. IF the Status is not "Delivery in Progress",
| |
| THEN GO TO Step B.2.
| |
| D n. INFORM Security (4695) that ERONS has been Same as element activated .
| |
| .-- .. ---------------------------------------------------------------~
| |
| Terminating Cue: This JPM is complete when the Candidate has informed Security that ERONS has been activated to recall the Emergency Response Organization.
| |
| | |
| Verification of Completion Job Performance Measure Number: RO-ADMIN-4 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator: --_ _ - - - - - - - - - - -
| |
| ..
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _
| |
| Result: SAT ________ UNSAT _ _ _ _ _ __
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| IMMEDIATE ACTIONS ERPIP*3.0 Revision 04600 Page 15 of 143 Page 1 of 2 ATTACHMENT 3, INITIAL NOTIFICATION FORM USE THIS FORM FOR INITIAL NOTIFICATION AND EMERGENCY CLASS UPGRADING AND DOWNGRADING ONLY
| |
| : 2. Facility: Calvert Cliffs Nuclear Power Plant Unit 0 1 2 0 Common/BothllSFSI
| |
| : 3. Emergency Class: 0 Unusual Event t:! Alert 0 Site Area Emergency 0 General Emergency o None (downgraded)
| |
| : 4. EAL Number: ~ ~ _t_ or 0 None (downgraded)
| |
| : 5. Radioactivity is/was released to the environment due to the event: 'SI Yes 0 No
| |
| : a. Radioactivity released is/was monitored: 0 N/A 1&1 Yes 0 No
| |
| : b. Type of Release: 0 N/A .E Airborne 0 Liquid
| |
| : 6. Protective Action Recommendation (Must choose one from b through f for General Emergency)
| |
| : a. None (for downgrade, unusual event, alert or site area emergency only)
| |
| : b. Shelter entire 10 mile EPZ
| |
| : c. Evacuate PAZ 1 unless conditions make evacuation dangerous, notify the public in PAZ 1 to take KI, shelter remainder of the 10 mile EPZ, Evacuate PAZ 1 & 2 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 2 to take KI, shelter remainder of the 10 mile EPZ.
| |
| Evacuate PAZ 1 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 3 to take KI, shelter remainder ofthe 10 mile EPZ, Evacuate PAZ 1, 2 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1, 2 & 3 to take KI, shelter remainder of the 10 mile EPZ.
| |
| ACTION o Unusual Event
| |
| ]&I Alert UNIT o Site Area Emergency o Staff Alternate Emergency Facilities
| |
| {gJ Calvert Cliffs o General Emergency o Staff Normal Emergency Facilities as a Precaution o Event Termination o Staff EOF and .IIC Only o Staff TSC and OSC Only o Staff EOF with ED and RAD Only ED Name (print)_---=-E_,...;;\)_\1Z.EC:.;;...;..._l1....;O_(2~_ _ __ Signature:_-"...:.!.~~~J!.!.._ _ _ _ _ _ __
| |
| | |
| IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 37 of 143 ATTACHMENT 11, ALERT ACTIONS (CONTINTJED)
| |
| B.l. ACTIVATE the Emergency Response Organization Notification System (ERONS).
| |
| : a. HAVE the Initial Notification Form immediately available for reference.
| |
| : b. ACCESS a computer with Internet capability.
| |
| : 1. IF at any time the Internet cannot be accessed, THEN IMMEDIATELY GO TO step B.2 of this attachment.
| |
| : c. CLICK the Internet Explorer icon AND TYPE the following into the address bar: http://www.envoyprofiles.comlce/.
| |
| NOTE The user name and password are case sensitive.
| |
| : d. WHEN the NotiFind log in page appears, THEN ENTER:
| |
| Username: CCNPP Trainer Password: Train61\now Hit "Login"
| |
| : e. ON the "Welcome to NotiFind" screen, THEN CLICK on "Activation".
| |
| : f. ON the "NotiFind Main Menu" screen, THEN CLICK on "Activate System".
| |
| : g. ON the "Create Notification/Select Notification Type" screen, THEN SELECT "ERO Notification System" AND CLICK on "Next".
| |
| : h. ON the Create Notification/Notification Details screen, THEN:
| |
| : 1. SELECT the "Event" indicated on the Initial Notification Form (Section B)
| |
| : 2. SELECT the "Unit" indicated on the Initial Notification Form (Section B)
| |
| : 3. SELECT "Reason for Notification" indicated on the Initial Notification Form (Section B)
| |
| : 4. SELECT ERO personnel "Action" indicated on the Initial Notification Form (Section B)
| |
| : 5. VERIFY that the message in the "Message Text" box is correct.
| |
| : 6. UTILIZE the "Back" button as required to correct errors NOTE The selection under "Polling Options" and "Security Options" are pre-populated and should not be altered.
| |
| | |
| IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 38 of 143 Page 3 of5 ATTACHMENT 11, ALERT ACTIONS (CONTINUED)
| |
| : i. UNDER "Sender Information", THEN ENTER the following:
| |
| Name: leave blank Caller ID: 410-495-4444 Email: CCNPP_EP@constellation.com Click on the "Next" button
| |
| : j. ON the "Create NotificationINotification Lists" screen, THEN CHECK the box next to the "Simulator Test" AND CLICK on the "Next" button.
| |
| : k. ON the "Create NotificationINotification Verify and Send" Screen, THEN VERIFY information is accurate AND CLICK on the "SEND" button.
| |
| : 1. RECORD the time sent from the Track Delivery Summary page:
| |
| _ _ _ _ _ _ _ (Time)
| |
| : 1. CHECK Status is "Delivery in Progress" from the Track Delivery Summary page.
| |
| : m. IF the Status is not "Delivery in Progress", THEN GO TO Step 8.2.
| |
| : n. INFORM Security (4695) that ERONS has been activated.
| |
| NOTE The following actions are steps which activate ERONS if the Internet is non-functional.
| |
| This method does NOT have all the selection features as the Internet-based ERONS.
| |
| B.2. IF the internet is non-functional, THEN ACTIVATE the Backup Process for ERONS:
| |
| : a. USING the initial notification form, THEN NOTIFY the ERO AND DETERMINE which of the following actions should be performed:
| |
| : 1. NOTIFY the ERO of an emergency and direct them to staff the normal emergency facilities.
| |
| : 2. NOTIFY the ERO of an emergency and direct them to staff the alternate emergency facilities.
| |
| : b. DIAL the following number on ANY working telephone: 8-1-800-735-0318
| |
| : 1. WHEN prompted, THEN PRESS "2" for Scenario Activation Line.
| |
| : 2. WHEN prompted, THEN ENTER the Account Number for Calvert- 4955201#.
| |
| : 3. WHEN prompted, THEN ENTER the PIN number as follows:
| |
| 00000#.
| |
| | |
| IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 39 of 143 Page 4 of5 ATTACHMENT 11, ALERT ACTIONS (CONTINUED)
| |
| : 4. WHEN prompted, THEN ENTER the access code as follows:
| |
| (a) To direct the ERO to staff normal emergency facilities, enter access code: 5555#
| |
| (b) To direct the ERO to staff alternate emergency facilities, enter access code: 6666#
| |
| (c) To notify ERO of an emergency, but no response is required, enter access code: 7777#
| |
| : c. WHEN ERONS reads the "Subject" line of the message, THEN PRESS "I" to accept the message.
| |
| : d. WHEN prompted, THEN PRESS "1" to send the message
| |
| : e. RECORD the time that you completed step B.2.d. above _ _ _ _ (TIME).
| |
| : f. INFORM Security (4695) that ERONS has been activated.
| |
| C.l. NOTIFY Offsite Agency (Within 15 minutes).
| |
| : a. USING the dedicated phone, DEPRESS the "OFFSITE CONFERENCE" button to simultaneously call the 5 Agencies.
| |
| : 1. IF not working, THEN USE BfU OFFSITE CONFERENCE button.
| |
| (REFER to ERPIP 105 if further issues occur with agency contact.)
| |
| I~- NOTE:
| |
| ~g off hours MDE is not staffed. No answer from them is satisfactory.
| |
| : b. AS each agency answers, THEN SAY" This is Calvert Cliffs. Standby for an emergency message. Please report your agency and your name."
| |
| : c. RECORD time, name, and method of contact in Contact Table below.
| |
| : d. AFTER all agencies are on line, THEN SAY " Please get an Initial Notification Form."
| |
| : e. WHEN all agencies have the form OR 1 minute has elapsed, THEN SAY "I will give out the information on the form completely once". Page 4 of 5
| |
| : f. GIVE OUT the form information.
| |
| : g. ASK each agency if the full message was received. (REFER to ERPIP 105 if problems occur transmitting the form information.)
| |
| C.2. VERIFY the Control Room pager activation via ERONS. IF the pager in the Control Room does not receive the intended ERO notification within 5 minutes of the message being sent then repeat steps B.t or B.2 as appropriate
| |
| | |
| IMMEDIATE ACTIONS ERPIP-3.0 Revision 04600 Page 40 of 143 Page 5 of5 ATTACHMENT 11, ALERT ACTIONS (CONTINUED)
| |
| C.3 NOTIFY NRC (Within 1 Hour).
| |
| : a. USING the NRC Emergency Notification System (ENS) phone, DIAL the phone number listed on the label attached to the phone.
| |
| (1) IF there are any issues using the NRC Emergency Notification System (ENS) phone, THEN USE another phone.
| |
| : b. IDENTIFY yourself AND ASK for the name of who you are talking with.
| |
| : c. RECORD time, name and method of contact in Contact Table below.
| |
| : d. PROVIDE all form information AND VERIFY they received it.
| |
| : e. STAY on line with the NRC until released AND to respond to any inquiries.
| |
| CA. TRANSMIT completed Attachment 3, Initial Notification Form.
| |
| : a. SIGN Table below.
| |
| : b. FAX Attachment 3 form to the Plant Parameters Communicators for the TSC.
| |
| : c. FAX Attachment 3 form to EOF and JIC when manned.
| |
| : d. KEEP completed forms with communication records.
| |
| Contact Table Location *Time Received by: Method of Contact Calvert DP Rad OL St Mary's DP Rad OL Dorchester DP Rad OL MEMA DP Rad OL MDE DP Rad OL
| |
| . NRC DP OL DP = dedicated phone Rad = Radio OL outside line
| |
| *Record Time that all calls to the above agencies were completed.
| |
| Printed Name and Signature: _ _ _ __
| |
| | |
| APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. Unit -2 tripped from 100% power
| |
| : 2. EOP-5, Loss of Coolant Accident, has been implemented
| |
| : 3. The SM has declared an Alert Condition on Unit 2.
| |
| : 4. You are performing the duties of an extra licensed operator.
| |
| Initiating Cue:
| |
| You are directed to recall the Emergency Response Organization according to Step B.l of Attachment 11. Are there any questions? You may begin.
| |
| | |
| > - - - - - - - - - - - - -
| |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-Admin-1
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-Admin-l Task Title: Ability to implement plant procedures for a Condenser Tube Leak Task Number: 202.008 KJA
| |
| | |
| ==Reference:==
| |
| 2.1.34 (2.7,3.5)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: [g]
| |
| Classroom: [g] Simulator: D Plant:
| |
| READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1) Unit-l was in Mode-l at 100% power when AOP-IO was implemented for a Condenser Tube Leak. Power was reduced to 88% to remove 12A Waterbox from service
| |
| : 2) At 0015, 12A Waterbox was secured lAW AOP-I0, Abnormal Secondary Chemistry Conditions, due to a condenser tube leak.
| |
| : a. Condensate Demineralizers are in service with full flow
| |
| : b. Condenser High Level Dump is manually isolated
| |
| : c. S/G Blowdown flow has been maximized
| |
| : 3) At 0045, Chemistry notifies the Control Room exceeded Action Level 2 values for sodium in the Steam Generators, 52 ppb in 11 S/G & 55 ppb in 12 S/G.
| |
| : 4) At 1800, Chemistry notifies the Control Room we are still exceeding Action Level 2 values that sodium levels are lowering slowly. Chemistry anticipates exiting Action Level 2 at 0330
| |
| : 5) You are performing the duties of an extra SRO.
| |
| Initiating Cue:
| |
| The Shift Manager directs you to evaluate continued operation per AOP-IO, Section VI.
| |
| Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when it is determined a reactor trip is required. No further actions are required. The evaluator is expected to end the JPM.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-lO, Abnormal Secondary Chemistry Conditions.
| |
| : 2. CP-217, Specifications and Surveillance - Secondary Chemistry Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| - - a. None
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| CUE: The Shift Manager directs you to evaluate continued operation per AOP-IO, Section VI 0 Locates AOP-I 0, Section VI Same as element.
| |
| Reviews step and determines step is 0 A. Determine if a reactor trip is required. NIA at this time CUE: The CRS is directing the Crew in the performance of AOP-IO, Section VI.B Determines required actions are in 0 B. Determine required plant conditions. progress NOTE:
| |
| If SG chemistry levels are reduced below the Action Level 3 value, before or during the power reduction, power level is still required to be reduced below 5%.
| |
| C. Actions with power greater than or equal to 30%
| |
| ,
| |
| [J l.lF~~~t
| |
| ""',' """i'fj;"
| |
| Chemistry determines
| |
| ",,'''''' "',
| |
| SG Chemistry is
| |
| " " ' , , ' ",
| |
| in Action"Level 3, as aresultofaCondensefw.be Yi~'
| |
| leak, Determines step is NIA at this time THEN ~ommenceanord~r1y pfatit shutdown, tQ'be less tlj.atf5%powerasquickly ~'sare operatio; permits PER OP~3 and OP-4.
| |
| : 2. IF Plant Chemistry determines that SG Chemistry is in Action Level 2, as a result of a Condenser tube leak, THEN perform the following actions:
| |
| [J a. Witlilii24 hours of initiating Action, Level Determines power must be reduced 2, reduc~,povvef;to less than~O%,PER OP-3, to less than 30% by 0045 NORMAiL POWER'OPERATION.
| |
| 0 b. WHEN the following conditions exist:
| |
| * The source of the impurity ingress is controlled Determines step is NIA at this time
| |
| * SG Chemistry is less than the value for Action Level 2 THEN the power reduction may be terminated and power stabilized.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| D c. IF the SO chemistry level has NOT been reduced to less than Action Level 1 within 300 hours of entering Action Level 2 THEN consl.der the SO ChemlS . try IeveI t 0 bem .
| |
| Determines step is N/A at this time Action Level 3, AND commence an orderly plant shutdown to be less than 5% power as quickly as safe operation permits PER OP-3 and OP-4.
| |
| I CUE: 12A Waterbox is secured for leak location/repair Determines actions already in D 3. Attempt to locate and repair the tube leak. progress CUE: Chemistry reports SG sodium has exceeded Action Level 3 values Note to evaluator: Candidate will have to refer back to Step VI.C.1 D VLC.l. IF Plapt Chemistry determines SO Chernistry is in Action. Level 3, a§' altesult.'.of a Condenser tube leak, '~ Determines a plant shutdown to <5%
| |
| THENll()futfien~ ail orderly*:plant ~hutdownt(")be power is required.
| |
| less thanS%poweras quickly as safe operation permrts.;g~R OP-3 andPP':'4.
| |
| CUE: Chemistry reports Condensate and Feedwater Sodium levels are 210 ppb and rising rapidly. The source appears to be 138 Waterbox.
| |
| D VLA. Determine if a reactor trip is required.
| |
| '. .... ......... 1",%,; "i, d::l .. IF Feeo.
| |
| .
| |
| r sodiurn~fs&I:f!at<rrth:f:Ill200 pp6 ..
| |
| ANDeQn ~'Sodium isgreater.tlla:n200 ppb, THENpeiform"ilie folloWing: Determines reactor trip is required a.~Tril'f .the R~~~to~. ) J'~:.
| |
| Terminating Cue: This JPM is complete when it is determined a reactor trip is required. No further actions are required. The evaluator is expected to end the JPM.
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SRO-Admin-l Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT UNSAT _ _ _ _ _ __
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1) Unit-l is in Mode-l at 88% power.
| |
| : 2) At 0015, 12A Waterbox was secured lAW AOP-I0, Abnormal Secondary Chemistry Conditions, due to a condenser tube leak.
| |
| : a. Condensate Demineralizers are in service with full flow
| |
| : b. Condenser High Level Dump is manually isolated
| |
| : c. SIG Blowdown flow has been maximized
| |
| : 3) At 0045, exceeded Action Level 2 values for sodium in the Steam Generators, 52 ppb in 11 SIG and 55 ppb in 12 S/G.
| |
| : 4) At 1800, Chemistry notifies the Control Room we are still exceeding Action Level 2 values and sodium levels are lowering slowly. Chemistry anticipates exiting Action Level 2 at 0330
| |
| : 5) You are performing the duties of an extra SRO.
| |
| Initiating Cue:
| |
| The Shift Manager directs you to evaluate continued operation per AOP-lO step VI.
| |
| Are there any questions? You may begin.
| |
| | |
| .. .!.-,---'- --~--------------,
| |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-Admin-2
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-Admin-2 Task Title: Verify an Estimated Critical Condition Calculation Task Number: 202.247 KIA
| |
| | |
| ==Reference:==
| |
| 2.1.25 (3.9, 4.2)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: [8J Classroom: [8J Simulator: D Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit-2 is in MODE 3 at normal operating temperature and pressure. Current time is 0800.
| |
| : 2. The reactor tripped while performing RPS testing 32 hours ago. Preparations are underway for a quick trip recovery startup to begin within the next 30 minutes with criticality anticipated in 2 hours at lOam.
| |
| : 3. The following conditions exist:
| |
| : a. Unit-2 tripped from 100% power 32 hours ago.
| |
| : b. Power history: Prior to the trip, Unit-2 operated at 100% for the previous 68 days.
| |
| : c. Burnup from the plant computer point "CEBURNUP" is 14,400 MWDIMTU.
| |
| : d. Nuclear Fuels has provided a Xenon Worth Calculation and a B-10 Correction factor of 0.971.
| |
| : 4. An ECC has been prepared by an extra licensed operator.
| |
| Initiating Cue:
| |
| The Shift Manager has directed you to Verify the Estimated Critical Concentration calculation per NEOP-302, Estimated Critical Condition, Step 6.1.23. Do not verify the
| |
| +/-lhr or the +/-2hr values. Do not verify the ECC tolerance band values. Are there any questions? You may begin.
| |
| Task Standard:
| |
| Verify an Estimated Critical Condition Calculation.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| | |
| NEOP302, Estimated Critical Condition NEOP-23, Technical Data Book (Unit-2)
| |
| Time critical task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. None required
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| 0 Locates NEOP-302, Step 6.1.23 Same as element 0 6.1.23. The Shift SRO shall perform the following:
| |
| 0 6.1.23.1. Verify the previous critical condition is Same as element correct 0 6.1.23.2. Verify that criticality is expected within the +/-2 hour window bounded by the time points Same as element 2h and+/-2h.
| |
| 0 6.1.23.3 Independently verify the ECC is calculated correctly Note to Evaluator: Candidate will complete independent verification of the calculation using NEOP-302, Section 6.1 0 6.1.1 Complete the previous critical conditions section of Attachment 2, Four Hour Window With Same Boron:
| |
| 0 6.1.1. Verify correct Unit and cycle numbers Same as element 0 6.1.2. Verify correct date and time the unit shut Same as element down CUE: Burnup from the plant computer point "CEBURNUP" is 14,400 MWDIMTU Determines correct Bumup is 14,400 0 6.1.3. Verify correct burnup, for the cycle, has MWD/MTU. Verifies correctly been recorded entered on Attachment 2 0 6.1.2 Complete the "Current Conditions" section of Attachment 2:
| |
| CUE: Candidate will reference 0 6.1.2.1. Verify correct value for Excess Determines correct value for Excess Reactivity has been determined and entered on Reactivity is 9.9375 %~p. Verifies Attachment 2. correctly entered on Attachment 2.
| |
| 0 6.1.2.2. Verify correct HZP Inverse Boron Worth Determines correct value for HZP (IBW) has been determined and entered on IBW is 116.2 ppm/%~p. Verifies Attachment 2. correctly entered on Attachment 2.
| |
| 0 6.1.2.3. Verify correct B-I0 Correction Factor Verifies B-1 0 Correction Factor has has been determined and entered on Attachment been entered as .971 on Att 2 2.
| |
| 0 6.1.3 Verify correct estimated date and time of Verifies correct estimated date and reactor criticality entered on Attachment 2 for the time of reactor criticality entered on time point "Oh" Attachment 2 for the time point "Oh"
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP) o 6.1.4 Verify correct elapsed time from reactor Verifies correct elapsed time from shutdown to the estimated time of criticality, as reactor shutdown to the estimated "Hours After Shutdown", is entered on Attachment 2 time of criticality, as "Hours After Shutdown", is entered on Attachment for time point "Oh".
| |
| 2 for time point "Oh".
| |
| o 6.1.5 Verify correct shutdown xenon worth, at the Determines correct xenon worth is estimated time of criticality, is entered on 1.120 %i1p. Verifies correctly Attachment 2. entered on Attachment 2 Note to Evaluator: Steps 6.1.6 and 6.1.7 are not performed during verification Determines correct CEA heights are:
| |
| * Group 3 @ 135 inches o 6.1.8 Verify correct CEA position for criticality is
| |
| * Group 4 @ 90" determined and entered on Attachment 2.
| |
| * Group 5 @ 0" Verifies correctly entered on Attachment 2 o 6.1.9 Verify correct CEA reactivity worth has been Determines correct CEA worth is
| |
| .6808 %i1p. Verifies correctly determined and entered on Attachment 2.
| |
| entered on Attachment 2 Determines a math error exists in the calculation (HZP IBW multiplied by B-I0 Correction Factor. HZP IBW should be divided by the B-1 0 Correction Factor). Determines Correct value for Corrected HZP IBW = 119.67 ppml%i1p Determine Boron Worth value of 8.1367 %i1p. Verifies correctly entered on Attachment 2 o 6.1.12 Verify timatedCritica1 Boron Determine Estimated Critical Boron Coucentratio n.tieietmincd and entered on Concentration value of 974 ppm.
| |
| Affttchment .
| |
| o 6.1.23. (continued) The Shift SRO shall perform the following:
| |
| CUE: Verification of the ECC Upper and Lower bounds are beyond the scope of this JPM o 6.1.23.4. Verify the ECC Upper and Lower bounds are calculated correctly and the established bounds are between 135 inches No actions are required withdrawn on Reg Group 5 and the Zero Power PDIL
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP) o 6.1.23.5. If an error is found, Then instruct the Returns ECC Calculation worksheet preparer to make the necessary corrections and repeat the review to the preparer for correction Terminating Cue: This JPM is complete when errors in the Estimated Critical Boron Concentration calculation have been identified & corrected and the Estimated Critical Boron Concentration has been correctly determined. No further actions are required.
| |
| I Time Stop: _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SRO-ADMIN-2 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator: --~---------------------
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _______________________________
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ ____ UNSAT _ _ _ _ _ ____
| |
| Examiner's Signature and Date:
| |
| | |
| XENON WORTH CALCULATOR Revision 3 Chan:.llOg~e_O~_ _ _ _ _ _ _ __
| |
| Unit 2 Cycle 18
| |
| =
| |
| Burnup 14,400 MWD/MTU Trip from Equilibrium at 99.5% Power At 07/09/201000:00 Calculation performed 0511312010 15:52 Hours After Trip (DatefTime) Xenon Worth o (07/09/201000:00) ----------- 2.531 %~p 1 (07/09/201001:00) -------- 2.904 %~p 2 (07/09/201002:00) ----------- 3.172 %~p 3 (07/09/201003:00) ---------- 3.372 %6p 4 (07/09/2010 04:00) --------- 3.513 %llp 5 (07/09/201005:00) -------- 3.604 %Ap 6 (07/09/2010 06:00) ------- 3.654 %Ap 7 (07/09/201007:00) ------ 3.668 %Ap 8 (07/09/201008:00) ------ 3.652 %&p 9 (07/09/201009:00) ----------- 3.612 %&p 10 (07/09/201010:00) -------- 3.552 %Ap 11 (07/09/201011:00) ------- 3.476 %~p 12 (07/09/201012:00) ---------- 3.386 %Ap 13 (07/09/201013:00) ------ 3.286 %Ap 14 (07/09/201014:00) ---------- 3.179 %Ap 15 (07109/201015:00) -------- 3.065 %Ap 16 (07/09/201016:00) ----------- 2.948 %Ap 17 (07/09/201017:00) ---------- 2.829 %Ap 18 (07/09/201018:00) ---------- 2.708 %Ap 19 (07/09/201019:00) ----------- 2.588 %Ap 20 (07109/201020:00) --------- 2.468 %Ap
| |
| | |
| XENON WORTH CALCULATOR Revision 3 Change 0 Hours After Trip (OatelTime) Xenon Worth 21 (07/09/201021 :00) ----------- 2.350 %6p 22 (07/09/201022:00) ------- 2.235 %6p 23 (07/09/2010 23:00) ------- 2.122 %6p 24 (07/10/201000:00) --------- 2.012 %6p 25 (07/101201001 :00) -------- 1.905 %6p 26 (07/10/201002:00) ------ 1.802 %6p 27 (07/10/201003:00) - - - - - 1.703 %6p 28 (07/10/201004:00) - - - - 1.608 %6p 29 (07/10/201005:00) ---------- 1.517 %6p 30 (07/10/201006:00) --------- 1.430 %i.lp 31 (07/10/201007:00) ------ 1.346 Q/oAp 32 (07/10/201008:00) ------- 1.267 %Ap 33 (07/10/201009:00) ---------- 1.192 %l\p 34 (07/10/201010:00) ----------- 1.120 %.Ap 35 (07/10/201011:00) ---------- 1.052 %l\p 36 (07/10/201012:00) --------- 0.987 %l\p 37 (07/101201013:00) --------- 0.926 %6p 38 (07/1012010 14:00) ----------- 0.868 %.Ap 39 (07/1012010 15:00) --------- 0.814 %.Ap 40 (07/10/2010 16:00) ----------- 0.762 %Ap 41 (07110/201017:00) --------- 0.714 %Llp 42 (07110/201018:00) ---------- 0.668 %Ap 43 (07/10/2010 19:00) ---------- 0.625 %Llp
| |
| %
| |
| 44 (07/10/201020:00) --------- 0.584 Llp 051131201015:52 Page 2 of4
| |
| | |
| XENON WORTH CALCULATOR Revision 3 Change 0 Hours After Trip (DatefTime) Xenon Worth 69 (07/11/201021:00) ------- 0.100 %tlp 70 (07/11/201022:00) ------- 0.093 %tlp 71 (07/11/201023:00) ------- 0.087 %tlp 72 (07/12/201000:00) ---------- 0.081 %.0.p 73 (07/12/201001:00) --------- 0.075 %.0.p 74 (07/12/201002:00) ------------ 0.070 %.0.p 75 (07/12/201003:00) ---------- 0.065 %.0.p 76 (07/12/201004:00) --------- 0.060 %.0.p 77 (07/12/201005:00) .-------- 0.056 %.0.p 78 (07/121201006:00) -----------. 0.052 %.n.p 79 (07/121201007:00) ---------- 0.048 %.n.p 80 (07/121201008:00) ------------ 0.045 %.n.p 81 (07/12/201009:00) ---------- 0.042 %.0.p 82 (07/12/201010:00) ---------- 0.039 %6p 83 (07/12/201011:00) ---------- 0.036 %Ap 84 (07/12/201012:00) ---------- 0.033 %Ap
| |
| ~----------------/~------
| |
| Prepared by Date
| |
| ~~--~--------~/~~----
| |
| Reviewed by Date
| |
| | |
| Units 1 & 2 r Estimated Critical Condition NEOP*302 Revision 0700 Page 27 of 33 Attachment 2, ECC - Four Hour Window With Same Boron #_---
| |
| Previous Critical Conditions
| |
| ,---~~~
| |
| - - --- - Current Conditions Excess Reactivity, %)A HZP IBW, (ppm/%)A B-I0 Correction Unit Cycle Date Time Burnup, MWDIMTU
| |
| -----
| |
| [A] [B] [C) 2 18 812/10 0000 14,400 9.9375 116.2 0.971 Estimated Critical Conditions
| |
| ------- ------- ----- ------- -------
| |
| Hours CEA Xenon Group Group Group Corrected Boron After Worth, Critical Boron Time Worth, 3, 4, 5, HZP IBW, Worth, Date Time Shutdown %)A Cone., ppm Point %)A inches inches inches ppm/%)A %)A
| |
| [E] (for Dh) or [H] = F*G
| |
| [D] [F] = B/C [G] A-(D+E)
| |
| -------
| |
| [E] A-(D+G) i
| |
| -2h 8/3/10 0800 32 1.267 135 104.25 14.25 .5410 112.83 8.1367 918
| |
| -lh 8/3/10 0900 33 1.192 135 97.5 7.5 .6160 112.83 8.1367 918 Oh 813/10 1000 34 1.120 135 90 0 .6808 112.83 8.1367 918
| |
| +lh 8/3/10 1100 35 1.052 135 78.75 0 .7560 112.83 8.1367 918
| |
| +2h 8/3/10 1200 36 0.987 135 67.5 0 .8210 112.83 8.1367 918 ECC Tolerance Band -----
| |
| Lower CEA Bound~C Worth + 0.5 %)A) Upper CEA Bound ECC Worth - 0.5 %)A)
| |
| Time Date Time Bounding Group 3, Group 4, GroupS, Bounding Group 3, Group 4, Group 5, Point Worth
| |
| ~-~
| |
| inches inches inches Worth inches inches inches
| |
| -2h 8/4/10 0800 1.0410 30 120 0 .0410 135 135 117.75
| |
| -lh 8/4/10 0900 1.1160 24.75 114.75 0 .1160 135 135 104.25 Oh 8/4/10 1000 U808 19.5 109.5 0 .1808 135 135 91.5
| |
| +lh 8/4/10 1100 1.2560 15 105 0 .2560 135 135 68.25
| |
| +2h 8/4/10 1200 1.3210 99.75 9.75 0 .3210 135 126 36 Excess Reactivity Source: NEOP*23, Figure 2-II.A.7 IBW Source: NEOP-23,Figure 2-U.A.2 B-IO Source: Isotopic sample analysis CEA Worth Source: NEOP-23, Figure 2-11.8.1 Prepared by: SRO Verification by: _ _ _ _ _ _ _---: _ _ __
| |
| Signature Date Signature Date
| |
| | |
| ...
| |
| Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. Unit-2 is in MODE 3 at normal operating temperature and pressure. Current time is 0800.
| |
| : 2. The reactor tripped while performing RPS testing 32 hours ago.
| |
| Preparations are underway for a quick trip recovery startup to begin within the next 30 minutes with criticality anticipated in 2 hours at lOam.
| |
| : 3. The following conditions exist:
| |
| : a. Unit-2 tripped from 100% power 32 hours ago.
| |
| : b. Power history: Prior to the trip, Unit-2 operated at 1000/0 for the previous 68 days.
| |
| : c. Burnup from the plant computer point "CEBURNUP" is 14,400 MWDIMTU.
| |
| : d. Nuclear Fuels has provided a Xenon Worth Calculation and a B-10 Correction factor of 0.971.
| |
| : 4. An ECC has been prepared by an extra licensed operator.
| |
| Initiating Cue:
| |
| The Shift Manager has directed you to Verify the Estimated Critical Concentration calculation per NEOP-302, Estimated Critical Condition, Step 6.1.23. Do not verify the +/-lhr or the +/-2hr values. Do not verify the ECC tolerance band values. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-Admin-3
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-Admin-3 Task Title: Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Instrumentation Task Number: 204.129 KIA
| |
| | |
| ==Reference:==
| |
| 2.2.42 (3.9, 4.6)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: [g]
| |
| Classroom: [g] Simulator: Plant: 0 READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.
| |
| : 2. CEAs are currently inserted to 108 inches on Group 5.
| |
| : 3. Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.1.A and 3.3.1.D have been entered.
| |
| : 4. The plant computer has "crashed" and is inoperable.
| |
| : 5. Last "good" values for F xyT and F rT were:
| |
| : a. F xyT = 1.72
| |
| : b. FrT 1.64
| |
| : 6. You are performing the duties of the STA.
| |
| : 7. NI Readings are as follows:
| |
| Channel Lower Upper
| |
| !
| |
| A 69.9 70.9 B I 67.3 68.3 i C 68.7 69.7 I D 0 0 i
| |
| Initiating Cue:
| |
| AOP-7H, LOSS OF PLANT COMPUTER, has been implemented and the Shift Manager directs you to determine the Azimuthal Power Tilt (Tq) using the excore Nls per Section IV.E. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when calculated azimuthal power tilt (Tq) is determined to be outside acceptable limits with T.S. component appropriately addressed. No further actions are required.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| | |
| I. AOP-7H, Loss of Plant Computer in Mode One or Two.
| |
| : 2. T.S. 3.2.4 Azimuthal Power Tilt Tq
| |
| : 3. Unit-I, Cycle 19, Core Operating Limits Report Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. None
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| I Time Start: ---_-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| * CUE: eRS directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per Section IV.E.
| |
| o Locates AOP-7H, Section IV.E. - IF Greater than Same as element.
| |
| 50% Rated Thermal Power, Monitor Tq.
| |
| 0 1. Calculate upper AND lower Tq using ANY of ro the following:
| |
| o IF ALL four Linear Power Channels are operable, Determines Step is N/A
| |
| * THEN perform EITHER of the following:
| |
| NOTE to Evaluator: If Opscalc is used then steps under a are critical, if Manual Calc is performed then step under b is critical.
| |
| CUE: Opscalc is available to use OR A total of 3tipper Lirte~,d~!yctors ~,~,.
| |
| reqwr~d to pe operCU/~,..t~ faileddetemo:rS
| |
| -f_'--;' t .:';' ,:j"f'5r:~ _Ie''',
| |
| can. bean c- --.
| |
| different channels.. Determines Step is applicable b *IFQhly 3Lin~~pq,w~r Channels at~i operab '., "*5~l:'.\ j.. ,..
| |
| AND ~::ifY' *.
| |
| ReactOt;PowerJs lissth~~15%,Tl!EN pe:r.fQl1l1 EITHj£Rof tlie following:
| |
| o a. Calculate Tq using Opscalc function Tq Calculator.
| |
| o R~cordi ings on ATTAC T (5),Tq Records NI values on Attachment 5 c;AL@3 'PION USINGEXCORE, DETECTORS Same as element.
| |
| Same as element.
| |
| | |
| ELEMENT STANDARD
| |
| (* - CRITICAL STEP) 2r.ttq Calculatipn~' from Same as element.
| |
| m~nti Enters data from Attachment 5.
| |
| Cl Enters data . and selects
| |
| - ~ \'
| |
| Calculates Upper Tq .03013 "CaI~ulat(!" .
| |
| Calculates Lower Tq .02970 CUE: Manual Calc is acceptable
| |
| -------------,---------------------j o b. Calculate Tq using the method in ATTACHMENT 5), Tq CALCULATION USING EXCORE DETECTORS Records Readings on Attachment 5 and performs calculations per formula on Attachment 5 Calculates Upper Tq .03013 Calculates Lower Tq .02970 OR o
| |
| * Notify the Reactor Engineering Work Determines Step is NIA Group to provide an alternate method to monitor Tq.
| |
| CUE:
| |
| o 2. Once every 12 hours, recalculate the Determines step is NIA at this time OR Azimuthal Power Tilt using the Excore Detectors Informs CRO to add note to Shift PER Step E.l, Page 11. Turnover o 3. IF Tq is greater than 0.03, THEN perform the Determines Tq is greater than 0.03 following actions:
| |
| NOTE The Reactor Engineering Work Group will determine what actions are necessary to correct Tq.
| |
| o a. Notify the Reactor Engineering Work Grou and GS-NPO of actual Tq.
| |
| | |
| NOTE If Tq is greater than 0.10, a two hour action applies.
| |
| Determines Tq is less than .10 0 *b. Enter the following Technical Specifications as applicable:
| |
| (J 3.22 Total Planar Radial Peaking Determines T.S. 3.2.2 limits have not Factor .;.Fxy T been exceeded per COLR Figure 3.2.2. Verifies CEAs are withdrawn to or above the Long Term Steady State Insertion Limits of Figure 3.1.6 0 323 Total.!htegrated Radial Determines T.S. 3.2.3 limits have not
| |
| ..Peaking.Factor- FrT been exceeded per COLR Figure 3.2.3 .
| |
| . :
| |
| CJ 3.2.4 AZimlithal Power Tilt - Tq Determines T.S. LCO 3.2.4.A is applicable 0 c. Record Fxy T and FrT on ATTACHMENT (3), VERIFICATION OF FxyT AND FrT.
| |
| Terminating Cue: This JPM is complete when calculated azimuthal power tilt (Tq) is determined to be outside acceptable limits with T.S. component appropriately addressed. No further actions are required.
| |
| I Time Stop:
| |
| | |
| **f*~~~-------------~------------------------'
| |
| Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: SRO-Admin-3 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _~._ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT UNSAT _ _ _ _ _ _ __
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.
| |
| : 2. CEAs are currently inserted to 108 inches on Group 5.
| |
| : 3. Channel "D" LRNI is out of service for maintenance. T.S. LCOs 3.3.1.A and 3.3.1.D have been entered.
| |
| : 4. The plant computer has "crashed" and is inoperable.
| |
| : 5. Last good values for F xyT and FrT :
| |
| : a. FxyT = 1.72
| |
| : b. FrT= 1.64
| |
| : 6. You are performing the duties of the STA.
| |
| : 7. NI Readings are as follows:
| |
| Channel Lower Upper A 69.9 70.9 B 67.3 68.3 C 68.7 69.7 D 0 0 Initiating Cue:
| |
| AOP-7H, LOSS OF PLANT COMPUTER, has been implemented and the Shift Manager directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per Section IV.E. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-Admin-4
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-Admin-4 Task Title: Approve a Liquid Waste Discharge Permit Task Number: 064.040 KJA
| |
| | |
| ==Reference:==
| |
| 2.3.6 (2.0, 3.8)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: ~
| |
| Classroom: ~ Simulator: D Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1) Unit-l is in Mode 3 with llA and 13B Waterboxes removed form service for cleaning
| |
| : 2) Unit-2 is at 88% power with 21A Waterbox removed from service for cleaning
| |
| : 3) 12 RCWMT discharge has been risk assessed and is on the schedule for today.
| |
| : 4) You are performing the duties of the CRS.
| |
| Initiating Cue:
| |
| The Shift Chemistry Technician has delivered a permit for the discharge of 12 RCWMT for your review and approval. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when the candidate rejects the permit because the required numbers of Circulating Water Pumps are not operating and RMS values are inconsistent. No further actions are required.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. CP-601, Liquid Radioactive Waste Release Permit Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. None
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| CUE: Provide the candidate the prepared copy of CP-601, Attachment 2 (12 RCWMT Discharge Permit)
| |
| D Release Criteria is understood: Same as element.
| |
| D Discharge Point Determines Unit 1 is checked.
| |
| D Min # Cire Water Pumps Required Determines 5 CW Pps are required Determines 1,000,000 GPM is D Dilution Flow Rate Pre-Release: consistent with 5 CW Pps running I
| |
| D Maximum Release Flow Rate: 120 GPM
| |
| * D RMS Number: 0-RE-2201 CUE: If checked, RMS reads as stated on permit.
| |
| Checks RMS reading for agreement D RMS
| |
| | |
| ==Background:==
| |
| with permit value Notes value is above RMS D Expected RMS Reading: background Notes that Adjustable Setpoint is
| |
| ~~
| |
| D Adjustable. S~tpoin~1~
| |
| , lower then Expected Reading
| |
| ,,,
| |
| Note to Evaluator: Candidate may determine permit criteria not met when reviewing Min
| |
| # ofCirc Water Pumps required.
| |
| Determines Unit 1 has only 4 CW D Required' .plant l~~tion for conducting rel~ase Pps running and does not meet has.heene i
| |
| ,'::::..
| |
| permit conditions Ii fe' ..
| |
| o*_emiStry n'tJ- .~ .lf~~*~~t:. . with SROJSMJ'"'~
| |
| Informs Chemistry Tech of mistakes
| |
| 's' ~
| |
| ~~Pltm
| |
| !,
| |
| ....... found on permit and does not approve permit.
| |
| Terminating Cue: This JPM is complete when the candidate rejects the permit because the required numbers of Circulating Water Pumps are not operating and RMS values are inconsistent. No further actions are required. The evaluator is expected to end the JPM.
| |
| | |
| Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: SRO-Admin-4 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts:
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT UNSAT _ _ _ _ _ __
| |
| Examiner's Signature and Date:
| |
| | |
| LIQUID RADIOACTIVE CP 601 WASTE RELEASE PERMIT Rev. 01403 Page 126 of 136 CHEMISTRY ATTACHMENT 2 12 RCWMT LIQUID RADIOACTIVE WASTE BATCH RELEASE PERMIT PERMIT#: qOllO Recire Start Date/Time: Pre-Release Gamma Scan#:
| |
| B/4/ZoID 0\'2.1 I Release Source Level:
| |
| 21.1 feet Release Volume: 21 ~ 2 e S liters I
| |
| RELEASE CRITERIA Unit 1 )( Unit 2 I Min # Cire Water Pumps Required:
| |
| Discharge Point: 0 S
| |
| Dilution Flow Rate Pre-Release: 1e:.c.. gpm Maximum Release Flow Rate: 120 gpm i
| |
| RMS Number: O*RE*2201 !
| |
| RMS
| |
| | |
| ==Background:==
| |
| epm 28,000
| |
| * Expected RMS Reading: cpm 2.'27,055 Adjustable Selpoln!:
| |
| ~'25,1o~f> epm APPROVAL (Release Criteria Is within ODCM Reaulrements)
| |
| Independent Verification for Calculations: ~~ t
| |
| )O~
| |
| v
| |
| ~ ...d -6
| |
| * Prepared By: v -
| |
| i Compositor Setup ~~D.t!! t. y
| |
| 'Y--r-- r DatelTime 814/7010 ,q?,b Compositor Setup Peer Ctfeck 8y: "i2Ft.n. ..In..!-o DatelTime 8J41ZOl0 \')40 SCO Approval:
| |
| Wr~1 DatelTime
| |
| ~14 '~OIO 1..000 Release Criteria Is understood, Plant Systems are in operation, Required plant configuration for conducting release has been established. Chemistry Tech discussed permit with SROlSM.
| |
| SM/CRS: DatelTime I If discharging RCWMT, tank has been flushed thru O-RI-2201, and response reported to Chemistry. RMS Pre-Op checks have been completed and release criteria reviewed.
| |
| Correct Setpolnts entered in computer and Peer Checked.
| |
| CRO: DatelTime Independent Verification of Alarm Setpolnts CRO: DatelTime RELEASE DATA Release Start DatelTime: Chemistry Informed Initial Level: feet !
| |
| I Release End DatelTime: Chemistry Informed Final Level: feet i
| |
| RMS Reading Near Start of Discharge cpm Time:
| |
| RMS Reading at Midpoint of Discharge cpm Time:
| |
| RMS Reading Near End of Discharge cpm Time:
| |
| I Background Count Rate O-RE-2201 During DI Flush cpm
| |
| # Gire Water Pps Operating During Release: I # Saltwater Pps Operating During Release:
| |
| POST RELEASE DATA AND REVIEW PERMIT COMPLETE. Release Criteria and Discharge Procedure Requirements Satisfied.
| |
| CRO: i Post Release Gamma Scan #: Post Release Volume: liters Post Release Dilution Flow Rate: gpm Sample Composited (init/date):
| |
| Independent Verification for Calculations:
| |
| I Permit Closed Out (sign/date): SCO Approval/Date:
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1) Unit-l is in Mode 3 with llA and 13B Waterboxes removed form service for cleaning
| |
| : 2) Unit-2 is at 88% power with 21A Waterbox removed from service for cleaning
| |
| : 3) You are performing the duties of the CRS.
| |
| Initiating Cue:
| |
| The Shift Chemistry Technician has delivered a permit for the discharge of 12 RCWMT for your review and approval. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-Admin-5
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-Admin-5 Task Title: Emergency Response Plan Implementation Procedures for a General Emergency (Time Critical)
| |
| Task Number: 204.101 204.032 KiA
| |
| | |
| ==Reference:==
| |
| 2.1.41 (2.9,4.6)
| |
| Method oftesting:
| |
| Simulated Performance: D Actual Performance: IZI Classroom: IZI Simulator: D Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit-1 was at 100% power when the letdown line radiation monitor alarmed.
| |
| : 2. RCS sample analysis indicated RCS activity of 650 /lcilcc Dose Equivalent Iodine.
| |
| : 3. A plant shutdown, to comply with Technical Specification requirements, was begun.
| |
| : 4. At 97% power, 11 SG was diagnosed with a SG tube leak. Pressurizer level was rapidly lowering. A manual trip was initiated due to Pressurizer level <101" and continuing to lower.
| |
| : 5. On the trip, a S/G safety lifted and has not yet reset. During EOP-O, the leaking safety was identified as being on 11 S/G.
| |
| : 6. You are performing the duties of the Shift Manager and have not yet referenced the ERPIP.
| |
| Initiating Cue:
| |
| Per EOP-8, you are to determine the appropriate emergency response actions per the ERPIP. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when an EAL classification is determined based on given plant conditions, initial notification form completed, and Protection Action Recommendation is completed.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| | |
| ERPIP 3.0, Immediate Actions Time critical task:
| |
| Yes Validation Time:
| |
| 10 minutes Simulator Setup:
| |
| Not required
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| 0 Locate ERPIP 3.0 Same as element 0 Refers to Immediate Actions, identifies the category Determines ATTACHMENT 2 is from the listing and goes to the appropriate applicable Attachment.
| |
| ATTACHMENT 2, EMERGENCY CLASSIFICATION o A. CLASSIFY the Event 0 1. ~~EN an event is in progress potentially requmng emergency response, THEN CONDUCT the following actions in parallel:
| |
| 0 a. DETERMINE if existing conditions warrant implementation of one of emergency response attachments:
| |
| * Personnel Emergency, Att 15
| |
| * Fire, Att 16,17,18
| |
| * Radiological Event, Att 19
| |
| * Severe Weather, Att 20,21
| |
| * Hazardous Material Release, Att 22 May determines a Radiological Event exists
| |
| * Containment Evacuation, Att 23
| |
| * Security, Att 24
| |
| * Large Area Loss, Att 25
| |
| * Large Steam Leak, Att 26
| |
| * Extensive Damage Mitigation Guidelines, Att27
| |
| * S/G Level Monitoring During Extensive Damage Mitigation, Att 28 NOTE to Evaluator: 15 minute clock starts when Candidate determine criteria is met for aGE.
| |
| TIME:
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Detennines a GENERAL EMERGENCY classification is warranted under FISSION PRODUCT BARRIER DEGRADATION, based on a loss of all 3 barriers-H.G.5.1.4 Fuel Clad Barrier- Coolant activity is> 600 Ilci/cc DEQ 1-131 RCS Barrier- SGTR>available charging pump capacity.
| |
| * Containment Barrier- Ruptured SG is also faulted outside of containment CUE: U-2 CRS will handle Attachment 19 for a Radiological Event o B. IMPLEMENT Emergency Response Actions o I. IF existing conditions warrant implementation
| |
| * Detennines that U-2 CRS will handle of an emergency response attachment, in parallel, the Radiological Event attachment.
| |
| THEN GO TO that attachment AND begin response actions.
| |
| Detennines from previous evaluation that an EAL is satisfied and obtains an Initial Notification fonn.
| |
| Identifies General Emergency Actions as the appropriate
| |
| * Sitl.A.red Eme;~~n~¥Actions, Att 9 declaration attachment and goes to
| |
| * Alert N~tions
| |
| -.-' AwT'1 Attachment 4.
| |
| --- . -'
| |
| Unusual.i!vept ActiorlS CUE: Candidate commences actions per Attachment 4, General Emergency o Al COMPLETE Attachment 3, Initial Refers to Attachment 3, Initial Notification Fonn. Notification Fonn.
| |
| NOTE TO EVALUATOR: Page 2 of ATTACHMENT 3 contains instructions for completing the form and mayor may not be referred to as the Candidate completes page 1.
| |
| * CUE: Candidate completes Attachment 3 Initial Notification Form, following instructions provided on the back of the form o 1. Emergency Director (ED) completes items A.I Detennines that items AI. through through A 7. Items not mentioned are self A 7 must be completed.
| |
| explanatory.
| |
| | |
| ELEMENT STANDARD
| |
| {* = CRlTICAL STEP)
| |
| I 0 a. ItemA4:
| |
| Retrieve this information from the EAL chart Enters H.G.S.IA on Attachment 3.
| |
| in ERPIP-3.0, Immediate Actions, Attachment i 1, Emergency Action Level Criteria CUE: SG BD RMS showed rising trends prior to blowdown being isolated. The Main Steam Effluent Radiation Monitor for 11 S/G continues to increase and currently reads 3.2E-4 mr/hr. I Blowdown was going overboard prior to the event.
| |
| 0 b. Item AS:
| |
| Radioactivity is being released if there is a breach in the RCS barrier OR a rise in indication occurs on any of the following effluent monitors as a result of the event:
| |
| * WRNMG (RlC-S415) [MCC-114 / MCC 204 P-panels]
| |
| * Main steam Effluent (Rl-542 I , [1I2YOl])
| |
| (Rl-5422 [1I2Y02])
| |
| * Main Vent (RI-5415) [I YIO, 2YlO]
| |
| Determines that radioactivity is being
| |
| * Waste Processing (Rl-54IO) [I YI0] released.
| |
| * Fuel Handling Area Vent (RI-5420)
| |
| * Access Control Area Vent (RI-5425)
| |
| [1 YI 0]
| |
| * ECCS PP Room Vent (Rl-S406) [1 YIO, 2YlO]
| |
| * Liquid Waste Disch (RE-2201) [I YI 0]
| |
| * SGBD Recovery (RI-4095) [MCC-103 /
| |
| MCC203 P-panel]
| |
| * SGBD Tank (RI-4014) [1 Y09, 2Y09]
| |
| 0 c. ItemA5a:
| |
| Radioactivity release is unmonitored if the release bypasses all of the above effluent Determines release is monitored since S/G safety valve lifting is being .
| |
| monitors, such as a containment breech to the monitored by the MSLRM. ~
| |
| outside atmosphere, or an RWT rupture to a storm drain.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP) 0 d. Item A6:
| |
| IF General Emergency is checked in Item 3, THEN DETERMINE appropriate Protective Action Recommendation and PAZs from ERPIP 3.0, Attachment S, General Emergency Protective Action Recommendations, AND CHECK Determines that Protective Action corresponding box (check one box only). Recommendations are necessary and refers to Attachment S.
| |
| IF General Emergency is not checked in Item 3, THEN CHECK "None."
| |
| IF downgrading from General Emergency, THEN CHECK "None."
| |
| Determines items in Section B must 0 2. ED completes items in Section B.
| |
| be completed.
| |
| 0 a. IF ERO has already been notified, THEN Determines step is not required, leaves box unchecked, and proceeds check "N/A." to Step 2.b.
| |
| Identifies:
| |
| 0 b. CHOOSE Notification message from list in Drill General Emergency Section B. Staff Normal Emergency Response Facilities.
| |
| Signs Attachment 3 after Section B is 0 c. ED must sign form. completed. ; Page-l Section-A
| |
| -- 1. Complete Item AI. Checks "is" a drill
| |
| - - 2. *Complete Item A2. Checks "Unit 1"
| |
| -- 3. . *Complete Item A3. Checks "General Emergency"
| |
| ...
| |
| - 4. *Complete ItemA4.
| |
| ... :.
| |
| ..
| |
| Enters "H.G.S.1.4"
| |
| -- S. *Colllplete Item AS. Checks "Yes"
| |
| -- Sa. Complete Item ASa. Checks "Yes"
| |
| -- Sb. Complete Item ASb. Checks "Airborne"
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Note to Evaluator: Attachment 5 should be referenced to complete Item 6.
| |
| ATTACHMENT 5 GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS D A. SELECT A PROTECTIVE ACTION RECOMMENDATION 1.0 IF a controlled release of radioactive material Determines step is NI A.
| |
| from containment is to be commenced in less than 2 hours AND there is assurance that the release will be a short term puff release lasting no more than 2 hours:
| |
| NOTE: If using the meteorological data screen (DRDT), then the DIR "60" indication is to be used for a release from the main vent. The "DIR 10" indication will be used for any other release. If using a backup meteorological data source, then the direction the wind is "from" is to be used.
| |
| CUE: When DRDT screen checked, DIR10 is 90° and DIR60 is 80°.
| |
| D 1.1 When DRDT screen checked, DIRI0 is 90° and Determines step is applicable DIR60 is 80°.
| |
| D If "From" wind direction is between 168.75-303.75, Determines recommendation is NIA then: due to DIRI0.
| |
| D If "From" wind direction is between 303.75-33.75, Determines recommendation is NIA then: due to DIRI0.
| |
| D If "From" wind direction is between 33.75-56.25, Determines recommendation is NIA then: due to DIRI0.
| |
| Determines recommendation is applicable using DIRI0. Selects D
| |
| * If'*'From" wihd ditectionis between 56.25-168.75, "Evacuate PAZ 1 & 2 unless then Evacuate:eAZJ &[.2 unless conditions make conditions make evacuation evacuation dangerous,notify the public in PAZ 1 & 2 dangerous, notify the public in PAZ to take KI, shelter remainder ofthe 10 mile EPZ. 1 & 2 to take KI, shelter remainder
| |
| :.
| |
| of the 10 mile EPZ."
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRlTICAL STEP)
| |
| ATTACHMENT 3, Page 1, Section A Checks "d" Completes A.7 only after items 1 through 6 are completed, and within 15 minutes of determining an EAL is met.
| |
| ATTACHMENT 3, Page 1, Section B Selects blocks for:
| |
| Drill General Emergency Staff Normal Emergency Response Facilities.
| |
| Prints name and signs (only after Section A is completed)
| |
| Terminating Cue: This JPM is complete when an EAL classification is determined based on given plant conditions, the Initial Notification Form is completed, and a Protection Action Recommendation is completed. No further actions are required.
| |
| | |
| Appendix C Job Perfonnance Measure Fonn ES-C-I Verification of Completion Job Perfonnance Measure Number: SRO-ADMIN-5 Applicant:
| |
| NRC Examiner:
| |
| Date Perfonned:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~_ _ _ _ __
| |
| Applicant Response: ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT UNSAT Examiner's Signature and Date: _____________________
| |
| | |
| Appendix C Job Performance Measure Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. Unit-1 was at 100% power when the letdown line radiation monitor alarmed.
| |
| : 2. RCS sample analysis indicated RCS activity of 650 p.cilcc Dose Equivalent Iodine m .
| |
| : 3. A plant shutdown, to comply with Technical Specification requirement, was begun.
| |
| : 4. At 97% power, 11 SG was diagnosed with a SG tube leak. Pressurizer level was rapidly lowering. A manual trip was initiated due to Pressurizer level <101" and continuing to lower.
| |
| : 5. On the trip, a SIG safety lifted and has not yet reset. During EOP-O, the leaking safety was identified as being on 11 S/G.
| |
| : 6. You are performing the duties of the Shift Manager and have not yet referenced theERPIP.
| |
| Initiating Cue:
| |
| Per EOP-8, you are to determine the appropriate emergency response actions per the ERPIP. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-1
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Sim-l (AU Path)
| |
| Task Title: Respond to CEA(s) Misaligned by 15" or more Task Number: 202.008 KIA
| |
| | |
| ==Reference:==
| |
| 001 A2.11 (4.4,4.7)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: IZI Classroom: D Simulator: IZI Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit 1 is in Mode 1 at 100% power.
| |
| : 2. STP 0-29-1, MONTHLY CEA PARTIAL MOVEMENT TEST, was in progress.
| |
| When CEA 01 was being exercised, it became misaligned from its group.
| |
| : 3. AOP-IB has been implemented and all stabilizing actions have been performed.
| |
| : 4. You are performing the duties of the Unit 1 RO.
| |
| : 5. You have been assigned the trip criteria of 'If Any CEAs continue to move without operator action, then trip the Reactor."
| |
| Initiating Cue:
| |
| The CRS directs you to realign CEA 01 per AOP-IB step VI.B. Are there any questions?
| |
| You may begin.
| |
| Task Standard:
| |
| This JPM is complete when the reactor is manually tripped due to 2 dropped CEAs.
| |
| | |
| "
| |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| I. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-IB, CEA Malfunction Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| _ _ I. Reset to IC-24 (both units at 100%)
| |
| _ _ 2. Enter Triggers:
| |
| _ _ a. CEA #01 on bottom; Tl:ceds_ceaOl
| |
| - - 3. Enter malfunctions:
| |
| : a. Dropped CEA #01; cedsO12_1 on Fl
| |
| : b. Dropped CEA #64; ceds012_64 on F2
| |
| : 4. Place CEA #01 in desired condition:
| |
| _ _ a. Manually insert CEA #01 to 110" withdrawn.
| |
| : b. Place CEDS control panel in OFF
| |
| : c. Place the Group 5 inhibit Bypass to OFF
| |
| _ _ d. Select Group 4 and the individual CEA button for CEA #35
| |
| : e. Allow plant to stabilize.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| !
| |
| CUE: The CRS directs you to realign CEA 01 per AOP-IB step VI.B.
| |
| 0 Locates AOP-I B, Section VLB Same as element.
| |
| iD 1. IF at any time the CEA is realigned, THEN perform the subsequent actions in Section Determines step is currently NIA IV., PRELIMINARY, Step B, Page 16.
| |
| i . . . . . .
| |
| CUE. CEA alIgnment time expires In 45 mInutes . i o 2. IF the CEA alignment time has expired, Determines step is NIA THEN PROCEED to Step BA, Page 24.
| |
| CAUTION: CEA movement should be minimized until the cause of the misalignment has been determined.
| |
| CUE: The electric shop discovered and replaced a faulty power supply during the troubleshooting. The CRS directs you to continue the procedure.
| |
| CUE: The CRS has directed the CRO to maintain power level no higher than the present level via boration.
| |
| o 3. Attempt to realign the affected CEA(s): Same as element D a. Maintain Reactor Power as required by:
| |
| * Boration PER OI-2B, CVCS BORATION, Determines CRO will maintain DILUTION AND MAKEUP OPERATIONS. power with no action necessary on OR his part
| |
| * Adjust Regulating CEAs.
| |
| Selects Group 5 Selects CEA 01 Same as element Determines CMI is in effect NOTE: CMI will be bypassed to the affected group and applied to all other groups, and CMI bypass annunciation will alarm.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Same as element Same as element CAUTION: Do NOT allow Reactor Power to rise above the power the unit was stabilized at in Section IV. PRELIMINARY, Step A.2, while the CEA is being realigned. Turbine load shall NOT be raised until the CEA is within its alignment requirements.
| |
| : f. Realign the CEA.
| |
| Determines SID CEA rates are NtA.
| |
| Determines Regulating CEA rates are appropriate. Commences recovery of CEA using the shim stick on lCOS. (Pull no more than 6.75" on CEA #01 each time CEA is withdrawn).
| |
| o 2. IF the CEA must be inserted, THEN insert Determines step is NtA the CEA.
| |
| I NOTE TO EVALUATOR: The intent ofthe JPM going forward is for the student to I recognize that a Rx trip is required when two CEAs become misaligned by >15" per Step V.A.I.
| |
| CUE: Cue the Booth Operator to initiate Fl to drop the two CEAs into the core when either CEA 01 is within 7.5 inches of its respective group OR when cued by the Evaluator.
| |
| Candidate secures attempts to lC05 alarms DROPPED CEA PI, PRIMARY PPDIL, I. withdraw CEA. Observes alarms.
| |
| PRIMARY PDIL, SECONDARY PPDIL, i Reviews the 1COS indications and i SECONDARY PDIL, and the CEA deviation alarms determines that two CEAs have annunciate fallen into the core, using CEAPDS and the CEA mimic display.
| |
| 0 Locates AOP-IB, Section V Same as element 0 1. IF two or more CEAs are misaligned from the other CEAs in their respective group by greater than Determines 2 CEAs have dropped.
| |
| 15 inches, THEN perform the following actions:
| |
| i
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| CUE: If the candidate recommends tripping the reactor to the CRS, Acknowledge and Direct the RO to trip the reactor and implement EOP-O.
| |
| ' , ,>";" 'i: ,),<tL" :;:~\, \'~5 Depresses the two manual reactor tf a.:rriptheReaotor: trip buttons on 1COS.
| |
| D b. Implement EOP-O, Post Trip Immediate No action required Actions Terminating Cue: This JPM is complete when the manual reactor trip PB's are depressed. No further actions are required. The evaluator is expected to end the JPM.
| |
| I Time Stop: _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: Sim-l Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT UNSAT _ _ _ _ _ __
| |
| Examiner's Signature and Date:
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1) Unit 1 is in Mode 1 at 100% power.
| |
| : 2) STP 0-29-1, MONTHLY CEA PARTIAL MOVEMENT TEST, was in progress.
| |
| When CEA 01 was being exercised, it became misaligned from its group.
| |
| : 3) AOP-IB has been implemented and all stabilizing actions have been performed.
| |
| : 4) You are performing the duties of the Unit-l RO.
| |
| : 5) You have been assigned the trip criteria of' If Any CEAs continue to move without operator action, then trip the Reactor."
| |
| Initiating Cue:
| |
| The CRS directs you to realign CEA 01 per AOP-1B step VLB. Are there any questions?
| |
| You may begin.
| |
| | |
| \r-------. --~ ----.-----,
| |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-2
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Sim-2 Task Title: Restart RCPs Task Number: 201.028 KIA
| |
| | |
| ==Reference:==
| |
| 022 A4.01 (3.6,3.6)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: L8J Classroom: D Simulator: L8J Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit-l is shut down for a short maintenance outage.
| |
| : 2. The Unit is expected to be maintained in Mode 3 per OP-4.
| |
| : 3. A short time ago RCP Feeder Breaker, 252-1201, tripped.
| |
| : 4. AOP-3E has been implemented.
| |
| : 5. The cause of the tripped breaker was determined to be personnel error. There is no common mode failure. RCP Feeder Breaker, 252-1201, has been reclosed.
| |
| : 6. It has been determined that no RCP CBO temperatures exceeded 250 of.
| |
| : 7. You are performing the duties of the Unit 1 RO.
| |
| Initiating Cue:
| |
| The CRS has directed you to start Reactor Coolant Pumps per AOP-3E Step IV.I.5. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when 11A and 11B RCPs have been started. No further actions are necessary
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-3E- LOSS OF ALL RCP FLOW, MODES 3, 4, OR 5 Time Critical Task:
| |
| No Validation Time:
| |
| 15 minutes Simulator Setup:
| |
| : 1. IC-ll
| |
| : 2. Cool down to approximately 520 OF Tc.
| |
| : 3. Place TBV controller in Auto with a setpoint of810#
| |
| - - 4. Freeze simulator.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| a Locate AOP-3E, Step IV.I.5 Same as element.
| |
| CUE: T COLD indicates approx 520 OF o 5. Reduce T COLD to less than 525 OF using Checks loop T COLD indications (1 C06) andlor the ADVs or TBVs average TCOLD (ICOS).
| |
| CUE: PZR level indicates 160 inches a 6. Raise PZR level to between 155 and 170 Checks in-service PZR level control channel inches. (IC06)
| |
| CUE: T COLD indicates approx 520 OF o 7. IF TCOLD is less than 369 OF, Checks loop TCOLD indications (IC06) andlor THEN perform the following: average TCOLD (1 C05). Determines step is NIA CUE: RCP restart criteria are met o 8. Verify that ALL of the following Rep restart criteria are met:
| |
| Checks 12 SERV BUS VOLTS ~ 13.8KV Checks lights for l2AIB RCP Oil Lift Pps on or contacts ABO to verify Checks lights for 11 AlB RCP Oil Lift Pps on or contacts ABO to verify Checks 12 SERV BUS VOLTS (IC20)
| |
| Checks 11,12,13,14,15/16 4KV bus volts (1CI7,18,19)
| |
| Checks CBO temps on the plant computer a '. ReS suiJc60lingls ~re~~e Checks CET SCM indicators (IC05)
| |
| 'based
| |
| ~. .
| |
| (m'eeT temper~t*
| |
| .,.~. .\'~
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Checks S/G levels (IC03)
| |
| Checks Main or Aux Feedwater in operation and feeding S/G (lC03/IC04)
| |
| Checks ADVs or TBVs in operation (IC03) and controlling RCS temp (1 C06)
| |
| Checks PZR level on in-service level control channel or PZR level recorder (1 C06).
| |
| Checks loop Tc indications (lC06) and or average TCOLD (1 C05)
| |
| Refers to EOP Attachment (1)
| |
| NOTE If 11 RCS loop is available, then a RCP in that RCS loop should be started to restore Main Spray capability.
| |
| NOTE Determines IlA & B RCPs will be started The second RCP in the same loop should be first.
| |
| started within 5 minutes of starting the first RCP. This should be done due to the NPSH requirements for two RCPs in the same loop being less restrictive than NPSH requirements for single RCP operation.
| |
| : 9. WHEN RCP restart is desired, AND RCP restart criteria are met, THEN start one RCP in a loop with a SG available for heat removal as follows:
| |
| Same as element
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| CUE: "CCW FLOW LO" alarms are clear on all RCPs Checks alann on I1A RCP alann panel (lC07) i CUE: llA RCP Oil Lift Pp indicates running Places HS for IIA RCP to Start and checks Oil Lift Pp running CUE: "OIL LIFT PP PRESS LO" alarm is clear (J d. Verify that the "OIL LIFT PP PRESS Checks RCP alann on IIA RCP alann panel LO" alarm is cleared. (lC07)
| |
| CUE: Oil Lift Pp has been operating for 60 seconds (J e. Operate the Oil Lift Pump for at least Same as element 60 seconds before starting the RCP.
| |
| (J Inserts Sync Stick in HS for 252-11 P02
| |
| ! CUE: Synchroscope is not rotating (J g. On panel 1C 19, verify that the Same as element synchroscope is NOT rotating.
| |
| CUE: llA RCP is running with normal starting amps indicated CAUTION Starting an Rep may cause a Pressurizer level transient. The potential for a pressure transient exists if an RCP is started in a loop in which no SIG is available for heat removal.
| |
| Places HS for llA RCP to start and check lights and motor amps CUE: llA RCP running motor amps are steady at the normal operating value (J i. Verify that the RCP is NOT cavitating by observing that running current is Checks motor amps at RCP HS steady.
| |
| CUE: CVCS is operating to restore PZR level to 160 inches (J 10. Operate Charging and Letdown to Checks in-service PZR level control channel, restore and maintain PZR level between 101 on 1C06. Checks LID flow and Chg Pps are and 180 inches. consistent restoration of PZR level.
| |
| | |
| ELEMENT STANDARD I CUE: ttA RCP seal pressures indicate normal seal operation I D 11. Monitor RCP seal parameters following Checks llA RCP Middle and Upper seal pump restart. pressure indicators on 1C06 CUE: Loop temperatures are equalized D 12. Allow backflow to equalize Checks loop temperature indicators on 1C06 temperatures in the opposite loop.
| |
| I
| |
| : 13. Start a second RCP in the same loop by performing the following actions:
| |
| :'------.
| |
| CUE: RCP parameters meet NPSH requirements for starting a second RCP D a. Ensure RCP NPSH requirements are maintained PER ATTACHMENT (1),
| |
| Refers to EOP Attachment (l)
| |
| RCPPRESSURE/TEMPERATURE LIMITS of the EOP ATTACHMENTS.
| |
| I D b. Start an RCP PER Step 1.9, Page 21. Refers back to Step 9.
| |
| : 9. WHEN RCP restart is desired, AND RCP restart criteria are met, THEN start one RCP in a loop with a SG available for heat removal as follows:
| |
| CUE: CVC 505 & 506 indicate open D a. On 1C07, verify that the RCP BLEED-OFF ISOL valves are open:
| |
| Same as element o l-CVC-505-CV D l-CVC-506-CV CUE: "CCW FLOW LO" alarms are clear on all RCPs Checks lIB RCP alarm panel (lC07)
| |
| CUE: llB RCP Oil Lift Pp indicates running Places HS for 11 B RCP Oil Lift Pp to Start and checks Pp running
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| : "OIL LIFT PP PRESS LO" alarm is clear 0 d. Verify that the "OIL LIFT PP PRESS Checks lIB RCP alarm panel (lC07)
| |
| LO" alarm is cleared.
| |
| CUE: Oil Lift Pp has been operating for 60 seconds o e. Operate the Oil Lift Pump for at least Same as element 60 seconds before starting the RCP.
| |
| Inserts Sync Stick in HS for 2S2-13P02
| |
| .
| |
| CUE' Synchroscope is not rotating o g. On panel 1C 19, verify that the Same as element synchroscope is NOT rotating.
| |
| CUE: 11B RCP is running with normal starting amps indicated CAUTION Starting an RCP may cause a Pressurizer level transient. The potential for a pressure transient exists if an RCP is started in a loop in which no S/G is available for heat removal. !
| |
| ~ ,
| |
| Places HS for 11 B RCP to start and check I o h.s:tartthe RGP. lights and motor amps
| |
| ;~;4jf\;i~ ..... .' ....
| |
| CUE: 11B RCP running motor amps are normal 0 i. Verify that the RCP is NOT cavitating by observing that running current is Checks motor amps at RCP HS steady.
| |
| CUE: 11B RCP seal pressure indicate normal seal operation 0 13.c.Monitor RCP seal parameters Checks IlA RCP Middle and Upper seal following pump restart. pressure indicators on 1C06 Terminating Cue: This JPM is complete when l1A and lIB RCPs have been started.
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: Sim-2 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT -------
| |
| UNSAT ______________
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-1 APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1) Unit-1 is shut down for a short maintenance outage.
| |
| : 2) The Unit is expected to be maintained in Mode 3 per OP-4.
| |
| : 3) A short time ago RCP Feeder Breaker, 252-1201, tripped.
| |
| : 4) AOP-3E has been implemented.
| |
| : 5) The cause of the tripped breaker was determined to be personnel error. There is no common mode failure. RCP Feeder Breaker, 252-1201, has been reclosed.
| |
| : 6) It has been determined that no RCP CBO temperatures exceeded 250 OF.
| |
| : 7) You are performing the duties of the Unit 1 RO.
| |
| Initiating Cue:
| |
| The CRS has directed you to start Reactor Coolant Pumps per AOP-3E Step IV.I.5. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-3
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Sim-3 (Alt Path)
| |
| Task Title: Monitor RCS Depressurization Task Number: 201.059 KIA
| |
| | |
| ==Reference:==
| |
| 013 A4.01 (4.5,4.8)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: BJ Classroom: D Simulator: BJ Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. A LOCA occurred on Unit-120 minutes ago.
| |
| : 2. SIAS has automatically initiated.
| |
| : 3. EOP-5 has been implemented.
| |
| : 4. RCS pressure has lowered to 600 - 700 PSIA.
| |
| : 5. You are performing the duties of the Unit-l CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to perform EOP-5, Block Step D, Monitor RCS Depressurization.
| |
| Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when 12 HPSI Pump has been started and HPSI flows have been compared to RCS pressure to verify adequate safety injection system operation.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. EOP-5
| |
| : 2. EOP Attachment (10)
| |
| Time critical task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. IC-24, both units at 100% power
| |
| : 2. Insert Malfunction RCS 002 at 10,000 gpm
| |
| : 3. Run simulator until reactor trips.
| |
| _ _ 4. Trip RCPs and allow RCS pressure to stabilize at approximately 600 - 700 PSIA.
| |
| : 5. Start 13 AFW Pp
| |
| : 6. Insert Malfunction SI002_03, 13 HPSI PP Breaker failure
| |
| : 7. Throttle 11 HPSI PP Discharge valve, I-SI-428, to obtain a flow of 400 500 GPM (approximately.15 turns open).
| |
| _ _ 8. Insert trigger attached to 12 HPSI PP start, SCI2HPSI, to open 11 HPSI Discharge valve, I-SI-428, to .35 turns open
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start: - - -
| |
| o Identifies and locates EOP-5, Block Step "D" Same as element CUE: When checked,
| |
| * RCS pressure is 600 - 700 PSIA
| |
| * Actuation SYS SIAS TRIPPED ALARM (G-5) is in.
| |
| Verifies SIAS Alarm in, HPSI PP o 1. IF Pressurizer pressure is less than or equal to running and HPSI Header Valves 1725 PSIA OR containment pressure is greater open. May note 13 HPSI PP failure than 2.8 PSIG, THEN verify SIAS actuation.
| |
| at this time.
| |
| o 2. IF Pressurizer pressure is greater than 1725 PSIA AND containment pressure is less than 2.8 Determines step is N/A.
| |
| PSIG o 3. IF SIAS has actuated, Determines step is applicable THEN perform the following actions:
| |
| CUE: When checked, 11 HPSI Pump; 11 and 12 LPSI Pumps; and 11, 12, and 13 CHG Pps are operating. 13 HPSI Pump did not start.
| |
| : a. Verify the following pumps are running:
| |
| Checks 11 HPSI Pp running at 1C08 o 11 HPSIPP Determines 13 HPSI PP failed to start. May note "U-l 4KV ESF o 13 HPSI PP MOTOR OVERLOAD" alarm on
| |
| * lC18 o 11 LPSIPP Checks both LPSI Pumps running at o 12 LPSI PP 1C08 and 1C09 Checks all 3 Charging Pumps o ALL available Charging PPs running at 1C07 .
| |
| : b. Verify safety injection flow:
| |
| CUE: When checked: Total BPSI flow is - 500 GPM (totals from FI-311, 321, 331 & 341) or per I-FI-351, at lC09, reads - 500 GPM.
| |
| Refers to Att (10) and determines HPSI flow should be - 600 GPM.
| |
| Attempts to verify HPSI flow using FIs-311132113311341 or FI-35 1.
| |
| Determines HPSI flow is insufficient.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Alternate Actions begin NOTE TO EVALUATOR:
| |
| It is anticipated the candidate will start 12 HPSI PP due to the failure of 13 HPSI PP to start. However, the procedure leaves room for possible determination that 11 HPSI has failed due to less than adequate flow. The candidate MUST start 12 HPSI to complete the critical element. If candidate chooses to start 12 HPSI due to the failure of 11 HPSI he will complete the first asterisked element. If candidate chooses to start 12 HPSI due to the failure of 13 HPSI he will complete the second, third and fourth asterisked elements.
| |
| NOTE TO EVALUATOR:
| |
| An alternative to unthrottling 11 HPSI discharge, to ensure 2 PP curves on ATT (10) is met when 12 HPSI is started would, be to trip 11 HPSI CUE: When 12 HPSI PP is started HPSI flow will slowly raise to meet requirements of Attachment (10) for 2 HPSI Pumps running. (Cue Booth Operator to open 11 HPSI Pump Discharge valve, I-S1-428, simultaneous with the start of 12 HPSI Pump) b.l Perform the following actions as necessary:
| |
| Determines step is N/A OR Starts 12 HPSI PP due to failure of 11 HPSI PP D If 13 HPSI PP failed, Then align 12 HPSI Determines step is applicable PP as follows:
| |
| Determines step is NIA
| |
| [J Start 12 HPSIPP OR Starts 12 HPSI PP due to failure of 13 HPSI PP
| |
| [JOpe{l, HH~I{H1:)R XCONN valve,l-SI-
| |
| . 53;M~.Y .... Same as element Same as element Alternate Actions complete Refers to Attachment (10) and determines HPSI flow should be ~
| |
| [J HPSI flow PER ATTACHMENT (10), 1200 GPM for 2 HPSI operation.
| |
| HIGH PRESSURE SAFETY INJECTION Notes HPSI flow meets requirements FLOW, when pressure is below 1270 PSIA. of ATT (10) by totaling header flows using FIs-3I1I3211331/341 or FI 351.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP) o LPSI flow PER ATTACHMENT (11),
| |
| LOW PRESSURE SAFETY INJECTION Determines step is NIA FLOW, when pressure is below 185 PSIA.
| |
| Terminating Cue: This JPM is complete when 12 HPSI Pump has been started and HPSI flows have been compared to RCS pressure to verify adequate safety injection system operation.
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: Sim-3 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT __________ UNSAT _________
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
| |
| : a. A LOCA occurred on Unit-l 20 minutes ago.
| |
| : b. SIAS has automatically initiated.
| |
| : c. EOP-5 has been implemented.
| |
| : d. RCS pressure has lowered to 600 - 700 PSIA.
| |
| : e. You are performing the duties of the Unit-l CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to perform EOP-5, Block Step D, Monitor RCS Depressurization.
| |
| Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-4
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: Sim-4 (Alt Path)
| |
| Task Title: Respond to RCS leakage exceeding one Charging Pump, Modes 1 and 2 Task Number: 202.015 KJA
| |
| | |
| ==Reference:==
| |
| 004 KI.15 (3.8,4.0)
| |
| Method of testing:
| |
| Simulated Perfonnance: D Actual Perfonnance: [gJ Classroom: D Simulator: [gJ Plant:
| |
| READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit 1 is at 100% power and operating with steady state conditions.
| |
| : 2. Pressurizer level begins to steadily lower and the backup charging pumps automatically start.
| |
| : 3. Pressurizer level is still slowly lowering.
| |
| : 4. You are performing the duties of the Unit 1 CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to perform Steps VI.B thru VI.E of AOP-2A. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when AOP-2A Block Steps VI.B thru VI.E are completed. No further actions are required.
| |
| | |
| J Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-2A, Excessive Reactor Coolant Leakage Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. IC-24, 100%.
| |
| : 2. Insert malfunction CVCS 020 (Charging header break inside Containment) with a value of22.5%.
| |
| _ _ 3. Run simulator until the second backup charging pump starts. Lower leak size to
| |
| -5% so that PZR level is still lowering, but charging header pressure is > RCS pressure. Ensure both Pressurizer Level channels indicate greater than a 15 inch deviation from program level.
| |
| : 4. Makeup to VCT to ensure level is high in the band when the simulator is taken out of freeze.
| |
| _ _ 5. Shut 1-CVC-183 when requested.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| o Locate AOP-2A, Section VI. Same as element B. Verify the event is not challenging RPS CUE: The RO will be responsible for monitoring for trip criteria.
| |
| o B.1 IF, at ANY time, PZR pressure reaches the TM/LP pretrip setpoint, Determines RO will be assigned to THEN, with the permission of the SM/CRS, monitor trip criteria perform the following actions:
| |
| C. Control Pressurizer Level CUE: When checked, Pressurizer level is slowly lowering.
| |
| Monitors Pressurizer level (LI-IIOX-l and LI-IIOY-l and/or o C.1 Verify that Charging Pumps are maintaining LR-I10, on 1C06). Notes that PZR level within 15 inches of programmed level. Pressurizer level is slowly lowering with all backup ~harging pumps runnmg.
| |
| CUE: When checked, CVe-515 and CVC-516 indicate shut.
| |
| o C.l.l IF PZR level is NOT being maintained by ALL available Charging Pumps, THEN shut the LID CNTMT ISOL valves:
| |
| Same as element o l-CVC-5l5-CV o l-CVC-5l6-CV CUE: RO will initiate makeup to VCT if (as) required. (Cue Booth Operator to initiate makeup to VCT if necessary).
| |
| o C.l.2 Makeup to the VCT to maintain level Determines no action required at this as necessary. time.
| |
| D. Check for a S/G Tube Leak CUE: Condenser Off Gas, S/G BID & Main Steam Line Rad Monitors all indicate normal readings. Preliminary check of S/G samples indicate no tube leakage. S/G levels are normal.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| D D.I Detennine if a SG Tube Leak exists by observing a rise in ANY of the following:
| |
| D SG sample activities D Condenser Off-Gas radiation levels at I-RI 1752 Monitors RI-1752, RI-4014 and/or D SG Blowdown radiation levels at l-RI-4095 or RI-4095 on lC22, and RIC-5421 and 5422, on 2C24B.
| |
| l-RI-4014 Monitors LIA -1105 and D MAIN STEAM EFFL RAD MONITOR LIA-I106 and/or LR-l111 and LR radiation levels at l-RIC-5421 or l-RIC-5422 1121, on IC03. Chemistry acknowledges samples requested.
| |
| D MAIN STM N-16 RAD MONITOR levels at l-RIC-5421A or l-RIC-5422A D SG water level (Unexplained)
| |
| D Feed flow mismatch D D.2 IF a SG Tube Leak is indicated, THEN Detennines step is N/A perfonn the following actions:
| |
| E. Attempt to Isolate the Leak D E.1 Verify that the LID CNTMT ISOL valves are shut:
| |
| Same as element D l-CVC-515-CV D I-CV C-516-CV CUE: When checked, Quench Tank parameters, discharge piping temperatures and acoustic monitor indications are normal.
| |
| D E.2 Check there is NO PORV leakage by the following indications: Monitors Quench Tank: parameters (LIA-116, PA-116 and PA-116A and 0 Quench Tank: Parameters TIA-116, on lC06). Monitors 0 PORV discharge piping temperatures, computer point T107 and T108.
| |
| Monitors acoustic monitor computer points T107 and TI08 indication.
| |
| 0 Acoustic Monitor indication
| |
| * CUE: When checked, PS-5464 indicates shut.
| |
| 0 E.3 Verify that RCS SAMPLE ISOL valve, Same as element I-PS-5464-CV, is shut.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| * CUE: When checked, RC-I03 and RC-I04 indicate shut.
| |
| o EA Verify that the Reactor Vessel Vent valves are shut:
| |
| Same as element o l-RC-I03-SV o l-RC-104-SV CUE: When checked, RC-I05 and RC-I06 indicate shut.
| |
| o E.S Verify that the Reactor Vessel Vent valves are shut:
| |
| Same as element o l-RC-IOS-SV o I-RC-I06-SV NOTE:
| |
| A leak on the Charging header which exceeds the capacity of the charging pumps can be identified by Charging header pressure indicating less than RCS pressure. Identification of the leak may be missed if more than one charging pump is running.
| |
| CUE: When checked, charging header pressure is - 650 PSIG with one charging pump,
| |
| -1850 PSIG (2 charging pumps running) or 2280 PSIG (3 charging pumps running).
| |
| o E.6 Determine if the leak is on the Charging header by performing the following actions:
| |
| Same as element Determines charging header pressure is less than RCS pressure, verifies leak is on the charging header.
| |
| : c. IF the leak is NOT on the Charging header, THEN start any CHG PPs that were Determines step is NtA stopped.
| |
| CUE: When checked, charging header pressure is 1700 PSIG (2 charging pumps running) or 2280 PSIG (3 charging pumps running).
| |
| o E.7 IF the leak is on the Charging header, Determines step is applicable THEN perform the following actions:
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| GlJ~b~DispRlchan qpe~torf' Dispatches an operator to determine "lQcation~f the . " l the location of the leak.
| |
| NOTE: CHG PP HDR XCONN, l-CVC-182, is located near 12 Charging Pump.
| |
| * CUE: ABO reports no leakage in CHG PP Room. RadCon reports video surveillance
| |
| * indicates no abnormal leakage anywhere in the Aux Building.
| |
| o c. IF the leak is upstream of CHG PP HDR XCONN, l-CVC-I82, THEN shut I-CVC- Determines leak is downstream of 182, AND start 12 or 13 CHG PP as I-CVC-182 and this step is NtA.
| |
| required.
| |
| o d. IF the leak is downstream of l-CVC-182, Determines step is applicable THEN align Charging to the Auxiliary HPSI Header:
| |
| CUE: When checked, l-CVC-517, 518 and 519 indicate shut.
| |
| o (1) Verify that the following valves are shut:
| |
| o AUX SPRA Yvalve, l-CVC-S17-CV Same as element o l-CVC-S18-CV Same as element o l-CVC-S19-CV NOTE: The Auxiliary HPSI Header is out of service and T.S. 3.5.2 applies when I-SI-656-MOV is shut.
| |
| * CUE: The CRS will handle all TS entries. When checked, SI-656 indicates shut.
| |
| o (2) Shtlt the BPSr AUi'{HIllSISOt Same as element valve,;.1-S1-656-MOV:*?
| |
| CUE: Selected valve indicates open.
| |
| Cl(i5)ccOpell Q~Ii~of;;tlle following ..,.~~~.~~. ~
| |
| HPSI~RValve&~7, ...
| |
| . 0 '1-SP617-MOV}l~
| |
| . [J 1-SI~627-MOV".~~r;*** Same as element
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| CUE: When checked, l-CVC-269 indicates open.
| |
| o (4}Qpeil.th~StrQ'CHG HDR v~ve,l- Obtains key from locker & opens 1 CVC-269-MOV. CVC-269-MOV NOTE:
| |
| REGEN HX CHG INLET, l-CVC-183, is located in the 27 foot West Penetration Room.
| |
| CAUTION:
| |
| When a Charging Pump is started, Reactor power will lower due to the concentration of Boric Acid in the Auxiliary HPSI header being 2300 PPM or greater.
| |
| CUE: ABO reports no leakage in either the 5' or 27' West Penetration rooms, concurring with RadCons earlier report. Containment parameters clearly indicate the leak is inside containment. When dispatched, ABO reports l-CVC-183 is shut. (Cue booth operator to shut l-CVC-183) o (5) IF the leakis dpvvnstream ofthe , Determines leak is downstream of REGENHX CHG INLET valve, l-CVC CVC-I83. Dispatches ABO to shut 183, THEN shutl:~CVC-183, ' ,','
| |
| CVC-I83.
| |
| AND start any available CHG PP.
| |
| o (6) IF the leak is upstream of I-CVC-I83, Determines step is N/A CUE: CRS will review LCO actions o (7) Declare the Auxiliary HPSI Header Informs CRS of need to refer to T.S out of service and refer to T.S. 3.5.2 ECCS-OQerating. 3.5.2 NOTE: If charging via the Auxiliary HPSI header, the Reactor power reduction will result in an initial PZR level reduction.
| |
| CUE: When checked, Pressurizer level is lowering as is Tcold and generator output (due to boron just injected from SI line.
| |
| NOTE TO EVALUATOR: Cue the booth operator to lower turbine load and restore TcoLD to program as necessary. Once turbine load is being reduced, PZR level starts to rise.
| |
| Determines that PZR level is 0 e. Verify charging flow by observing a rise lowering due to boron addition from SI line. When turbine load is being in PZR level. reduced, determines PZR level is increasing.
| |
| CUE: When checked, Containment humidity, sump level alarm frequency, Containment gaseous and particulate activity has risen. WRNGM and Main Vent Gaseous alarms are clear.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Monitors TI-5309 and 5311, on 0 E.8 IF the leak is detennined to be occurring lCIO. Monitors PI-5308, on IClO. I inside Containment by checking the following Monitor MI-53l0 and 5312, on indications: lClO. Monitors sump level alann
| |
| ! frequency.
| |
| 0 Rise in Containment temperature, pressure, Detennines leak is in Containment.
| |
| humidity or sump level alann frequency 0 Rise in Containment gaseous or particulate Monitors RI-5281 and 5280, on activity lC22.
| |
| 0 "U-I WR NOBLE GAS RAD MON" and Monitors window 18, on ICIO and "UNIT I MAIN VENT GASEOUS" alanns RI-54l5, on lC22.
| |
| clear 0 THEN perfonn the following actions:
| |
| CUE: All available Containment air coolers are running in high.
| |
| o a. Start ALL available CNTMT AIR Starts all available Containment air CLRs in HIGH. coolers in high.
| |
| CUE: When checked, all CNTMT CLR EMR OUT valves indicate open.
| |
| o b. Open the CNTMT CLR EMER OUT valves for the operating CNTMT AIR Same as element CLRs.
| |
| o E.9 IF the leak is NOT occurring inside of Detennines step is NIA Containment, CUE: RI-3819 indicates normal.
| |
| o E.10 Detennine that NO leakage into the Component Cooling System is indicated by:
| |
| o NO rising trends on Component Cooling Radiation Monitor, Monitors RI-3819, on lC22.
| |
| l-RI-3819.
| |
| Detennines there is no leak into the o "CC HEAD TK LVEL" high alarm clear CC system.
| |
| | |
| Terminating Cue: This JPM is complete when AOP-2A Block Steps VLB thru VLE are completed. No further actions are required.
| |
| | |
| Verification of Completion Job Performance Measure Number: Sim-4 (Alt Path)
| |
| Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. Unit 1 is at 100% power and operating with steady state conditions.
| |
| : 2. Pressurizer level begins to steadily lower and the backup charging pumps automatically start.
| |
| : 3. PressurizerI level is still slowly lowering.
| |
| : 4. You are performing the duties of the Unit-l CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to perform Block Steps VI.B thru VI.E of AOP-2A. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-5
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Sim-S (Alt Path)
| |
| Task Title: Verify the Containment Environment Safety Function is satisfied Task Number: 201.016 KJA
| |
| | |
| ==Reference:==
| |
| 022 A3.01 (4.1, 4.3)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: C8J Classroom: D Simulator: C8J Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. A transient resulting in a Reactor trip has occurred on Unit-I.
| |
| : 2. EOP-O, Post Trip Immediate Actions, has been implemented.
| |
| : 3. You are performing the duties of the CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to verify the Containment Environment Safety Function. Are there any questions? You may begin.
| |
| Task Standard:
| |
| The JPM is complete when the CRS is informed of the status of the Containment Environment Safety Function. No further actions are required.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. EOP-O, Post Trip Immediate Actions Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| _ _ 1. IC-24, Unit 1, 100% power
| |
| : 2. Insert the following Malfunctions:
| |
| - - a. ESFAOOI 01
| |
| - - b. ESFAOOI 02
| |
| : c. SIAS auto failure
| |
| : d. RCSOOI cold leg rupture
| |
| : 3. Run simulator for 2 minutes then freeze.
| |
| : 4. Override Containment Narrow Range pressure on lC10, I-PI-5308, to 0#.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| F. VERIFY THE CONTAINMENT ENVIRONMENT SAFETY FUNCTION IS SATISFIED.
| |
| CUE: When checked: Containment pressure is 0 PSIG as read on PI-5308 (NR), 35 PSIG as read on both WR indications (PI-5307/5310), and Rx Cavity humidity is 100%.
| |
| Checks containment pressure indication on 1C09 and determines that containment pressure is greater than 0.7 PSIG based on WR indication. Though not critical, identifies that NR pressure indicator is suspect and makes report to CRS
| |
| "~~;;ii that Alternate Actions are being taken for Containment Environment due to high pressure.
| |
| -----I NOTE TO EVALUATOR:
| |
| * The report of "Taking Alternate Actions" can be made at the direction of the candidate but should be reported as soon as practical.
| |
| * The candidate may manually initiate SIAS early if it is recognized SIAS has not automatically actuated. Equipment may already be in its desired condition when Containment Environment is checked.
| |
| 1.11F containment pressure exceeds 0.7 PSIG, THEN perform the following:
| |
| CUE: All available Containment Air Coolers are operating.
| |
| Checks all four containment air coolers on 1C09ll 0 to determine if all available coolers are operating, starts any not running, or may recognize that SIAS failed to initiate and may manually initiate SIAS.
| |
| , CUE: All containment cooler emergency outlet valves are open.
| |
| Checks valve indication on 1ClO and places the valves in open or may recognize that SIAS failed to initiate and may manually initiate SIAS 1.2 IF containment pressure exceeds 2.8 PSIG, THEN verify ESFAS actuation of the following:
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| CUE: SIAS has NOT actuated. SIAS alarm not actuated, 11 & 13 HPSI pumps are not operating and HPSI header MOVs are shut.
| |
| Determines that SIAS has failed to D SIAS actuate.
| |
| CUE: After SIAS is manually actuated: SIAS alarm "ACTUATION SYS SIAS TRIPPED" actuated, 11 & 13 HPSI pumps are operating normally, and HPSI header valves are open Channel A & B SIAS manual actuation pushbuttons are depressed on lC09l10. Checks SIAS alarm "ACTUATION SYS SIAS TRIPPED" has actuated, 11 & 13 HPSI pumps are operating and HPSI header valves are open.
| |
| CUE: CIS alarm "ACTUATION SYS CIS TRIPPED" has actuated, CCW isolations to containment are shut.
| |
| Checks CIS alarm "ACTUATION SYS CIS TRIPPED" has actuated D CIS and Containment CCW isolation valves are shut.
| |
| CUE: RCPs are tripped Trips all RCPs at 1C06.
| |
| CUE: CSAS alarm "ACTUATION SYS CSAS TRIPPED" has actuated, Containment Spray pumps are operating normally, spray CVs are open and 1400 GPM of spray flow is indicated.
| |
| Verifies CSAS has actuated by CSAS alarm "ACTUATION SYS D 1.4 IF containment pressure exceeds 4.25 PSIG, CSAS TRIPPED" has actuated, Containment Spray pumps are THEN verify CSAS actuation. operating and spray discharge valves are open. Verifies CS flow and that the CBP's are not running.
| |
| CUE: All containment temperatures are >235 OF Checks containment temperature D 2. Check containment temperature is less than 120 indication on 1C09 and determines OF. that temperature is greater than 120 OF.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| NOTE TO EVALUATOR: Actions in step F.2.1 may not be performed because these actions were taken earlier in the JPM.
| |
| 2.1 IF containment temperature exceeds 120 OF, THEN perform the following:
| |
| I CUE: All available Containment Air Coolers are operating.
| |
| Checks all four Containment Air o a. Verify ALL available CNTMT AIR CLRs Coolers on lC09l10 to determine are operating. that all available coolers are operating.
| |
| CUE: The containment cooler emergency outlet valves are open.
| |
| o b. Open the CNTMT CLR EMER OUT valves Checks valve indication 1C 10 to for the operating CNTMT AIR CLRs. ensure they are open I
| |
| CUE: Containment gaseous RMS indicates 7000 CPM and the Particulate RMS reads 3000 CPM. Both are above normal and slowly increasing, though not in alarm. The Containment Hi-Range monitors are indicating normal. The IRUs started if the SIAS was initiated earlier or start if manually started.
| |
| Verifies alarms clear on 1C 10 and uses indications at 1C22 to identify that the containment RMS have a o 3. Check containment radiation monitor alarms are rising trend. Starts IRUs if not already running. May take actions clear with NO unexplained rise. based on temperature affects to the Cntmt High Range Monitors depending on interpretation of Containment RMS Reports to the CRS that the Containment Environment Safety o Report status of the Containment Environment Function CANNOT BE MET due to Safety Function to the CRS. high containment pressure and temperature, and rising Containment RMS indications. I TERMINATING CUE: The JPM is complete when the CRS is informed of the status of the Containment Environment Safety Function. No further actions are required.
| |
| | |
| Appendix C Job Perfonnance Measure Form ES-C-l Worksheet Verification of Completion Job Perfonnance Measure Number: Sim-5 (Alt Path)
| |
| Applicant:
| |
| NRC Examiner:
| |
| Date Perfonned:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UNSAT ____________
| |
| Examiner's Signature and Date:
| |
| | |
| Appendix C Job Performance Measure Form ES-C-I APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. A transient resulting in a Reactor trip has occurred on Unit-I.
| |
| : 2. EOP-O, Post Trip Immediate Actions, has been implemented.
| |
| : 3. You are performing the duties of the CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to verify the Containment Environment Safety Function. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-6
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Sim-6 Task Title: Respond to a Fuel Handling incident in the Containment Task Number: 202.051 KIA
| |
| | |
| ==Reference:==
| |
| 036 AA1.01 (3.3,3.8)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: [;gI Classroom: D Simulator: [;gI Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. Unit-l is in Mode-6 with refueling operations in progress.
| |
| : 2. The FHS has informed the Control Room, via the RCRO, that a fuel assembly has been dropped in the reactor vessel. The FHS reports there is obvious damage to the fuel assembly.
| |
| : 3. You are performing the duties of an extra licensed operator.
| |
| Initiating Cue:
| |
| AOP-6D, FUEL HANDLING INCIDENT has been implemented. The CRS directs you to perform AOP-6D, Step V.A. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when the available Penetration Room Exhaust Filter trains have been placed in service. No further actions are required.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-6D, FUEL HANDLING INCIDENT Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. Reset simulator to IC-5
| |
| : 2. Place Containment Purge in operation.
| |
| : a. Open Purge Supply & Exhaust Valves
| |
| : b. Start Purge Exhaust Fan
| |
| : c. Secure 3 Cntmt Clrs, place the fourth in "SLOW"
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| 0 Locate AOP-6D, Section V, Step A. Same as element A. Control the Potential for a Radiological Release:
| |
| : 1. Isolate Containment Purge:
| |
| 0 a. Stop 11 CNTMT PURGE SUPPLY and EXHFANS .
| |
| Places I-HS-5289 & 5290 in STOP 0 I*HS;.5290 and verifies green lights illuminate Dl~HS-5289)
| |
| .., ...
| |
| o b. Close 11 CNTMTPURGKSUPP and EXH valves: .. .. Places I-HS-1410 & 1412 in CLOSE and verifies red lights extinguish and 0 I-HS-1410 green lights illuminate 0 I-HS-1412 CUE: No Containment Closure Deviations exist.
| |
| : 2. Restore any Containment Closure Deviations per NO-114, CONTAINMENT CLOSURE.
| |
| CAUTION: Mini-flow requirements for the SRW Pumps is 1700 GPM. Ensure operating SRW Pump differential pressure remains less than 87 PSID o 3. IF the SRW system is aligned for reduced load Determines step is NIA.
| |
| operation, THEN start a second SRW Pump o 4. Open the cke EMERGENCY OUT valves on ALL availableCoIltaipm~nt Air Coolers*:** ..
| |
| 0 I1.CACI-HS-1582 Places I-HS-1582, 1585, 1590 and 1593 in OPEN and verifies open 0 12 CACI-HS-1585 indications.
| |
| 0 13 CAC I-HS-1590 0 14 CAC I-HS-1593 Verifies SRW flow increases to all o 5. Verify SRW flow through all available CACs CACs
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Places I-HS-5299, 5300, 5301 and 5302, not running in FAST speed, to FAST and verifies all are running in fast.
| |
| Places I-HS-5293, 5295 and 5297 in START and verifies running indications.
| |
| o 8. Log the start time of the Iodine Filter Fans Logs start time for each fan
| |
| : 9. Start the available Penetration Room Exhaust Filter trains:
| |
| o a. Verify open 11 and 12 Penetration Room FILT ISOL DMPRS Verifies the Unit-l Dampers are o open o
| |
| Places I-HS-5283 and 5284 in START and verifies running indications.
| |
| : c. Log the start time of the Penetration Room Logs start time for each fan Exhaust Fans.
| |
| Terminating Cue: This JPM is complete when the available Penetration Room Exhaust Filter trains have been placed in service. No further actions are required.
| |
| I Time Stop: _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: Sim-6 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UNSAT - - - - - - - -
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. Unit-l is in Mode-6 with refueling operations in progress.
| |
| : 2. The FHS has informed the Control Room, via the RCRO, that a fuel assembly has been dropped in the reactor vessel. The FHS reports there is obvious damage to the fuel assembly.
| |
| : 3. You are performing the duties of an extra licensed operator.
| |
| Initiating Cue:
| |
| AOP-6D, FUEL HANDLING INCIDENT has been implemented. The CRS directs you to perform AOP-6D, Step V.A. Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-7
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Sim-7 (Alt Path)
| |
| Task Title: Recovery from Automatic Feedwater Isolation Task Number: 201.033 KIA
| |
| | |
| ==Reference:==
| |
| 059 A4.11 (3.1,3.3)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: ~
| |
| Classroom: D Simulator: [8J Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. A total loss of all feedwater has occurred on Unit 1.
| |
| : 2. The reactor is tripped and EOP-O is complete.
| |
| : 3. The CRS directed the RCPs be secured and a cooldown started prior to the EOP-3 brief.
| |
| : 4. You are performing the duties of the Unit 1 CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to establish natural circulation and cooldown the RCS per EOP-3, Step IV.G. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when SGIS is reset and a Condensate Booster Pump is started. No further actions are required.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. EOP-3, Loss of All Feedwater.
| |
| Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. Reset simulator to IC-24, 100% power
| |
| : 2. Insert Malfunctions AFW005, AFW001_01, AFW001_02 for the trip of 13, 11 and 12 AFW Pps
| |
| : 3. Trip the Reactor, the Main Feed Pumps and the RCPs, cooldown using the TBVs until just before SGIS actuates. Leave ADV controller output at ~ 100%. SGIS should actuate shortly after the candidate "assumes" the watch providing them with feedback indicating alternate actions are required.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start: - - -
| |
| Note to EVALUATOR: SGIS should actuate shortly after the candidate "assumes" the watch (simulator is placed in RUN) providing them with feedback indicating alternate actions are required.
| |
| o Locate EOP-3, Step IV.G. Same as element o PERFORM the following: Same as element CUE: Both S/G levels are currently -200 inches and Tcold is - 505 of and steady.
| |
| o 1. IF, at ANY time, BOTH S/G levels are less than Verifies S/G levels on 1C03 or
| |
| (-)350 inches OR TCOLD rises uncontrollably 5° F or greater, THEN initiate Once-Through-Cooling SPDS. Verifies TCOLD is not rising uncontrollably.
| |
| concurrently PER step J.
| |
| : 2. Block SGIS as follows:
| |
| CUE: SGIS has already actuated.
| |
| o a. WHEN the "SGIS A BLOCK PERMITTED" Determines step is NIA. Initiates alarm is received THEN block SGIS A: Alternate Actions.
| |
| ALTERNATE PATH CUE: SGIS actuated as a result of the cooldown.
| |
| o 2.1 IF SGIS actuates as a result of the cooldown Verifies loss of power has not AND the Non-Vital4KV buses are energized, occurred.
| |
| THEN reset the SGIS as follows:
| |
| o a. Place the COND BSTR PPs in PULL TO Places Condensate booster pump LOCK. control switches in PTL.
| |
| Places MSIV handswitches in SHUT. Places Feedwater isolation valve handswitches in SHUT.
| |
| Places 11 and 12 S/G SGIS keyswitches in BLOCK. Checks that Annunciators C59 and C60 (SGIS A (B) BLOCKED) actuate.
| |
| Places 11 and 12 S/G SGIS keyswitches in RESET. Checks that Annunciators G09 and G 10 (ACTUATION SYS SGIS A (B)
| |
| TRIPPED) are clear.
| |
| Same as element
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Same as element Same as element Terminating Cue: This JPM is complete when SGIS is reset and a Condensate Booster P~mp is I started. No further actions are required.
| |
| * Appendix C Job Performance Measure Form ES-C-I Verification of Completion Job Performance Measure Number: Sim-7 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| -- --------------------------
| |
| ..
| |
| Result: SAT _ _ _ _ __ UNSAT _ _ _ . . ._ _ __
| |
| Examiner's Signature and Date:
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. A total loss of all feedwater has occurred on Unit 1.
| |
| : 2. The reactor is tripped and EOP-O is complete.
| |
| : 3. The CRS directed the RCPs be secured and a cooldown started prior to the EOP-3 brief.
| |
| : 4. You are performing the duties of the Unit 1 CRO.
| |
| Initiating Cue:
| |
| The eRS directs you to establish natural circulation and cooldown the RCS per EOP-3, Step IV.G. Are there any questions? You may begin.
| |
| | |
| \
| |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: Sim-8
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Sim-8 Task Title: Transfer 11/17 4KV Bus Loads from lA DG to Offsite Power Source Task Number: 024.007 KIA
| |
| | |
| ==Reference:==
| |
| 064 A2.09 (3.1, 3.3)
| |
| Method of testing:
| |
| Simulated Performance: D Actual Performance: [8J Classroom: D Simulator: [8J Plant: D READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. 4KV Bus 11 was on its alternate feed, for maintenance on the normal feeder breaker, when the alternate feeder breaker tripped. The lA DG started, loaded on and is supplying 4KV Bus 11.
| |
| : 2. Maintenance has been completed on the normal feeder breaker.
| |
| : 3. You are performing the duties of the Unit 1 CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to Transfer 11/17 4KV Bus Loads from lA DG to Offsite Power Source in preparation to shut down the lA Diesel Generator. Are there any questions?
| |
| You may begin.
| |
| Task Standard:
| |
| This JPM is complete when offsite power is paralleled with the lA DG at approximately 2 MW and 4.0 KV. No further actions are required.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. OI-21A, lA Diesel Generator Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. Reset simulator to IC-24, 100% power
| |
| : 2. Override the lC18B Synchroscope to the 12 o'clock position
| |
| : 3. Override the ICl8B Synchroscope lights to "OFF"
| |
| : 4. Open the 11 4KV Bus normal feeder breaker causing the lA to start and load on the Bus
| |
| : 5. Stabilize plant and clear associated alarms
| |
| : 6. Place Alternate feeder breaker in PTL and place a "pinkie" on it to denote off normal position.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| CUE: General Precautions and Initial Conditions are met.
| |
| o Identify and locate OI-21A, Step 6.4.B.1. Same as element CUE: 114KV Bus normal feeder 152-1115 is expected to remain available.
| |
| o 1. CHECK the selected 11117 4KV Bus offsite power source is expected to remain available:
| |
| * 11 4KV BUS ALT FDR, 152-1101 Same as element OR
| |
| * 114KV BUS NORMAL FDR, 152-1115 o 2. VERIFY DC control power is available by observing the 11117 4KV Bus Normal OR Alternate Feeder breaker position light being illuminated at the Same as element control switch.
| |
| : 3. PLACE lA DG in the TRANSFER MODE by performing the following:
| |
| Da';.DEPRESS fA DG Same as element
| |
| . T,j-lIs-i707, P Inserts Sync Stick for l-CS-152-1703 at lC18A.
| |
| Same as element Same as element Same as element o f. REMOVE the Sync Stick from lA DG Same as element OUT BKR, l-CS-152-1703.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| CUE: CRS directs to close normal feeder.
| |
| Places sync stick in sync jack next to control switch for 152-1115.
| |
| CUE: Synchroscope and sync lights are operating.
| |
| o h. CHECK the associated Synchroscope Checks lC19 synchroscope.
| |
| AND Sync Lights are operating.
| |
| NOTE:
| |
| Offsite power voltage indication will be on the INCOMING voltmeter.
| |
| o i. ADJUST RUNNING VOLTS equal to Lowers running volts to match INCOMING VOLTS using lA DG AUTO incoming volts using l-CS-1704.
| |
| VOLT CONTR, l-CS-1704.
| |
| NOTE:
| |
| The Synchroscope works in the opposite direction from normal when lA DG is the RUNNING power source.
| |
| CUE: Synchroscope is running counterclockwise fast.
| |
| OJ. ADJUST 1A DO frequency so the synchroscope pointer is rotating slowly in the Adjusts synchroscope to slowly in FAST direction using lA DO SPEED fast direction.
| |
| CONTR,1-CS-1705.
| |
| JPM continued on next page
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| CAUTION:
| |
| To avoid improper paralleling, do NOT start OR stop any large loads on the 11/17 4KV Bus.
| |
| Closes l-CS-152-1115 at + 5° of the 12 o'clock position.
| |
| o 1. CHECK lA DG load is approximately 2.0 Same as element MW.
| |
| o m. REMOVE the Sync Stick AND Same as element RETURN to Home Base.
| |
| CUE: 11117 voltage is 4.2KV.
| |
| o 4. Monitor 11/17 4KV Bus voltage between 3.75 KV Verifies voltage in spec.
| |
| and 4.35 KV.
| |
| Terminating Cue: This JPM is complete when offsite power is paralleled with the lA DG, on 11 4KV Bus, at approximately 2 MW and 4.0 KV. No further actions are required.
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: Sim-8 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. 4KV Bus 11 was on its alternate feed, for maintenance on the normal feeder breaker, when the alternate feeder breaker tripped. The 1A DG started, loaded on and is supplying 4KV Bus 11.
| |
| : 2. Maintenance has been completed on the normal feeder breaker.
| |
| : 3. You are performing the duties of the Unit 1 CRO.
| |
| Initiating Cue:
| |
| The CRS directs you to Transfer 11117 4KV Bus Loads from IA DG to Offsite Power Source in preparation to shut down the lA Diesel Generator. Are there any questions?
| |
| You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-1
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Plant-l Task Title: Start 11 & 12 Containment Air Coolers Task Number: 032.049 KIA
| |
| | |
| ==Reference:==
| |
| 022 A4.01 (3.6, 3.6)
| |
| Method of testing:
| |
| Simulated Performance: ~ Actual Performance: D Classroom: D Simulator: D Plant: ~
| |
| READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.
| |
| : 2. You are performing the duties of the Unit-l ABO.
| |
| Initiating Cue:
| |
| You have just completed Step BK, RESTORE SWITCHGEAR ROOM VENTILATION which directs you to "Go to the 45' West Penetration Room to perform Step BL". Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when lC43 has been notified that 11 and 12 Containment Air Coolers are in high speed.
| |
| - '_ ....... _----------------------------------------'
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-9A, CONTROL ROOM EV ACUA nON AND SAFE SHUTDOWN DUE TO A SEVERE CONTROL ROOM FIRE.
| |
| Time Critical Task:
| |
| No Validation Time:
| |
| 20 minutes Simulator Setup:
| |
| : 1. None
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| * CUE: You have just completed Step BK, RESTORE SWITCHGEAR ROOM VENTILATION which directs you to "Go to the 45' West Penetration Room to perform Step BL".
| |
| D Locate AOP-9A, Step BL. Same as element.
| |
| D Candidate proceeds to the Unit-l 45' West Same as element Penetration Room CUE: When the LocallRemote Key is inserted and rotated each switch is in the LOCAL position.
| |
| : 1. Start 12 COlltainrnent AIr Cooler. in HIGH speed:
| |
| .D *. Place a Lo~~/Remote Key into 12 Containrnent~irJ'~ooler Load Contactorc:PaneJ Same as element handsWitch, 1-HS-5300AI, and unlock the ~ .
| |
| .l:~& hanciswitch. .*
| |
| D' h. Rotate the h'W;dswit~h toipCAL.. .. Same as element CUE: When the Local Control handswitch is positioned 12 CAC is running in HIGH.
| |
| o c. Place 12Containrnent i\irCooler Loc~li Same as element
| |
| /Handswitch, I-HS-5300A; to HIGH.4'*~-
| |
| D d. GO TO the 45' East Electrical Penetration Same as element Room.
| |
| CUE: When the LocallRemote Key is inserted and rotated each switch is in the LOCAL position.
| |
| : 2. StmtJ 1 Containrne~t Air Cooler in HIGH speed: ..
| |
| Df-a~ PlaceaLocrulRemotel(ey into 11 Containn1ent.Air~Cooler:LoadContactor Panel Same as element handswitch, 1(~H5*-5299Al, and Unlock the handswitch..
| |
| .
| |
| II ncb.
| |
| ..* : ( *.. ,
| |
| Rotate thehandsWltch
| |
| ... .
| |
| to LOCAL Same as element CUE: When the Local Control handswitch is positioned 11 CAC is running in HIGH.
| |
| | |
| CUE: Acknowledge communication that 11 and 12 Containment Air Coolers are in high speed using proper communication techniques.
| |
| : 3. Notify lC43 that 11 and 12 Containment Same as element Air Coolers are in high speed.
| |
| Terminating Cue: This JPM is complete when 11 and 12 Containment Air Coolers are in LOCAL and operating in high speed. per AOP-9A, Section BL
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: Plant-l Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UNSAT __________
| |
| Examiner's Signature and Date: _ _ _ _ _ _~ _______~ _______
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1) A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.
| |
| : 2) You are performing the duties of the Unit-l ABO.
| |
| Initiating Cue:
| |
| You have just completed Step BK, RESTORE SWITCHGEAR ROOM VENTILATION which directs you to "Go to the 45' West Penetration Room to perform Step BL". Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-2
| |
| | |
| * .
| |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Plant-2 Task Title: Initialize ADV Controllers and Align 11 and 12 ADVs to (1C43)
| |
| Task Number: 083.050 KJA
| |
| | |
| ==Reference:==
| |
| 068 AA1.21 (3.9,4.1)
| |
| Method of testing:
| |
| Simulated Performance: [gJ Actual Performance: D Classroom: D Simulator: D Plant: [gI READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.
| |
| : 2. You are performing the actions of the Unit-1 CRO.
| |
| Initiating Cue:
| |
| You have been directed by the Shift Manager to initialize the ADV controller-s and align 11 and 12 ADVs to 1C43, per AOP-9A steps Z and AA. Are there any questions? You may begin.
| |
| Task Standard:
| |
| This JPM is complete when both ADV Controllers are initialized and aligned for control at lC43.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-9A, Control Room Evacuation and Safe Shutdown due to a Severe Control Room Fire.
| |
| Time Critical Task:
| |
| No Validation Time:
| |
| 10 minutes Simulator Setup:
| |
| : 1. None
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start: - - -
| |
| * CUE: You have been directed by the Shift Manager to initialize the ADV controllers and align 11 and 12 Atmospheric Dump Valves to lC43, per AOP-9A steps Z and AA.
| |
| o Locates AOP-9A, Step Z. Same as element.
| |
| o Candidate proceeds to the Unit-1 45' Switchgear Same as element Room Note to Evaluator: ADV Controllers are initialized at lC43 CUE: ADV Controller output indicates zero.
| |
| ,,", " ;:
| |
| o 1. Place 11,,~V G9W~ I-HC-4056A, to SHUT. Same as element CUE: ADV Controller output indicates zero.
| |
| o 2. Ptace 12 ~y QONTfR, I-HC:"4056B, to SHUT. Same as element o Locates AOP-9A, Step AA. Same as element.
| |
| o 1. Place the following Handvalves to POSITION 2: Same as element NOTE TO EVALUATOR:
| |
| Opening ADV Hand Transfer Station enclosures will cause AFAS Status alarm in the Control Room. Have operator describe the transfer process.
| |
| NOTE TO EVALUATOR:
| |
| I-HV-3938A and 3938B are located in an enclosure marked "STEAM GENERATOR No.
| |
| 11 MAIN STEAM LINE ATMOS DUMP CONTROL VALVE l-CV-3938 CONTROL TRANSFER VALVES" CUE: l-HV-3938A is in position 2.
| |
| o JIADVA1lXSnut~own Control Transfer;l~FlV.;
| |
| {,9$8A "', ~. '" ' ' Same as element
| |
| ", ,
| |
| CUE: I-HV-3938B IS in position 2.
| |
| OllADV Same as element 393~B~
| |
| Continued on next page
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| NOTE TO EVALUATOR:
| |
| Opening ADV Hand Transfer Station enclosures will cause AFAS Status alarm in the Control Room. Have operator describe the transfer process.
| |
| NOTE TO EVALUATOR:
| |
| I-HV-3938A and 3938B are located in an enclosure marked "STEAM GENERATOR No.
| |
| 12 MAIN STEAM LINE ATMOS DUMP CONTROL VALVE l-CV-3939 CONTROL TRANSFER VALVES" CUE: I-HV-3939A is in position 2.
| |
| \~, >::""", ,
| |
| l:2:iA-DV: AuxShutdoWn 3939A ,,'
| |
| CQntrolTransfet, J-HV- '
| |
| ", ' '" , Same as element
| |
| [ ,',
| |
| CUE: I-HV-3939B is in position 2.
| |
| Same as element Terminating Cue: This JPM is complete when both ADV Controllers are initialized and aligned for control at IC43.
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Verification of Completion Job Performance Measure Number: Plant-2 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ . . _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| -- ..... ------------------- ------
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ ~_ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ _ __
| |
| Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| | |
| *.
| |
| .~
| |
| Appendix C Job Performance Measure Form ES-C-I APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1) A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.
| |
| : 2) You are performing the duties of the Unit-l CRO.
| |
| Initiating Cue:
| |
| You have been directed by the Shift Manager to initialize the ADV controllers and align 11 and 12 Atmospheric Dump Valves to lC43, per AOP-9A steps Z and AA.
| |
| Are there any questions? You may begin.
| |
| | |
| 2010 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-3
| |
| | |
| Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: Plant-3 Task Title: DeenergizelEnergize a 4KV Bus Task Number: 004.001 KIA
| |
| | |
| ==Reference:==
| |
| APE 068 AA1.31 (3.9,4.0)
| |
| Method of testing:
| |
| Simulated Performance: I2$J Actual Performance:
| |
| Classroom: D Simulator: D Plant: I2$J READ TO THE APPLICANT:
| |
| I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
| |
| Initial Conditions:
| |
| : 1. A severe fire has resulted in a control room evacuation and AOP-9A implementation.
| |
| : 2. You are performing the duties of the Unit 1 RO.
| |
| : 3. Step "AT" (OPEN THE FEEDER BREAKERS FOR 4KV BUS 11) is complete.
| |
| Initiating Cue:
| |
| You have been instructed to align the OC DG to 114 Kv bus per AOP-9A Step AU.
| |
| Task Standard:
| |
| This JPM is complete when the OC DG is aligned to the 114Kv bus per AOP-9A Step IV.AU.
| |
| | |
| Evaluation Criteria:
| |
| : 1. All critical steps completed (denoted by shading).
| |
| : 2. All sequential steps completed in order.
| |
| : 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
| |
| : 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
| |
| Required Materials:
| |
| : 1. Procedures and manuals normally available in the plant General
| |
| | |
| ==References:==
| |
| : 1. AOP-9A, CONTROL ROOM EVACUATION AND SAFE SHUTDOWN DUE TO A SEVERE CONTROL ROOM FIRE.
| |
| Time Critical Task:
| |
| No Validation Time:
| |
| 10 minutes Simulator Setup:
| |
| : 1. None
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| Time Start:
| |
| CUE: Give the operator a copy of AOP-9A.
| |
| o Locate AOP-9A, Step AU. Same as element.
| |
| D Candidate proceeds to the Unit-1 27' Switchgear Same as element Room CUE: ATTACHMENTS for determination of proper Electrical Safety PPE, along with PPE, are located at the Switchgear Room Tool Cabinet Candidate determines required PPE for:
| |
| D Candidate determines PPE required to complete
| |
| * Operation of a 4KV circuit breaker with enclosure doors assigned tasks closed
| |
| * Operation of 4KV disconnects NOTE TO EVALUATOR: Proper PPE for this task is: 100% Cotton Long Sleeve Shirt and Pants OR 100% Cotton short sleeve shirt and pants under FR Lab Coat. Discussion indicating candidate correctly determines PPE requirements is acceptable in lieu of donning the PPE for a simulation.
| |
| CUE: When the LocallRemote Key is inserted and rotated each switch is in the LOCAL position.
| |
| _ Z~f
| |
| : 1. Take, localconfrol?f qCPOJii>
| |
| 4KV bus,~,152..1106 VY pelf~mllpg
| |
| "":';~}i>,:+i,,:':j:>',~:~'" ___ ' __ - -,~,,, _>:~- ;~:ty
| |
| 'ir;lliSert Lo~t1.IIRent9te~Ke Same as element
| |
| ;!~:~;l~ Bre~~fJulligsWitcl1; ;i"
| |
| "'l-ns- 11 Q6A.
| |
| Db. Rotatethe hfi.Ildswitcht9' LOCAL. Same as element CUE: When taken to TRIP, I-HS-ll06B indicates trip.
| |
| Same as element CUE: When checked 152-1106 indicates open (red light is lit)
| |
| : d. Verify OC DO Output Breaker, 152-1106 is Checks Bkr indicating lights open.
| |
| | |
| ELEMENT STANDARD
| |
| (* = CRITICAL STEP)
| |
| NOTE TO EVALUATOR: Proper PPE for this task is: FR Long Sleeve Shirt and FR Pants OR FR Coveralls (minimum 4 cal) over 100% cotton short sleeve shirt and pants OR FR Lab Coat (minimum 4 cal) over 100% cotton shirt and pants. Discussion indicating candidate correctly determines PPE requirements is acceptable in lieu of donning the PPE for a simulation WARNING Improper operation of disconnects can result in serious injury. Keep body and head clear of the operating arc of the disconnect handle. Do NOT release handle prior to full travel. When the disconnect is opened, a very loud bang will be heard, and a switch position flag indication will be visible indicating disconnect position.
| |
| CUE: The keys insert into Disconnect 189-1106 and disconnect is unlocked.
| |
| C DO t~:4KVBU§IIDiscqrlt!~Pt~l-89..110~by per g!b~Joli~Wing:';;",~~:fc,~~~ .'
| |
| Same as element Cl Jl.;;triSe11t",uppl!t keys 1\ND unlock oe DOtQ' ..
| |
| ~""-
| |
| 7a~:*r~7D~coIlnect,t89;.il
| |
| ,,0: 7'00.'"" "<> ;""107"" :" ~ ,
| |
| 06 CUE: When operated, the disconnect indicates closed.
| |
| (J Close disconnect 189-1106. Same as element CUE: When the key is inserted and rotated, disconnect 189-1106 locks closed.
| |
| (J c. Insert lower key AND lock disconnect, 189 Same as element
| |
| . 1106, in the closed position.
| |
| CUE: Acknowledge communication that OC DG Output Bkr is in local and open and disconnect 189-1106 is closed, using proper communication techniques.
| |
| : 3. NotifY IC43 that OC Diesel Generator Output Breaker to 11 4KV Bus, 152-1106 is in local and tripped and the Same as element OC DG Disconnect to 4KV bus 11, 189-1106 is closed.
| |
| Terminating Cue: This JPM is complete when OC DG Output Bkr is in local and open and disconnect 189-1106 is closed. per AOP-9A, Section AU.
| |
| Time Stop
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Verification of Completion Job Performance Measure Number: Plant -3 Applicant:
| |
| NRC Examiner:
| |
| Date Performed:
| |
| Facility Evaluator:
| |
| Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Time to Complete:
| |
| Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
| |
| Result: SAT _ _ _ _ __ UN"SAT _ _ _ _ _ __
| |
| Examiner's Signature and Date:
| |
| | |
| Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
| |
| : 1. A severe fire has resulted in a control room evacuation and AOP-9A implementation.
| |
| : 2. Step "AT" (OPEN THE FEEDER BREAKERS FOR 4KV BUS 11) is complete.
| |
| : 3. You are performing the duties of the Unit 1 RO.
| |
| Initiating Cue:
| |
| You have been instructed to align the OC DG to 11 4 Kv bus per AOP-9A Step AU.
| |
| Do you have any questions? You may begin.
| |
| | |
| Appendix D Scenario Outline Form ES-D-1 Facility: CCNPP Scenario No.: 1 Op-Test No.: 2010 Examiners: Operators:
| |
| Initial Conditions:
| |
| U-1 is at 100% Qower MOC 10,885 MWD/MTU with long term steady state Qower history. U-2 at 100% Qower BOC.
| |
| Turnover:
| |
| 1A DIG removed from service and tagged out for scheduled maintenance (return in 12 hours}, with OC DIG aligned to 11 4kv bus (disconnect 189-1106 shut). 13 CBP is in PTL and is considered emergencll use onlll due to high vibrations. Instructions for the shift are to maintain Qower @ 100%.
| |
| Event Event Malf. No. Event Type*
| |
| No. Description RCS023 02 PZR Press Xmtr 100Y fails low RCS024 03 I (ATCIBOP) PZR Press Xmtr 102C fails low I
| |
| RCS025 02 TS (SRO) PZR Press Xmtr 103-1 fails low RCS026 02 PZR level XMTR I lOY fails high C (ALL) 2 RCS003 20 gpm RCS leak TS (SRO)
| |
| R(ATC/SRO) 3 Expeditious Downpower N (BOP) 4 HDV005 02 C (BOP/SRO) 12 Condensate Booster Pump Failure w/o auto start of standby 5 SWYD002 M (ALL) Loss of offsite power 6 CEDSOIO C (ATC) 2 Stuck CEA's 7 DG002 02 C (BOP) 1B DIG Auto Start Failure C (ALL) 8 4KVOOI 02 11 4kv bus electrical fault TS (SRO)
| |
| * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks: (bold)
| |
| * Commence boration due to 2 stuck CEA's
| |
| * Restore 4kv vital bus power with OC DIG
| |
| | |
| Op-Test No.: 2010 Scenario No.: _1_
| |
| SCENARIO OVERVIEW Res LEAK WITH STATION BLACKOUT Initial Conditions: U-l is at 100% power MOC 10,885 MWDIMTU with long term steady state power history. U-2 at 100% power BOC. lA DIG removed from service and tagged out for scheduled maintenance, with OC DIG aligned to 11 4kv bus (disconnect 189-1106 shut). 13 CBP is in PTL due to high vibes when running, it is considered emergency use only. Instructions for the shift are to maintain power @ 100%.
| |
| An instrument failure occurs on PZR reference leg which affects multiple pressure and level instruments. The crew will need to shift Pressure control from 11 OY to 11 OX or manually control PZR heaters. After a short delay the instrument line leak increases to 20 gpm leak which will prompt entry into AOP-2A, the leak is small enough to exercise AOP-2A completely and eventually lead to controlled SID.
| |
| During the down power a trip of 12 Condensate Booster Pump occurs without an auto start of standby CBP, the crew should implement AOP-3G Section V. After trip criteria is given out the CRS should direct bypassing Precoats and Demineralizers to maximize SGFP suction pressure. Next the crew should start 13 CBP.
| |
| When crew directs tripping the reactor, a loss of offsite power will occur. Concurrent with the trip a failure of IB DIG occurs which leaves U-I without either vita14kv bus. When the CRO performs Vital Auxiliaries safety function he will align the OC DIG to 11 4kv bus but an electrical fault will occur after aligned for 5 minutes. There will be a problem closing disconnect 189-1406 which will prevent aligning the OC DIG to14 4kv bus. Two stuck CEA's will not be able to be identified (due to electrical malfunctions) so boration by ATC in EOP-O is required. All safety functions will not be met due to loss of power effects. Numerous alternate actions will be required in EOP-O (eg. Isolate MSR's or MSIV's, PO operation of ADV's, align AFW Pumps, etc). The SRO should transition to EOP-8 due to RCS leakage and station blackout.
| |
| EOP-8 entry with Safety Function Assessment lAW Resource Assessment Table, with the following results RC-l Met, VA-2 Not Met, PIC-3 Met (PIC-4 Not Met ifSIAS actuates), HR-l Met (HR-2 Not Met if SIAS actuates), CE-l Met, RLEC-l Met.
| |
| The BOP should commence VA-2 immediately. Step B.2 will have him align OC to 14 bus (Electricians will have solved disconnect 189-1106 problem allowing alignment) or transition to VA 3 for SMECO. The ATC should commence RC-I.
| |
| When the crew has restored power to 14 4kv bus the scenario will end.
| |
| | |
| INSTRUCTOR SCENARIO INFORMATION
| |
| : 1. Reset to IC-24
| |
| : 2. Perform switch check.
| |
| : 3. Place simulator in RUN, advance charts and clear alarm display.
| |
| : 4. Place simulator in FREEZE.
| |
| : 5. Enter Malfunctions! Triggers
| |
| : a. CW002 01 at 0% as T-I on Fl
| |
| : b. PZR Press Xmtr IOOY fails low on T-l RCS023 02
| |
| : c. PZR Press Xmtr 102C fails low on T-l RCS02403
| |
| : d. PZR Press Xmtr 103-1 fails low on T-l RCS025 02
| |
| : e. PZR Level Xmtr 11 OY fails high on T-I RCS026 02
| |
| : f. RCS Leakage 20 gpm after 5 min delay on T-I RCS003
| |
| --g. Loss of 12 Condensate Booster Pump CDOO? 02 on F2
| |
| : h. CEA-Ol on bottom as T-2
| |
| : i. Loss of Offsite Power SWYD002 on T-2
| |
| --j. 2 Stuck CEA's CEDSO 10 at Time Zero
| |
| : k. 1B DG Auto-start Failure DG002 02 at Time Zero
| |
| : l. 11 4 KV bus electrical fault 4KVOOl 02 on F3
| |
| | |
| 6 Enter Panel Overides
| |
| : a. Shut disconnect 189-1106
| |
| : b. Place 13 CBP in PTL c Hang tags on lA DG
| |
| : d. Place pink abnonnal tags:
| |
| * 152-1406
| |
| * 152-2106
| |
| * 152-2406
| |
| * 13 CBP
| |
| : 7. Set simulator time to real time, then place simulator in RUN.
| |
| : 8. Give crew briefing.
| |
| : a. Present plant conditions: 100% load at MOe 10.885 MWDIMTU
| |
| : b. Power history: Long term steady state for past 39 days
| |
| : c. Equipment out of service:
| |
| * 1A DG removed from service for scheduled maintenance.
| |
| * OC DG aligned to 11 4 KV Bus
| |
| * 13 CBP is emergency use only due to high vibes
| |
| : d. Abnormal conditions: None
| |
| : e. Surveillances due: STP 0-90-1 in 3 hours
| |
| : f. Instructions for shift: Maintain power
| |
| : g. EOOS Risk: Low CDF 1.43 LERF 1.47
| |
| : h. Blowdown: Overboard at 100 gpm
| |
| : 9. Allow crew 3-5 minutes to acclimate themselves with their positions.
| |
| : 10. Instructions for the Booth Operator.
| |
| : a. Once the crew accepts the watch use Fl to initiate PZR Instrument Failures
| |
| : b. Once down power has begun for shutdown ofU-l use F2 to initiate failure of 12 Condensate Booster Pump.
| |
| : c. Approximately 5 minutes after crew aligns OC DG to 11 4KV bus use F3 to initiate electrical fault on 11 4KV Bus.
| |
| | |
| RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.
| |
| REQUEST RESPONSE
| |
| : 1. OWC contact 1M shop, Rad Con, Matrix Acknowledge request notification.
| |
| : 2. PWS or PPO check ESFAS panel. After 3 minutes, report SIAS Pressurizer Pressure Channel ZF is reading low and tripped.
| |
| : 3. PWS bypass ZD SIAS PP. After 5 minutes, give ESFAS door alarm, then bypass SIAS ZD, then clear door alarm.
| |
| : 4. TBO/EM Shop check 12 CBP & Breaker After 3 min report pump is stopped but nothing else looks abnormaL After 5 min report breaker is tripped with dropped flags.
| |
| : 5. ESO how long until offsite power restored No idea at this time but will call when we find out
| |
| : 6. TBO shut MSR isolation valves and panel Acknowledge request loaders to zero
| |
| : 7. ABO open ADV's locally After 2 minutes adjust ADV's to requested position
| |
| : 8. TBO open 189-1106 and shut 189-1406 After 2 minutes open 189-1106, after another 3 minutes report problems with shutting 189-1406.
| |
| : 9. OWC have EM shop check189-1406 After 10-15 min, shut 189-1406 and report
| |
| | |
| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 1 Page of ...1Q Event
| |
| | |
| == Description:==
| |
| Instrument line failure causes multi~le PZR level and ~ressure instrument failures.
| |
| I (ATC/BOP) TS (SRO)
| |
| Tim"
| |
| ... Applicant's Actions or Behavior RO A multinle alarms SRO Direct BOP to check if RPS calling for a trip and ATC to monitor primary BOP Review RPS indications and detennine RPS is not calling for a tri~
| |
| Monitors primary and recognizes PZR pressure is rising with no change in PZR ATC level or RCS temperature.
| |
| Reviews Alann Response Manual (ARM) and recommends shifting PZR Pressure BOP Control to 1 lOX and PZR heater low level cutout to X.
| |
| ATC Secures PZR BIU heaters usin2 individual handswitches or shifts PZR Pressure Direct shifting PZR pressure control to 11 OX and PZR heater low level cutout to SRO channel X.t BOP/SRO Review CNG OP-I.O 1-1 000 and/or system print to verify common tap analysis.
| |
| Review CNG OP-I.O 1-1 000 and/or Tech Specs for proper actions to comply with Tech specs.
| |
| SRO
| |
| * 3.3.l.A
| |
| * 3.3.4.A
| |
| * 3.3.4.C Announce Containment Sump alarm and review ARM. Drain containment sump BOP IAWOI-17.
| |
| !
| |
| ATC Recognize RCS leaka2e due to lowering PZR level with minimum letdown.
| |
| SRO Implement AOP-2A
| |
| | |
| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 2 Page .-£of j.Q Event
| |
| | |
| == Description:==
| |
| Instrument line leak increases to 20 912m RCS leak C (All) TS (SRO)
| |
| Position Applicant's Actions or Behavior Implement AOP-2A, make plant page announcement and announces trip criteria SRO and assigns to ATC.
| |
| Reports RCS leakage greater than capacity of one charging pump based on ATC lowering PZR level with LID at minimum.
| |
| Direct A TC to determine control PZR level lAW block step VLC SRO Direct BOP to check for SIG tube leakage lAW VLD Determines PZR level is being maintained with 15 inches of program. (No LID ATC isolation yet) and makes up to VCT as necessary BOP Determines no S/G tube leakage SRO Directs BOP to attempt to isolate leak JAW block step VLE BOP Isolate LID by shutting CVC-5I5 & 516 BOP Checks charging header for leakage (must go to single chg pp operation)
| |
| Determines leakage is inside containment and starts all CAe's in fast speed with BOP emergency outlet valves open.
| |
| Determines a trip is not necessary due to leakage less than capacity of I charging SRO pump now that LID is isolated.
| |
| Proceeds to Section V "RCS Leakage within capacity of 1 charging pump" Determines leakage greater than allowed by TS 3.4.13 and commences shutdown SRO ofU-1.
| |
| | |
| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 3 Page ~ of ...1.Q Event
| |
| | |
| == Description:==
| |
| Commence giant shutdown lAW OP-3.
| |
| R {ATC/SRO} N (BOP) lime Position Applicant's Actions or Behavior Directs down power lAW OP-3. IfSRO is concerned that leakage may increase SRO then a rapid power reduction IA W Appendix B is appropriate. If a rapid power reduction is not done then OP-3 section 6.4 should be used.
| |
| Borate RCS:
| |
| * Open Boric Acid Direct Makeup valve CVC-514-MOV
| |
| * Verify 2 charging pumps operating
| |
| * Start Boric Acid pump for 30 seconds and shuts CVC-SI4-MOV.
| |
| * Open RWT outlet to charging pump suction CVC-504-MOV
| |
| * Shut VCT outlet valve CVC-50l-MOV ATC Insert CEA's
| |
| * Selects Manual Sequential Control
| |
| * Insert Group S CEA's as necessary to support desired power reduction rate Initiate Boron Equalization
| |
| * Energize all PZR Backup heaters
| |
| * Adjust PZR Pressure controller 100X to "" 2200 psia BOP Open Hi Level dump valves for 11 & 12 LPFW Heaters BOP Adjust turbine load to maintain Tcold within 5°F of program Tcold
| |
| | |
| Appendix D Required Operator Actions Form ES~D~2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 4 Page .A. of J.Q Event
| |
| | |
| == Description:==
| |
| Loss of 12 Condensate Booster Puml2 without Auto Start of standb~ CSP.
| |
| C {BOP/SRO)
| |
| Time Position Applicant's Actions or Behavior BOP Announce alarm and reference ARM SRO Implement AOP-30 determines proper section is Section V SRO Announces trip criteria (S/O level approaching -40) and assigns to ATC SRO Direct BOP to maximize SOFP suction pressure Maximize SOFP suction pressure
| |
| * Place hotwel1 controller ill manual at 50%
| |
| BOP
| |
| * Open Condensate Precoat Sys bypass valve l-CD-581S-CV
| |
| * Open Condensate Demin Sys bypass valve l-CD-4439-MOV SRO Direct start of 13 CBP BOP Starts 13 CBP SRO Notifies Chemistry that Condensate Precoats & Demins were bypassed.
| |
| SRO Exits AOP-30
| |
| | |
| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 5 Page..§.. of J..Q Event
| |
| | |
| == Description:==
| |
| Reactor Tril2 with loss of Offsite Power with failure of 1B DG M (All)
| |
| Time Position Applicant's Actions or Behavior ATe: A Rel'lctoT i~ trinneli SRO Announces Reactor Trip and directs implementation of EOP-O ATC Perform Reactivitv control safety Function (See Event 6 for actions)
| |
| Ensure Turbine trip:
| |
| * Check Reactor tripped
| |
| * Depress both turbine trip pushbuttons
| |
| * Check Main Turbine Stop valves shut BOP 0 Shut MSIV's due to inability to determine stop valve position
| |
| * Check turbine speed drops
| |
| * Verify Turbine generator output breakers open
| |
| * Send TBO to ensure MS-4017 & 4018 MOV's shut BOP Verify Vital Auxiliaries (See Event 7 for actions)
| |
| ATC Verify Pressure and Inventory Safety Function BOP Verify Core & RCS Heat Removal Safety Function SRO When 11 4KV bus is lost direct ATC & BOP to reverify Safety Functions
| |
| | |
| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 6 Page..§.. of ..1Q Event
| |
| | |
| == Description:==
| |
| Two stuck CEA's on reactor triQ C (ATe) lillie Position Applicant's Actions or Behavior ATC Denress set of Manual Reactor Trio Pushhuttons ATC Check Reactor tripped by observing power & SUR ATC Announce U-l Reactor is tripped ATC Check CEA' s fully inserted Recognize 2 stuck CEA's and borates to 2300 ppm:
| |
| * Ensure VCT MIV valve CVC-512 shut
| |
| * Open BA Direct MIV valve CVC-514
| |
| * Opens BAST Gravity Feeds CVC-50S & 509 MOV's ATC
| |
| * Verify Makeup Modes Selector HS-210 in manual
| |
| * Start a Boric Acid Pump
| |
| * Shut VCT Outlet valve CVC-501-MOV
| |
| * Start all available charging pumps VerifY DI water M/U secured:
| |
| * II & 12 RCMU PP's secured ATC
| |
| * VCT Makeup valve CVC-512-CV is shut
| |
| * Recognize not in direct lineup and leaves RWT charging pump suction CVC-504 open.
| |
| ATC Reports Reactivity Control complete.
| |
| | |
| Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 7 PageLof .1Q Event
| |
| | |
| == Description:==
| |
| 1B DG Auto Start failure C (BOP}
| |
| Time Position Applicant's Actions or Behavior Checks 11 or 14 4KV bus is energized:
| |
| * Emergency start OC DG
| |
| * Attempts to start IB DG (pushes emergency start button)
| |
| BOP
| |
| * Verifies OC DG operating
| |
| * Verify shut OC DG discormect to 11 4 KV Bus 189-1106 shut
| |
| * Verify OC DG output breaker 152-0703 is shut
| |
| * Close 07 4 KV bus tie breaker 152-0701
| |
| * Insert sync stick and close OC DG to 11 4 KV Bus 152-1106 BOP Check all 125 VDC buses> 105 VDC BOP Check at least 3 120 VAC buses energized BOP Check either 1Y09 or 1Y 10 energized Verify CC flow to the RCP's BOP
| |
| * Starts 11 CC pp due to not getting start signal on shutdown sequencer BOP Dispatch ABO to verify switchgear room ventilation in service IA W OI-22H BOP Reports Vital Auxiliaries complete
| |
| | |
| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No,: 1 Event No.: _8_ Page Jt of -.1Q Event
| |
| | |
| == Description:==
| |
| Loss of 11 4KV bus (Station Blackout)
| |
| M (All) TS (SRO)
| |
| Position Applicant's Actions or Behavior SRO Direct A TC & BOP to re-verify Safety Functions ATC Reports Reactivity Control "Not Met" due to unable to borate due to loss of power BOP Reports Turbine trip complete Verify Pressure and Inventory Control
| |
| * Check PZR press between 1850-2300 psia, trending to 2250 psia ATC
| |
| * Check PZR level stabilizes between SO-ISO inches trending to 160 inches
| |
| * Ensure RCS subcooling >30°F Reports Pressure & Inventory as not met due to lowering PZR pressure and level Verify Vital Auxiliaries Safety Function
| |
| * Recognize II 4KV bus faulted and reports to SRO BOP
| |
| * Attempts to re-alignOC DG to 144 KV bus (OSO reports 189-1406 disconnect problem)
| |
| Reports Vital auxiliaries cannot be met due to no 4 KV bus & 1Y09 & to not energized Verify Core & RCS Heat Removal Safety Function
| |
| * Directs ABO to open ADV's manually (~40%) and reports position to SRO BOP
| |
| * Start 11 AFW pump due to loss of main feed water
| |
| * Trip SGFP and shut S/G Feed Isolations Reports Core & RCS Heat Removal as not met due to no operating RCP's Verify Containment Environment Safety Function
| |
| * Check pressure < 0.7 psig BOP/ATC
| |
| * Check temperature < 120°F
| |
| * Check radiation monitor alarms clear with no unexplained rise Reports Containment Environment as not met due to inability to assess due to power loss Verify Rad Level External to Containment Safety Function
| |
| * Check RMS alarms clear with no unexplained rise BOP/ATC
| |
| * Secures S/G Blowdown due to inability to assess Reports Rad Levels External to Containment as not met due to inability to assess SRO Brief crew on status of all Safety Functions & Actuations References Diagnostic Flowchart and Implements EOP-S due to RCS leak with SRO Station Blackout
| |
| | |
| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 8 (cont) Page JL of -.1Q Event
| |
| | |
| == Description:==
| |
| EOP-8 EntrY due to to ReS leakage with station Balckout Time Position Applicant's Actions or Behavior
| |
| ! ~R() Oirect A TC to " RCP trio stMepv SRO Contact Chemistry to monitor S/G activity and Containment Hydrogen Levels SRO Direct ATC & BOP to identify success paths per Resource Assessment Table Recommends RC-1 Met due to no 4KV buses with WRNI <10.4 and negative ATC SUR Recommends V A*3 Not Me due to no DG available and no 4KV buses (May BOP recommend V A*2 Not Met due to OC DG available but not able to be loaded on a bus currentlv with no 4 KV buses)t BOP Commences working on VA-3 (or VA*2) immediately Recommends PIC-3 Met due to no 4KV buses, No SIAS, subcooled margin>
| |
| ATC 25°F and RVLMS indicates core is covered. (If SIAS has actuates then PIC-4 Not Met and starts working immediately)
| |
| RecommendsHR*1 Met due to No SIAS and AFW operating to keep subcooled ATC margin> 25°F and RVLMS indicates core is covered (IfSIAS actuates then SRO must evaluate and determine HR*2 Not Met since ATC would be working PICA)
| |
| Recommends CE-I Met due to containment pressure < 2.8 psig and no ATC unexplained radiation alarms in containment with temperature <220°F Recommends RLEC-I Met due to normal rad levels and no alarms with ATC unexplained rise Performs V A-3 Appendix:
| |
| !
| |
| * Align Electrical System for power restoration (This step is similar in both BOP VA*2 & VA-3)
| |
| * When report comes in that E&C has repaired disconnect 189-1406, recommend to SRO to switch to V A-2 Performs PIC-l Appendix ATC
| |
| * Verify a charging path is available, so when power is restored then charging flow can be restored When report comes in that E&C has repaired disconnect 189-1406, direct BOP to SRO switch to VA*2 and align OC DG to 144 KV bus
| |
| | |
| Appendix D Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: 1 Event No.: 8 (cont) Page.1.Q. of J.Q Event
| |
| | |
| == Description:==
| |
| EOP-8 Ent[Y due to to ReS leakage with station Balckout
| |
| .. Applicant's Actions or Behavior Performs V A-2 Appendix:
| |
| * Align electrical systems for power restoration
| |
| * Verifies 07 4KV Bus 152-0704 breaker is open BOP
| |
| * Verify OC DG output breaker 152-0703 is sbut
| |
| * Verifies OC DG disconnect to 144 KV bus is 189-1406 is shut
| |
| * Close 07 4 KV Bus Tie breaker 152-0701
| |
| * Insert sync stick and close OC DG to 14 4KV bus breaker 152-1406 Tech Specs not met for event:
| |
| * 3.8.l.A, B, D, E, G, H, I, K SRO
| |
| * 3.0.3
| |
| * 3.8.9.A
| |
| | |
| Appendix D Scenario Outline Form ES-D-1 Facility: CCNPP Scenario No.: 2 Op-Test No.: 2010 Examiners: Operators:
| |
| Initial Conditions:
| |
| U-1 is at 100% Qower EOC, 15,500 MWD/MTU with long term stead:i state Qower histo!y. U-2 at 100% Qower MOC Turnover:
| |
| 11 HPSI PumQ is removed from service for scheduled maintenance {return in 3 hours}. 13 CCW Qum!2 is OOS for work on 3 l2uml2 disconnect. 13 CBP is for mergenc~ use onl~ due to high vibrations.
| |
| rll Instructions for the shift is to remain at 100% 120wer.
| |
| Event Event Malt. No. Event Type*
| |
| No. Description 1 CNTMOOI 04 TS (SRO) 14 Containment Air Cooler failure C (BOP/SRO) 2 TG017 Turbine vibration on bearing 4 R(ATC) 3 Various C (ATC) l-CVC-S14-MOV breaker failure 4 TGOOI M(ALL) Turbine trip RPSOOS, C (ATC) 5 RPSOO6& RPS & Manual Trip Pushbutton failure DSS failure TS (SRO) 6 CCW00201 C (BOP) 11 Component Cooling Pump failure 7 RCS022 M(ALL) Pressurizer Safety Valve fails to reseat (leak on top ofPZR) 8 ESFAOOI 02 I (BOP) SIAS B failure
| |
| * (N)ormal. (R)eactivity, (I}nstrument. (C)omponent, (M)ajor Critical Tasks:
| |
| * Trip Reactor from electrical panels due to A TWS
| |
| * Trip all RCP's due to no cooling
| |
| * Manually actuate SIAS B
| |
| | |
| Op-Test No.: 2010 Scenario No.:
| |
| SCENARIO OVERVIEW ATWS WITH PZR SAFETY VALVE LEAKAGE Initial Conditions: U-I is at 100% power EOC 15,500 MWD/MTU with long term steady state power history. U-2 at 100% power MOC. 11 HPSI pump is removed from service for scheduled maintenance and will be returned in 3 hours. 13 CCW pump is OOS for work on480V disconnect. Instructions for the shift are to maintain power @ 100%.
| |
| Scenario starts with a trip of 14 Containment Air Cooler which requires entry in TS 3.6.6.C.
| |
| Also consideration should be made to start 13 CAC to maintain containment cooling.
| |
| Turbine bearing #4 vibration problem develops, causing entry into AOP-7E. Crew must keep track oftime when vibration exceeds 10 mils (due to 15 minute limit for trip criteria). Vibration stabilizes at approximately 11 mils which will require a rapid downpower to attempt to lower vibration prior to exceeding 10 mils for 15 minutes.
| |
| When lining up for rapid downpower l-CVC-514-MOV will fail due to breaker trip requiring the crew to use a non-preferred method ofboration. Reducing power will have some affect on turbine vibration but not enough to avoid a trip. When crew is within 2 minutes of trip criteria the turbine will trip on its own due to vibration related problems.
| |
| When the turbine trips, RPS will be calling for the reactor to trip but due to a failure, both auto trip (including DSS) and manual pushbuttons fail. EOP-O ATWS actions (opening breakers at ICI8 & lC19) will trip the reactor.
| |
| Once the reactor is tripped a PZR safety valve will start to leak due to overpressure and 11 Component Cooling Pump will fail. The BOP attempts to start 12 CCW pump to provide cooling to RCP,s, when it fails he must secure all RCP's. The ATC will shut PORV block valves due to flow readings for both PORV's & Safety Valves. When RCS pressure lowers to SIAS setpoint the ATC should verify SIAS and at that time manually initiate SIAS B and secure 2 RCP's. Pressure and Inventory will be reported as Not Met due to low PZR pressure and high PZR level. The CRO should recognize trends on containment pressure and temperature and take alternate action to increase cooling and eventually call Containment Environment as Not Met.
| |
| CRS will follow EOP-O flow chart and transition to EOP-5.
| |
| In EOP-S, the ATC will shut letdown isolation valves and verify PORV block valves shut in step IV.F Leak Isolation. The crew will also commence a cooldown using S/G's and also depressurize in an attempt to lower the leak rate. The scenario will end when cooldown is commenced.
| |
| | |
| INSTRUCTOR SCENARIO INFORMATION
| |
| : 1. Reset to IC-24
| |
| : 2. Perform switch check.
| |
| : 3. Place simulator in RUN, advance charts and clear alarm display.
| |
| : 4. Place simulator in FREEZE.
| |
| : 5. Enter Malfunctions/ Triggers
| |
| : a. 14 Containment Air Cooler Failure CNTMOO I 04 on Fl
| |
| : b. Main Turbine Bearing 4 high vibrations TGO 17 (7-11.5) over 5 min on F2
| |
| : c. CVC-514-MOV H/S to Open as T-l
| |
| : d. CVC-514-MOV HIS to close on T-l
| |
| : e. CVC-514-MOV H/S lights to out on T-l
| |
| : f. Main Turbine trip TG017 on F3
| |
| --g. RPS Failure to trip Reactor RPS005 & RPS006 at Time Zero
| |
| : h. DSS failure to trip Reactor ESFAS????
| |
| : 1. CEA 0 I on bottom as T-2
| |
| --j. 11 component cooling pump failure CCW002 01 on T-2
| |
| : k. Pressurizer safety valve fails to resl~at RCS022 (0-25) over 5 min on T-2
| |
| : 1. SIAS B failure ESFAOO 1 02 at Time Zero
| |
| | |
| 6 Enter Panel Overides
| |
| : a. Place 11 HPSI Pump in PTL with yellow tag
| |
| : b. Override alarm H-17 "11 HPSI PP SIAS Block Auto Start" and place red dot on window
| |
| : c. Place 13 CCW pump in PTL with yellow tag
| |
| : d. Override 12CCW pump in PTL, with green off light lit.
| |
| : 7. Set simulator time to real time, then place simulator in RUN.
| |
| : 8. Give crew briefing.
| |
| : a. Present plant conditions: 100% load at EOC 14.885 MWD/MTU
| |
| : b. Power history: Long term steady state for past 16 days
| |
| : c. Equipment out of service:
| |
| * 11 HPSI removed from service for scheduled maintenance.
| |
| * 13 CCW Pump OOS for work on 480V disconnect
| |
| : d. Abnormal conditions: None
| |
| : e. Surveillances due: None
| |
| : f. Instructions for shift: Maintain power
| |
| : g. EOOS Risk: Low CDF 1.76 LERF 1.79
| |
| : h. Blowdown: Overboard at 100 gpm
| |
| : 9. Allow crew 3-5 minutes to acclimate themselves with their positions.
| |
| : 10. Instructions for the Booth Operator.
| |
| : a. Once the crew accepts the watch use Fl to initiate trip of 14 CAC.
| |
| : b. Once Tech specs reference and brief is complete then use F2 to initiate high vibrations on Main turbine bearing #4.
| |
| : c. After crew lowers Reactor power <90% use F3 to trip Main Turbine.
| |
| | |
| RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.
| |
| REQUEST RESPONSE
| |
| : 1. OWC contact EM shop, Matrix notification. Acknowledge request
| |
| : 2. TBO check 14 CAC breaker. After 3 minutes, report breaker is tripped but otherwise looks normal.
| |
| : 3. TBO man panel unloaders for down power.. Acknowledge request.
| |
| : 4. ABO check CVC-514-MOV valve & breaker After 3 min report breaker appears tripped, after another 3 minutes report valve looks shut.
| |
| : 5. OWC notify EM shop about CVC-514-MOV Acknowledge request breaker trip
| |
| : 6. ABO check 11 CC pump After 3 minutes report pump is not running but otherwise appears normal
| |
| : 7. OWC contact EM shop about 11 CC pump Acknowledge request trip
| |
| | |
| Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: Event No.: _1_ Page of 10 Event
| |
| | |
| == Description:==
| |
| 14 Containment Air Cooler (CAC) fails TS (SRO)
| |
| Time Position Applicant's Actions or Behavior BOP Announce alarm R-4 "U-l 480V ESF UN Trip" ATC Announce plant computer alarm for 14 CAC tripped i
| |
| SRO Reference Tech Specs and determine not meeting 3.6.6.C BOP Align Service Water to 13 CAC lAW OI-5A using I-HS-1591 BOP Start 13 CAC lAW OI-SA using I-HS-530 I BOP Secure Service Waterto 14 CAC using OI-5A using I-HS-1594 i
| |
| i
| |
| | |
| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: _ 2_ Event No.: _2_ Page..£ of 10 Event
| |
| | |
| == Description:==
| |
| High vibration on bearing #4 of Main Turbine C (BOP/SRO) R (ATC)
| |
| Time Position Applicant's Actions or Behavior BOP Announce alarm B-3 "Turbine Vibration" Verify alarm valid by observing both X & Y probes reading high, and adjacent BOP bearing also elevated Implement AOP-7E "Main Turbine Malfunctions" and make plant page SRO announcement Announce trip criteria" 12 mils or 10 mils for> 15 minutes", and assign trip SRO criteria to the BOP SRO Assign block step V.A to BOP Coordinate with the TBO to get Condenser Vacuum Breaker breaker 52-11618 BOP shut Coordinate with the Electrical System Operator to get reactive load reduced to BOP zero. When ESO gives permission then lowers Main Generator output voltage until VAR's read zero.
| |
| Direct ATC & BOP to perform rapid down power to reduce turbine loading to SRO reduce vibration Commences rapid down power procedure lAW OP-3 (See Event 3 for CVC-514 ATC failure actions)
| |
| Places all PZR heater handswitches to ON, lowers setpoint of on service PZR ATC Pressure Controller PIC-I00X to 2200 psia to equalize boron When RCS Tcold lowers to <537° F, lowers turbine load to maintain RCS Tcold within 5° F of program Tcold (5° is upper limit, should be maintained with 2° F):
| |
| BOP
| |
| * Uses manual Turbine Load Set handswitch l-CS-80
| |
| * Uses keyboard to set 3% minute ramp rate and puts turbine in auto After ensuring BOP is ready, insert CEA's as follows:
| |
| ATC
| |
| * Selects Manual Sequential pushbutton at I C05
| |
| * Moves CEA Control Handswitch to lower position while observing multiple indications of Reactor Power.
| |
| | |
| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: Event No.: _3_ Page .l.. of 10 Event
| |
| | |
| == Description:==
| |
| Failure of CVC-514-MOV (Boric Acid Pump discharge to Charging Pump suction)
| |
| C (ATC)
| |
| ~ Applicant's Actions or Behavior ATC h for CVC-514-MOV to open Recognizes indicating lights for CYC-514-MOY go out prior to open indication, ATC reports to SRO it appears MOY breaker has tripped.
| |
| Transitions to alternate method for borating to RCS:
| |
| * Opens 11 or 12 BAST Gravity Feed MOY's
| |
| * When full open indication for Gravity Feed, shuts YCT outlet CVC-501 ATC
| |
| * Starts a second Charging Pump (12 or 13)
| |
| * After 30 seconds, Opens R WT outlet to Charging Pump Suction CYC-504-MOY
| |
| * When full open indication of CYC-504-MOV, then shuts Gravity Feed MOY's ATC Rest of down power procedure actions are included with Event 2
| |
| | |
| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: Event No.: Page ..1. of 10 Event
| |
| | |
| == Description:==
| |
| Main turbine trip due to vibration induced event M (All)
| |
| Time Position Applicant's Actions or Behavior Recognize and announce "Main Turbine trip" BOP
| |
| * BOP should verify vibration did not drastically rise >50mils SRO Order A TC to trip Reactor and implement EOP-O ATC Pushes Reactor trip pushbuttons on 1C05 ATC Recognize A TWS and announce to SRO (A TWS actions listed in Event 5)
| |
| Ensure Turbine Trip:
| |
| * Ensure Reactor tripped, then depress both Turbine Trip buttons
| |
| * Check Main Turbine Stop Valves shut BOP
| |
| * Check Turbine speed drops
| |
| * Verify Turbine Generator breakers open
| |
| * Ensure MSR 2nd stage MOV's shut Reports Turbine Trip is complete Verify Vital Auxiliaries:
| |
| * Check 11 or 14 4KV Bus energized BOP
| |
| * If either 11 or 14 4 K V Bus de-energized then start OC DG
| |
| * Check 125VDC & l20VAC buses energized
| |
| * Check either 1Y09 or 1Y 10 energized
| |
| * Verify Component Cooling flow to RCP's (See Event 6 for actions)
| |
| | |
| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: _2_ Event No.: 5 Page ~ of 10 Event
| |
| | |
| == Description:==
| |
| RPS, DSS, & Manual Pushbutton Reactor Trip Failure C (ATC) TS (SRO)
| |
| Time Position Applicant's Actions or Behavior ATC Depress ONE set of Manual REACTOR TRIP buttons.
| |
| Recognize Reactor NOT tripped:
| |
| * Open t2A 480V BUS FDR
| |
| * Open 12A-12B 480V BUS TIE
| |
| * Open 13A 480V BUS FDR
| |
| * Open 13A-13B 480V BUS TIE ATC Checks Reactor tripped by observing power indications at ICt5 Energizes 12A & 13A 480V Buses by shutting the two breakers that were originally shut:
| |
| * 12A 480V BUS FDR
| |
| * 13A 480V BUS FDR ATC Checks to ensure all CEA's inserted Verifies no DI water aligned as makeup to the RCS:
| |
| ATC
| |
| * 11 and 12 RC MIU PPs are secured
| |
| * VCT M/u valve, l-CVC-512-CV, is shut ATC Reports Reactivity control Complete SRO Tech Spec 3.3.3.A, B, C, D, E (B only until trip, E until all TCB's opened)
| |
| | |
| Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: _2_ Event No.: _6_ Page ~of 1Q.
| |
| Event
| |
| | |
| == Description:==
| |
| 11 Component Cooling pump failure C(BOP)
| |
| Position Applicant's Actions or Behavior Verify Component Cooling flow to the RCP's:
| |
| BOP
| |
| * Recognize 11 CCW pump not running
| |
| * Attempts to start 11 and 12 CCW pump Component Cooling flow cannot be verified to RCP's:
| |
| BOP
| |
| * Secures all RCP's using HIS's at lC06 Reports Vital Auxiliaries cannot be met due to no Component Cooling Water BOP supplied to RCP's
| |
| | |
| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: Event No.: _7_ Page of J.Q.
| |
| Event
| |
| | |
| == Description:==
| |
| Pressurizer Safety Valve fails to reseat (RCS leak on top of PZR)
| |
| M(AII)
| |
| II Applicant's Actions or Behavior Verify Pressure and Inventory Control:
| |
| * Check pressure 185()-2300 psia trending to 2250 psia
| |
| * Verifies all PZR heaters on and spray flow is secured (No RCP's)
| |
| * IfPZR press <2300 psia and PORV cannot be verified closed (acoustic monitor indication) then:
| |
| o Shut PORV Block valve RC-403-MOV o Places PORV 402 Override in "Override to close"
| |
| * IfPZR Press lowers <1725 psia, then verify SIAS (see event 8)
| |
| ATC
| |
| * Verifies RCP's secured (BOP secured for no CCW pump)
| |
| * Checks PZR level bl~tween 80 & 180 inches, trending to 160 inches o If PZR levd low and trending lower, then isolate letdown o IfPZR level high and trending higher then secure charging pumps one at a time (Discuss with SRO prior to securing final pump)
| |
| * Ensure RCS subcooling >30° F
| |
| * Reports RCS Pressure & Inventory not met due to low RCS pressure Verify Core & RCS Heat Removal safety Function
| |
| * Verify TBV's or ADV's maintaining SIG press 850-920 psia and Tcold 525-535° F
| |
| * Verify at least 1 SIG available for heat removal:
| |
| o SIG level (-) 170 - (+)30 inches BOP o Main or Auxiliary Feed operating o Tcold >525° F
| |
| * Check at least one RCP in loop with available SIG
| |
| * If any RCP's operating ensure RCS 6.T <10° F
| |
| * Reports Core & RCS Heat Removal cannot be met due to no operating RCP's.
| |
| | |
| Verify Containment Environment Safety Function:
| |
| * Check containment pressure <0.7 psig:
| |
| 0 If>0.7 psig then verify all CAC's running with max SRW flow 0 If>2.8 psig then verify CIS & SIAS (not expected at this time)
| |
| BOP/ATC
| |
| * Check containment temp < 1200 F 0 If> 1200 F then verify all CAC's running with max SRW flow
| |
| * Check containment radiation alarms clear with no unexplained rise:
| |
| 0 If any alarms received then start all IRU's (not expected)
| |
| * Reports Containment Environment Safety Function as Not Met due to containment pressure negative trend Verify Radiation Levels External to Containment Safety Function:
| |
| BOP/ATC
| |
| * Check RMS alarms clear with no unexplained rise
| |
| * Report Radiation Levels External to Containment is complete Hold crew briefing covering:
| |
| * V A not met due to no operating CC pumps SRO
| |
| * PIC not met due to low RCS press (maybe high PZR level)
| |
| * HR not met due to no operating RCP's
| |
| * CE not met due to containment pressure trends
| |
| * SIAS actuation (SlAB B failure)
| |
| SRO Review Diagnostic flowchart and determines EOP-5 is correct path SRO Implements EOP-5, hold entry brief, assigns block steps to ATC & BOP Block step D "Monitor Depressurization" ATC
| |
| * Uses Attachment 10 to verify HPSI flow is consistent with pump curve Block Step F "Attempt Leak Isolation":
| |
| * Verifies LID isolation valves shut (CVC-5l5 & 516)
| |
| * Checks for PORV le:akage (leakage is present from RV) 0 Verifies PORV Block valve RC-403-MOV shut 0 Verifies PORV 402 Override handswitch in "Override to Close" BOP
| |
| * Shut RCS Sample valve PS-5464-CV
| |
| * Shut Reactor Vessel Vent valves RC-l03 & 104-SV's
| |
| * Shut PZR vent valv(:s RC-I05 & 106-SV's
| |
| * Checks no leakage into CC system
| |
| * Verifies leak is inside containment
| |
| | |
| Block Step G "Maintain Containment Environment":
| |
| * If containment pressure >2.8 psig then verify SIAS & CIS
| |
| * If CIS actuated then ensure all RCP's secured BOP
| |
| * Contact TBO to verify SRW pump room ventilation in service
| |
| * If containment pressure >4.25 psig the verify CSAS (not expected)
| |
| * Direct Chemistry to place Hydrogen Monitors in service
| |
| * Verify all CAC's, at least one Cavity Cooling, at least one CEDM Cooler, and all PZR Vent fans are running Block Step H "Commence Boration":
| |
| * Verify SIAS actuated, then:
| |
| 0 VCT Makeup CVC-512-CV shut 0 Boric Acid Direct Makeup CVC-514 open ATC 0 BAST Gravity Feed valves CVC-508 & 509-MOV's open 0 All available Boric Acid pumps running 0 VCT Outlet valve CVC-50 I-MOV is shut 0 All available Charging pumps operating 0 Record boration start time and BAST levels Block step I "Commence Cooldown" BOP
| |
| * Block SGIS when Block Permitted alarms are received
| |
| * Commence cooldown to < 3000 Fusing TBV's (if available, may be lost due to SIAS causing vacuum to go away) or ADV's ERPIP call Alert H.A.5.1.2 due to excessive RCS leakage> capacity of charging SRO pumps
| |
| | |
| Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: _ 2_ Event No.: _8_ Page ..1Q.. of J.Q Event
| |
| | |
| == Description:==
| |
| SIAS B failure (with 11 HPSI tagged out for maintenance)
| |
| I(ATC)
| |
| .
| |
| I~ SROIBOP/ATe Applicant's Actions or Behavior Recognizes SIAS actuation and announces to the crew ATe SIAS actuated due to low ReS pressure therefore ATe should verify SIAS Verify SIAS:
| |
| * Verify SIAS valid by checking RCS pressure
| |
| * Verifies 11 & 13 HPSI pumps running 0 Recognizes11 HPSI tagged out & 13 HPSI not running ATe 0 Reports failure of SIAS B to SRO 0 Pushes SIAS B manual actuation pushbutton on lCI0 0 Verifies 13 HPSI pump running
| |
| * Verifies all 8 HPSI header MOV's open
| |
| * Reports SIAS verified to SRO
| |
| | |
| Appendix 0 Scenario Outline Form ES-O-1 Facility: CCNPP Scenario No.: 4 Op-Test No.: 2010 Examiners: Operators:
| |
| Initial Conditions:
| |
| U-1 is at 100% power MOC 10,885 MWD/MTU long term steady state, U-2 is at 100% power EOC.
| |
| Turnover:
| |
| 13 4kv bus aligned to alternate feed while normal feed breaker 152-1311 is OOS for scheduled maintenance.
| |
| Event Event Malf. No. Event Type*
| |
| No. Description C (SRO/BOP) 1 MS009 01 TBV 3940 fails open R(ATC) 2 480vOOl 04 C (SRO/BOP) 12B 480V bus failure 3 CVCS003 01 C (ATC) 11 Chargin~ Pump coupling failure I (BOP) 4 ESFA009_02 Spurious CIS B Actuation TS (SRO) 5 CVCS009 I (ATC) VCT level transmitter fails high 6 CCWOO3 C (All) Component Cooling leak in the containment M (All) 7 MS002 02 12 S/G tube rupture TS (SRO)
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| * (N)ormal (R)eactivity, (I)nstrument (C)omponent (M)ajor Critical Tasks:
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| * Secure RCP's prior to exceeding temp limits.
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| * Isolate S/G in EOP-6
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| * Depressurize RCS to minimize leakage
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| Op-Test No.: 2010 Scenario No.: _4_
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| SCENARIO OVERVIEW CC LEAK & S/G TUBE RUPTURE Initial Conditions: U-l is at 100% power MOC 10,885 MWDIMTU long term steady state, U-2 is at 100% power EOC. 13 4kv bus aligned to alternate feed while normal feed breaker 152-1311 is OOS for scheduled maintenance.
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| The scenario starts with a failure ofTBV 3940 causing an overcooling event requiring entry into AOP-7K. Crew must control power <100% by unloading turbine and inserting CEA's, then isolate the affected TBV.
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| A loss of 12B 480V bus occurs next. The crew will implement AOP-7I, tying MCC-l 06 to MCC 116 and verifying pumps and fans running.
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| When 11 charging pump coupling fails proper alarm response (F-46) should have A TC start 12 or 13 charging pump prior to losing letdown due to high temp. After another charging pump is started the crew should consult OI-2A for proper positioning of charging pump selector switch.
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| A spurious actuation of CIS B isolates component cooling to RCP's. When crew verifies containment pressure <2.8 psig they should reset CIS B IA W alarm manual using EOP Attachments.
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| When CIS is reset the crew should reinitiate cooling to RCP's by opening CC isolation valves. When component cooling is re-established to the containment a slow leak develops in the component cooling system.
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| VCT level transmitter failing high causes letdown to be diverted to waste processing, ATC will position Diversion valve from Auto to VCT which should align system back to normal.
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| When component cooling is re-established to the containment a leak develops in the component cooling system. AOP-7C should be implemented which leads to isolating the leak which will require tripping reactor and securing all RCP's after Reactivity Control is completed.
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| When the reactor trips EOP-O will be implemented and after reactivity control is complete the ATC will secure all RCP's. Trip transient will also cause a S/G tube rupture in 12 S/G which will force alternate actions for both Pressure and Inventory Control. At completion of EOP-O the SRO should select EOP-6 using EOP-O diagnostic flow chart.
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| When EOP-6 is entered the ATC should be assigned monitoring RCS Depressurization which will align Safety Injection in preparations for blocking SIAS. RCS boration will also be started and a rapid cooldown of the RCS to <515 Thot will be commenced. BOP should recognize that TBV 3940 is isolated so controller manual output signal must be 25% higher for same cooldown.
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| Once Thot <515, the BOP should slow the rate of cooldown and commence isolating 12 S/G lAW EOP-6. When 12 S/G is isolated the scenario will end.
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| INSTRUCTOR SCENARIO INFORMATION
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| : 1. Resetto IC-17
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| : 2. Perform switch check.
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| : 3. Place simulator in RUN, advance charts and clear alarm display.
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| : a. Ensure 12 CEDM Fan running
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| : b. Ensure only 11 & 12 CAR's operating (secure 14 CAR)
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| : c. Lower VCT level to approximately 95-97"
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| : d. Align 13 4KV bus to alternate feed
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| : 4. Place simulator in FREEZE.
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| : 5. Enter Malfunctionsl Triggers
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| : a. TBV 3940 fails open MS009 on Fl
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| : b. 12B 480V Bus failure 480vOO 1 040n F2
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| : c. 11 Charging Pump coupling failure CVCS003 Olon F3
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| : d. Spurious CIS B actuation ESFAOlO_02 on F4
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| : e. VCT level transmitter fails high CVCS 009 high on F5
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| : f. CCW leak in Containment CCW003 0-3% over 5 minutes on F6
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| --g. CEAO 1 on bottom set as T1
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| : h. 12 S/G tube rupture MS002 _02 (1 tube) on T1
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| 6 Enter Panel Overides
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| : a. 13 4KV Bus Nonnal Feeder breaker in PTL with yellow tag.
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| : 7. Set simulator time to real time, then place simulator in RUN.
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| : 8. Give crew briefing.
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| : a. Present plant conditions: 100% load at MOC 10.885 MWD/MTU
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| : b. Power history: Long tenn steady state for past 52 days
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| : c. Equipment out of service:
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| * 13 4KV Bus nonnal feeder breaker OOS for scheduled maintenance.
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| * d. Abnormal conditions: None
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| : e. Surveillances due: None
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| : f. Instructions for shift: Maintain power
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| : g. EOOS Risk: Low CDF 1.16 LERF 1.19
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| : h. Blowdown: Overboard at 100 gpm
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| : 9. Allow crew 3-5 minutes to acclimate themselves with their positions.
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| : 10. Instructions for the Booth Operator.
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| : a. After crew assumes the watch use Fl to fail TBV -3940 open.
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| : b. After TBV isolation is shut and crew has a brief use F2 to fail12B 480V Bus
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| : c. After crew ties MCC-I 06 & 166 use F3 to fail 11 charging pump coupling.
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| : d. Once CVCS returned to nonnal use F4 & F5 to give spurious CIS B actuation and the VCT transmitter failure.
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| : e. After the crew has reset CIS and initiated CCW flow to containment use F6 to initiate the CCW leak in the containment
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| RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.
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| REQUEST RESPONSE
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| : 1. TBO check TBV 3940 After 3 minutes report an air leak and valve is open. Leak can be isolated by shutting l-IA-82, only 3940 affect by shutting IA-82
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| : 2. Shut MS-120 to isolate TBV-3940. Shut MS-120 as requested
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| : 3. OWC direct EM to check 12B 480V Bus After 10 min report bus is grounded.
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| : 4. PPOITBO tie MCC 106 & 116 After 5 min report ready to tie buses. Override SGFP A oil pump HIS's to off prior to tying bus using remote function.
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| : 5. ABO check 11 charging pump After 3 minutes report coupling failure
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| : 6. OWC direct 1M to evaluate CIS failure at Acknowledge request.
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| ESFAS
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| : 7. ABO check MIU to CCW Head Tank After 3 minutes report MIU valve open 8 TBO shift 12 ADV to lC43 with 0% output. After 3 minutes perform and inform Control Room
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| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: ._1_ Page -L of 12 Event
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| == Description:==
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| TBV 3940 fails open C (SRO/BOP) R(ATC)
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| I Time Position Applicant's Actions or Behavior ATC Recognize Tcold lowering & Reactor power increasing and reports to SRO BOP Recognize TBV -3940 failed open and reports to SRO SRO Implements AOP-7K due to overcooling event Assigns trip criteria to ATC:
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| SRO
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| * Reactor trip imminent
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| * Tcold <515 0 F Direct A TC to control Reactor Power < 100% by:
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| SRO
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| * Insert CEA's as necessary to control power
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| * Borate via fast borat:ton to control power Control Reactor Power < 100% by:
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| ATC
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| * Insert CEA's as necessary to control power
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| * Borate via fast boration to control power SRO Direct BOP to lower turbine load to maintain Tcold on program Lowers turbine load using Load Set HIS l-CS-80, to raise Tcold back to program BOP without exceeding 548 0 F BOP Direct TBO to investigate TBV-3940 and standby to isolate SRO When plant is stable direct BOP to work with TBO to get TBV isolated.
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| Direct shutting TBV isolation valve MS-120 while adjusting turbine load to BOP maintain temperature constant SRO Review Tech Specs for any n:quired entries
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| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _2_ Page.£of~ I Event
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| == Description:==
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| 12B 480V bus failure C (SRO/BOP)
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| Time Position Applicant's Actions or Behavior ATC/BOP Recognize multiple alarms and report to SRO SRO Direct ATC to monitor the primary and BOP to check RPS for a trip BOP Checks RPS and reports "RPS not calling for a trip" BOP Checks electrical buses and reports loss of 12 B 480V bus Implements AOP-7I and directs BOP to perform Block step IV.A to verify failed SRO bus BOP Determines only 12B 480V Bus is lost and reports Determines Section XV appropriate for 12B 480V Bus and direct BOP to perform SRO step XV.A BOP Directs TBOIPPO/OWC to tie MCC-106 to MCC-116 lAW AOP-71 XV.A.3 Performs remainder of Block step A:
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| * Verify Emergency Ih Seal Oil Pump running BOP
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| * Place 11 & 12 CAR's in PTL and starts 13 & 14 CAR's
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| * Verifies 12 CEDM fan running
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| * Verify 12 Gland Exhaust Blower in operatin SRO Directs OWC to have EM shop investigate loss of 12B 480V bus
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| Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: ._3_ Page ~ of .12.
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| Event
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| == Description:==
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| 11 Charging Pump coupling failure C (ATe)
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| Time Position Applicant's Actions or Behavior ATC Recognize & report alarm F45 "CHG HDR FLOW La, PRESS La" ATC Recognize and report 11 Charging pump amps low and charging header low flow IA W Alarm Response Manual direct ATC to start 12 or 13 Charging pump and SRO place 11 Charging pump in PTL ATC Start 12 or 13 Charging Pump and secure 11 Charging pump Review 0I-2A for shifting charging pumps and place Backup Charging Pump ATC Selector Switch to "13 & 11" position BOP Direct ABO to check 11 Charging pump locally SRO Direct OWC to contact Mechanical Maintenance to check 11 Charging pump
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| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _4_ Page..!. of 12.
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| Event
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| == Description:==
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| Spurious CIS B Actuation I (BOP) TS (SRO)
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| Position Applicant's Actions or Behavior ATC/BOP Recognize & Report CIS Actuation alarm SRO Direct A TC to monitor primary and BOP to investigate CIS alarm BOP Determine and report CIS actuation is invalid due to normal cont .
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| BOP Review alarm manual and recommend resetting CIS SRO Direct resetting invalid CIS alarm using EOP Att. 4 Match H*" handswitches :
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| * CC-3832-CV & CC-3833-CV BOP
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| * IA-2080-MOV Reset CIS by depressing CIS rest pushbuttons on 1C09 & 1C 10 After CIS is reset open valves shut during rest IA W ARM to restore CC & IA to the containment.
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| Direct ATC to monitor RCP temperatures and trip criteria lAW ARM for RCP SRO Aux Status Panel alarms due to no CC flow to RCP's Monitor RCP temperatures on Plant Computer
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| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario 1\10.: --.L Event No.: ._5_ Page 2 of 11 Event
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| == Description:==
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| VCT level transmitter fails high I (ATC)
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| Time Position Applicant's Actions or Behavior ATC Recognize and report Low VCT level alarm F-ll Refer to ARM for alarm window F-ll and recognize CVC-500 is diverting to ATC WPS and requests permission to place CVC-500 to VCT position SRO Direct A TC to place CVC-500 in VCT position ATC Places CVC-500 in VCT position and verifies valve changes position.
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| ATC Prepare to fill VCT lAW 0I-2B SRO Direct OWC to contact 1M shop to determine cause for CVC-500 failure to WPS
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| Appendix 0 Required Operator Actions Form ES*D*2 Op-Test No.: 2010 Scenario No.: ~ Event No.: _6_ Page ~ of 12 Event
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| == Description:==
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| Component Cooling leak in the containment C (All)
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| Time positinn Applicant's Actions or Behavior BOP ize & report containment sump alarm BOP containment parameters and report no abnormalities.
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| BOP Reference ARM and drain containment sump lAW 01-17 BOP Recognize & report low Component Cooling Head Tank alarm SRO Implement AOP-7C Direct A TC to monitor for trip criteria:
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| * RCP upper or lower thrust bearing temp> 195 0 F SRO
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| * RCP upper or lower guide bearing temperature> 195 0 F
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| * RCP controlled Bleed-Off flow temperature>200° F SRO Direct BOP to perform Block step C BOP Verify CC pump not cavitating BOP Bypass CVCS lX's using CVC-520-CV Determines leak location is in the containment and requests permission to isolate BOP CC to the containment SRO Direct BOP to shut Containment CC isolation valves Shut CC-3832 & 3833-CV's and verify leak is isolated by verifying CC Head BOP Tank level rise Direct A TC to trip the Reactor and when Reactivity Control Safety Function is SRO complete, then secure all RCP's Trip's Reactor & implements EOP-O:
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| * Depress one set of Reactor trip pushbuttons
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| * Verifies prompt drop in Reactor Power and negative SUR ATC
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| * Verifies no more than 1 CEA fails to insert
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| * Verifies DI water makeup to RCS is secured.
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| * Reports Reactivity Control Safety Function is comple Trips all RCP's due to no CC flow
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| Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2010 Scenario No.: ~ Event No.: ._7_ Page.l of Jl Event
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| == Description:==
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| 12 S/G tube rupture M (All) TS (SRO)
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| Time Position Applicant's Actions or Behavior Verify Turbine is tripped:
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| * Check Reactor is tripped
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| * Ensure Turbine is tripped o Depress both turbine trip pushbuttons BOP o Check Turbine Stop valves shut o Check turbine speed drops o Ensure TG breakers open nd
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| * Ensure both 2 stage MSR MOV's shut Report Turbine Trip complet(: to SRO Verify Vital Auxiliaries:
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| * Check 11 or 14 4KV Bus energized
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| * Ifeither 11 or 14 4KV Bus de-energized then start OC DG
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| * Check 125VDC & 120V AC buses energized BOP
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| * Check either 1Y09 or 1Y 10 energized
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| * Verify Component Cooling flow to RCP's
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| * Directs ABO to verify Switchgear Room Ventilation operating Reports Vital Auxiliaries cannot be met due to Component Cooling flow to RCP's.
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| Verify Pressure and Inventory Control:
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| * Check pressure 1850-2300 psia trending to 2250 psia o Opeates PZR heaters & spray to maintain o IfRCS Press <1725 psia verify SIAS ATC
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| * Checks PZR level between 80 & 180 inches, trending to 160 inches o IfPZR level low and trending lower, then start all available charging pumps and isolate letdown
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| * Ensure RCS subcooling >30 0 F Reports RCS Pressure & Inventory cannot be met due to low PZR level and negative trends on PZR level & pressure
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| Verify Core and RCS Heat Removal Safety Function
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| * Verify TBV's or ADV's maintain S/G press 850-920 psia and Tcold 525 535 0 F
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| * Verify at least one S/G available for controlled heat removal 0 S/G level (-) 170 - (+)30 inches BOP 0 Main or Aux Feedwater operating to maintain level 0 Tcold >525 0 F
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| * Check at least one RCP in loop with S/G available
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| * IfRCP's operating check ~T <10 0 F Report Core and RCS Heat Removal cannot be met due to no operating RCP's Verify Containment Environment Safety Function:
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| * Check containment pressure <0.7 psig:
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| BOP/ATC
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| * Check containment temp < 1200 F
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| * Check containment radiation alarms clear with no unexplained rise:
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| Reports Containment Environment Safety Function as complete Verify Radiation Levels External to Containment Safety Function:
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| * Check RMS alarms clear with no unexplained rise BOP/ATC 0 Valid condenser off-gas & S/G blow down radiation alarms, verify S/G blow down isolated.
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| * Report Radiation Levels External to Containment is complete Hold crew briefing covering:
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| * Vital Auxiliaries not met due to no component cooling flow to RCP's SRO
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| * PIC not met due to PZR level & pressure low and/or negative trends
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| * Heat Removal not met due to no operating RCP's
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| * RLEC not met due to valid off gas & blow down alarms
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| * SIAS actuation (if actuated)
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| SRO Review Diagnostic flowchart and determines EOP-6 is correct path SRO Implements EOP-6, hold entry brief, assigns block steps to A TC & BOP
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| I Block Step D Monitor RCS Depressurization:
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| * IfRCS pressure < 1725, psia verity SIAS
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| * IfRCS pressure> 1725 psia, take actions top block SIAS:
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| 0 Open Main & Aux HPSI header valves 0 Start 11 & 13 HPSI pumps 0 Start all available charging pumps 0 When PZR Press Block Permitted alarm is received, then Block ATC SIAS with key switches on IClO 0 When RCS pressure is below 1270 psia, then verity HPSI flow JAW Att. 10
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| * IfSIAS has actuated:
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| 0 Verity 11 & 13 HIS running 0 Verity 11 & 12 LPSi running 0 Verity all available charging pumps operating 0 Verity HPSI & LPSI flow per Att. lO & 11 Block Step F Commence RCS Boration:
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| * If SIAS has actuated then:
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| 0 Verity VCT MIU valve CVC-512-CY shut 0 BA Direct MlU valve CVC-514-MOV open 0 BAST Gravity Feed valves CYC-508 & 509-MOY's open 0 RWT CRG PP Suction valve CYC-504-MOY shut 0 All BA pumps running ATC 0 YCT outlet CYC-501*MOV shut 0 All available charging pumps operating
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| * IF SIAS ahs not actuated then:
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| a Same actions as above with ..
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| a MIU Mode selector in Manual
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| * Record time boration started and BAST levels
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| Block Step G Commence RCS Cooldown:
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| * If SGIS not actuated then:
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| 0 Block SGIS A & B when SGIS Block Permitted alarms are received
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| * If SGIS actuates with vacuum available: (not expected) 0 Place all CBP HfS's in PTL 0 Verity SGIS lAW Att. 7 0 Block SGIS 0 Reset SGIS signals 0 Open both MSIV's
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| * Cooldown RCS using TBV's 0 Ensure ADV's shut 0 Perfonn rapid cooldown to 515 0 F Thot, while maintaining <
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| 100° F cooldown in anyone hour (TBV controller to approximately 17 + 25 = 42%)
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| * If any of the following conditions exist:
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| BOP 0 SIAS actuated 0 TBV's not available 0 Main Feedwater not in operation then:
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| * Establish AFW flow with 13 AFW pump
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| * Open all Motor train block valves
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| * Start 13 AFW pump
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| * Restore unaffected S/G level (-)24 - (+)30 inches using flow control valve
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| * Secure Main Feedwater system:
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| * If SIAS not actuated, TBV's available & Main Feedwater in operation:
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| 0 Establish shutdown feed lineup
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| * One SGFP, One CBP, Two Condensate pumps, no HDP's
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| * Ensure feed flow restoring S/G level (-)24 (+)30 inches wlo exceeding 1000 F in anyone hour
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| * Dispatch TBO to standby in 45' SWGR room for shifting ADV control
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| Block Step H Evaluate Need for HPSI Throttling:
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| * If all following conditions met 0 At least 25 0 F subcooling based on CET's 0 PZR level:> 101inches ATC 0 One SIG available for heat removal, then
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| * HPSI flow may be reduced by throttling or stopping HPSI pumps one at a time to maintain:
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| * CET Subcooling 25 - 1400 F
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| * PZR level 101-180 inches Block Step I Depressurize RCS to reduce subcooling and maintain PZR level
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| * If a bubble exist in PZR then maintain subcooling as low as possible but between 25 & 140
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| * RCS Press < 900 psia
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| * RCS Press approximately equal to SIG pressure by 0 Initiation of Aux. Spray ATC
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| * Record PZR water temp & Charging temp
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| * Open Aux. Spray valve CVC-517-CV
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| * Shut Charging loop stops as necessary CVC-5I8 &
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| 5I9-CV's
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| * Shift PZR Main spray controller HIC-IIO to manual with 0% output
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| * Maintain PZR CID rate < 2000 F per hour
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| Block Step J Identify, Isolate and Confirm affected S/G
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| * Identify affected S/G using:
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| o S/G sampll~s o Main Steam Rad Monitor trends o S/G level trends when not feeding o Post trip S/G level trends
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| * When Thot < 5156 F then isolate most affected S/G 0 Shut 12 AnV using hand transfer valve in 45' SWGR room 0 Shut 12 MSIV 0 Verify 12 MSIV Bypass MS-4052-MOV shut 0 Verify 12 S/G Feedwater Isolation valveFW-4517-MOV shut BOP 0 Shut 12 S/g AFW Steam Supply valves MS-4071 7 4071A CV's 0 Shut 12 S/G AFW Block valves
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| * l-AFW-4530-CV
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| * l-AFW-4531-CV
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| * l-AFW-4532-CV
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| * l-AFW-4S33-CV 0 Shut 12 S/G Blowdown valves BD-4012 & 4013-CV's o Shut MS Upstream drain Isolation valves with HS-6622 in close o Direct ABO or OSO to verify no 12 S/G Safety valves leaking
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| *}}
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