ML092120013

Initial Exam 2009-301 Draft Administrative JPMs

ML092120013
Person / Time
Site:	Harris
Issue date:	07/31/2009
From:	NRC/RGN-II
To:	Progress Energy Carolinas
References
50-400/09-301
Download: ML092120013 (66)

Text

Appendix C Start Time: ___ _ Performance Step: 1 Standard:

Comment: ./ Performance Step: 2 Standard: ( Evaluator Cue: Comment: ./ -Denotes a Critical Step Page 2 of 7 PERFORMANCE INFORMATION OBTAIN PROCEDURE (provided with handout) Form ES-C-1 Obtains AOP-001 and refers to Attachments 1 and 2. DETERMINE THERMOCOUPLE LOCATION(S)

ADJACENT TO THE MISALIGNED ROD USING THE CORE GRID MAP (SHEET 1), AND CIRCLE LOCATION(S)

IN TABLE ABOVE. THESE THERMOCOUPLES(S)

ARE AFFECTED.

Using the core grid map (Attachment 2, page 1 of 2), Determines affected thermocouples to be G02, J02, and H03. Circles G02, J02, and H03 on the table (Attachment 2, page 2 of 2). Provide TC core map (page 8 of JPM) when TIC Core Map function of RVLlS accessed.

2009A NRC Admin Exam RO A1-1 Rev 1 Appendix C ( ./ Performance Step: 3 Standard:

Comment: ./ Performance Step: 4 Standard:

Comment: ./ -Denotes a Critical Step Page 3 of? Form ES-C-1 PERFORMANCE INFORMATION RECORD VALUES FOR ALL OPERABLE AFFECTED AND SYMMETRIC THERMOCOUPLES USING THE RVLlS CONSOLE OR ERFIS. SYMMETRIC THERMOCOUPLES ARE THOSE IN THE SAME ROW. Locates RVLlS Console and accesses TIC CORE MAP for Train A and Train 8. (Printout of RVLlS provided in handout) Records value for Affected TC G02 (640°F) and Symmetric TC PO? (636°F). Records value for Affected TC J02 (640°F) and Symmetric TC PO? (636°F). Records value for Affected TC H03 (636°F) and Symmetric TCs COB (636°F), H13 (640°F), and NOB (644°F). DETERMINE THE AVERAGE OF SYMMETRIC COUPLES, FOR EACH AFFECTED THERMOCOUPLE.

Determines (636°F) for G02's Symmetric TC. Determines (636°F) for J02's Symmetric TC. Determines (640°F +/- 2°F) for H03's Symmetric TCs. 2009A NRC Admin Exam RO A1-1 Rev 1 Appendix C ./ Performance Step: 5 Standard:

Evaluator Cue: Comment: Stop Time: ___ _ Terminating Cue: ./ -Denotes a Critical Step Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-1 CALCULATE THE DIFFERENCE BETWEEN EACH AFFECTED THERMOCOUPLE AND THE AVERAGE OF ITS SYMMETRIC THERMOCOUPLES.

Calculates difference of 4°F (+/- 2°F between all affected TCs and their symmetric TCs.) Reports that temperature difference is within 10°F. USCO acknowledges report. END OF JPM Difference between each affected thermocouple and it's symmetric thermocouples has been calculated.

2009A NRC Admin Exam RO A1-1 Rev 1

( ( Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009a NRC JPM RO/SRO A1-1 DETERMINE ROD MISALIGNMENT USING THERMOCOUPLES Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: Form ES-C-1 2009A NRC Admin Exam RO A1-1 Rev 1 Appendix C INITIAL CONDITIONS:

INITIATING CUE: Page 6 of 7 JPM CUE SHEET Form ES-C-1 The plant was at 90 percent power, with a load decrease in progress, when the USCG noticed that the DRPI indication for rod H02 was reading 24 steps higher than the group demand. The load increase has been stopped and AOP-001 entered. The USCG has directed you to calculate the temperature difference between thermocouple(s) adjacent to the misaligned rod and the average of symmetric thermocouple(s), using Attachment 2 of AOP-001. 2009A NRC Admin Exam RO A1-1 Rev 1 Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET ( TIC CORE MAP (DATA SHEET 1) TRAIN B MSG#245 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A A B 632 B C I 636 I C D 644 D E 644 50 640 E F 50 644 G 644 H I 636 644 IH J 640 50 K 640 L 644 640 644 L M M N I 640 I N P 636 P R R 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TRAINA TIC CORE MAP MSG # 245 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A I 50 A B I 636 B C I 632 I C D D E 636 640 E F 640 644 640 644 G 640 H I 640 644 642 640 640 IH J K 640 644 50 L L M 640 644 M N I 636 640 644 I N P 640 P R 636 R 2 3 4 5 6 7 8 9 10 11 12 13 14 15 2009A NRC Admin Exam RO A1-1 Rev 1

}<ey /I.o-AI-I I MALf:UNCTION OF SYSTEM ( ( R -ControJRod T Thermocouple 1* -ThermQcouplesabandoned by EC 47997 AOP-001 Rev,* 32

( e. Kf Y "<<oAJ-1 MALFUNCTION OF ROD CONTRciLAND1NDICATIONSYSTEM Attachmeot 2 -Adjacent and'$Ymmetric Therm,ocouple Locations NOTE .. B10,E07, HOS, K08 .* and POShave no symmetrio'loqatlons.

at Symmetricthermocoupl(;;ts arefhose,jo,the SYMMETRIO,I.:OOATIONS' GRID I ' II TRAIN A B AOS* GO 1* 615 S L, B05 Y 0 COS M C D03 M A E04 005 E T T I F05 R 0 Foa* J N G06 F09 C S G08 '* Thermocouples abandoned by EC 47997 HOt.. HOS LOO. K03 1. ,.DETERMINE thermocoQple 8,QjacenHQfthe rod using core grid map ,', (Sheet 1). AND CIRCLE location(s) in Table above. ' Rev. 32 Page41of47 I ( >/(.£ Yilt) A I-I , MALFUNCTION OF ROD CONTRO(ANO JNDI¢ATION\SYSTEM

-, .' Attachment 2 ...

Thermocouple Locations

' Sheet30f3

2. RECORD.the following in the table below:

• AdjacentTC number "

• AdjCicentTC vafueUsing the RVLfSConsofe, ERFIS, orOSI ... PI 3. Ad'acentTC Number Value 4. COMPARE each adjacent thermocouple va,lue listeato its symmetric thermocouple average for indicatiOn of a misaligned rod, (REFER TO'Attachment1.)

• ",END OF ATTACHMENT 2""':" AOP-001 Rev. 32

( Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet Form ES-C-1 HARRIS Task No.: 301005H401 Determine Rod Misalignment Using JPM No.: 2009a NRC JPM Thermocouples SRO A 1-1 G2.17 4.4 / 4.7 NRC Examiner:

Date: ----Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

INITIAL CONDITIONS:

The plant was at 90 percent power, with a load decrease in progress, when the USCG noticed that the DRPI indication for rod H02 was reading 24 steps higher than the group demand. The load increase has been stopped and AOP-001 entered. Task Standard:

All calculations within +/- 2° of actual. Required Materials:

Calculator General

References:

AOP-001, Attachment 1 and Attachment 2, Rev. 32 and Tech Specs Handouts:

JPM Cue Sheets Pages 6-7 AOP-001, Attachments 1 and 2, (Rev. 32) Initiating Cue: The USCG has directed you to calculate the temperature difference between thermocouple(s) adjacent to the misaligned rod and the average of symmetric thermocouple(s), using Attachment 2 of AOP-001. Upon completion of Attachment 2 of AOP-001, evaluate Tech Specs for compliance.

When evaluating Tech Spec compliance, assume that the other parameters listed on Attachment 1 of AOP-001 agree with your determination of thermocouples.

Time Critical Task: No Validation Time: 16 minutes 2009A NRC Admin Exam SRO A1-1 Rev 1 Appendix C ( Start Time: ___ _ Performance Step: 1 Standard:

Comment: ./ Performance Step: 2 Standard:

Evaluator Cue: Comment: ./ -Denotes a Critical Step Page 2 of? Form ES-C-1 PERFORMANCE INFORMATION OBTAIN PROCEDURE (provided with handout) Obtains AOP-001 and refers to Attachments 1 and 2. DETERMINE THERMOCOUPLE LOCATION(S)

ADJACENT TO THE MISALIGNED ROD USING THE CORE GRID MAP (SHEET 1), AND CIRCLE LOCATION(S)

IN TABLE ABOVE. THESE THERMOCOUPLES(S)

ARE AFFECTED.

Using the core grid map (Attachment 2, page 1 of 2), Determines affected thermocouples to be G02, J02, and H03. Circles G02, J02, and H03 on the table (Attachment 2, page 2 of 2). Provide TC core map (page 8 of JPM) when TIC Core Map function of RVLlS accessed.

2009A NRC Admin Exam SRO A1-1 Rev 1 Appendix C ./ Performance Step: 3 Standard:

Comment: ./ Performance Step: 4 ( Standard:

Comment: ./ -Denotes a Critical Step Page 3 of? Form ES-C-1 PERFORMANCE INFORMATION RECORD VALUES FOR ALL OPERABLE AFFECTED AND SYMMETRIC THERMOCOUPLES USING THE RVLlS CONSOLE OR ERFIS. SYMMETRIC THERMOCOUPLES ARE THOSE IN THE SAME ROW. Locates RVLlS Console and accesses TIC CORE MAP for Train A and Train B. (Printout of RVLlS provided in handout) Records value for Affected TC G02 (640°F) and Symmetric TC PO? (636°F). Records value for Affected TC J02 (640°F) and Symmetric TC PO? (636°F). Records value for Affected TC H03 (636°F) and Symmetric TCs C08 (636°F), H13 (640°F), and N08 (644°F). DETERMINE THE AVERAGE OF SYMMETRIC COUPLES, FOR EACH AFFECTED THERMOCOUPLE.

Determines (636°F) for G02's Symmetric TC. Determines (636°F) for J02's Symmetric TC. Determines (640°F +/- 2°F) for H03's Symmetric TCs. 2009A NRC Admin Exam SRO A1-1 Rev 1 Appendix C ( ./ Performance Step: 5 Standard:

Evaluator Cue: Comment: ./ Performance Step: 6 Standard:

Evaluator Cue: Comment: Stop Time: ___ _ Terminating Cue: ./ -Denotes a Critical Step Page 4 of? Form ES-C-1 PERFORMANCE INFORMATION CALCULATE THE DIFFERENCE BETWEEN EACH AFFECTED THERMOCOUPLE AND THE AVERAGE OF ITS SYMMETRIC THERMOCOUPLES.

Calculates difference of 4°F (+/- 2°F between all affected TCs and their symmetric TCs.) Reports that temperature difference is within 1Q°F. USCO acknowledges report. OBTAIN AND EVALUATE TECH SPECS Obtains Tech Specs and refers to LCO 3.1.3.2 Determines that ACTION a. is applicable. (See Attached)

USCO acknowledges report. END OF JPM Difference between each affected thermocouple and it's symmetric thermocouples has been calculated . 2009A NRC Admin Exam SRO A1-1 Rev 1 Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009a NRC JPM RO/SRO A1-1 DETERMINE ROD MISALIGNMENT USING THERMOCOUPLES Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

Form ES-C-1 2009A NRC Admin Exam SRO A1-1 Rev 1 Appendix C INITIAL CONDITIONS:

INITIATING CUE: Page 6 of 7 JPM CUE SHEET Form ES-C-1 The plant was at 90 percent power, with a load decrease in progress, when the USCG noticed that the DRPI indication for rod H02 was reading 24 steps higher than the group demand. The load increase has been stopped and AOP-001 entered. The USCG has directed you to calculate the temperature difference between thermocouple(s) adjacent to the misaligned rod and the average of symmetric thermocouple(s), using Attachment 2 of AOP-001. Upon completion of Attachment 2 of AOP-001, evaluate Tech Specs for compliance.

When evaluating Tech Spec compliance, assume that the other parameters listed on Attachment 1 of AOP-001 agree with your determination of thermocouples.

2009A NRC Admin Exam SRO A1-1 Rev 1 Appendix C TIC CORE MAP (DATA SHEET 1) TRAIN B 2 3 4 5 6 A B C I D 644 E F 50 644 G H I 636 644 J K 640 L 644 M N I P R 2 3 4 5 6 ( TRAIN A TIC CORE MAP 2 3 4 5 6 A I B I 636 C I D E 636 F 640 G 640 H I J K 640 L M N I 636 640 P R 2 3 4 5 6 Page 7 of 7 JPM CUE SHEET 7 8 9 10 632 636 644 50 644 640 640 640 636 7 8 9 10 7 8 9 10 50 640 644 640 644 644 640 644 640 636 7 8 9 10 11 11 11 640 642 50 644 11 Form ES-C-1 MSG #245 12 13 14 15 A B I C D 640 E IH 50 644 L M I N P R 12 13 14 15 MSG #245 12 13 14 15 A B 632 I C D E 644 640 640 IH L M I N P R 12 13 14 15 2009A NRC Admin Exam SRO A1-1 Rev 1

(

MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM Attachment 2 w Adjacent and Symmetric Thermocouple Locations Sheet 1 of 3 THERMOCOUPLE LOCATIONS 1 2 3 4 A .n ,,'" B**** ..

• C D E F G H J K L M N P R .. H J ',.. * ** t: n,. ." f ... I

• I : ,.........;'--+-,,",", ... : ...... :... T R I I I ... :... R T

• I ... : ... R T* R *

• T' T T R T R* Control Rod T -Thermocouple 5 6 7 R T R R T R R T T T"'-Thermocouples abandoned by EC 47997 AOP-001 Rev. 32 9 10 11 1213 14 R T R T' T R Page 40 of4?

( 1(fY MALFUNCTION OF ROD CONTROL AND INDICATIONSY$TEM -Adjacent andSYl11metric Thermocouple Locations Sheet2of3 NOTE

• 810, EO?, H08, K08, and P08 have no symmetric rocations

• Symmetric thermocouples are those in the same row, SYMMETRIC LOCATEON$

GRID TRAIN A B A A08* G01* S L B05 Y 0 C08 Hi3 M C D03 C12 M A 005 E12 E T H11 E08 T F05 F11 EtO Kit'" R 0 F03* F13 I N G06 F09 C S G08 H09 M09 J12*

• Thermocouples abandoned by EC 47997 1. DETERMINE thermocouple location(s) adJacenttothemisalignedrod using core grid map (Sheet 1), AND CIRCLE location(s) inTable above. AOP-001 Rev. 32 Page 41 of 47

( MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM Attachment 2 Adjacent and Symmetric Thermocouple Locations Sheet 3 of3 2. RECORD the following in the table below: .. Adjacent Te number .. Adjacent TC value using the RVUS Console, ERFIS, or

.. Symmetric TC numbers including adjacent TCCs) '* Symmetric TC values for all OPERABLETCsusing the RVLlS Console,ERFIS,or OSI-PI 3. DETERMINE the average of symmetric thermocouples, for eachadjacenfthermocouple, Ad'acent TC Number Value

4. COMPARE each adjacent thermocouple value listed to its symmetric thermocouple average for indication of a misaligned rod. (REFER TO Attachment 1.) Rev. 32 Page 42 of 47 REACTIVITY CONTROL . SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT UMITINGCONOITION FOR OPERATION 3.1. 3.1 All shutdown and control rods shall be OPERABLE and positi oned with; n +/- 12 steps (indicated position) of thetrgroupstep counter demand position, APPLICABILITY:

MODES 1'" andt'. ACTION: a. With one or more rods inoperable due to being immovable as a result of excessive frictiorlor mechanical interference or known to be untrippable.

determine.

that the SHUTDOWN MARGTN.requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY withi n 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. b, With more than one rod misaligned from the group step counter demand position by more than +/- 12 steps (indicated position).

be tnBOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. c. d. With more than one rodi noperab 1 e ,due. to a rod control urgent fa 11 ure alarm or obvious electrical.

prob 1 emi n the rod control system existing for greater than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. With one rod trippable but inoperable due to causes other than addressedbyACTIONa

.. above.or misaligned from its group step counter demand height by more than +/- 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour: 1. The rod is restored to OPERABLE status within the above aJ i gnment requi rements. or, 2. The rod is declared inoperable and the remainder of the rods in the group with. the .in. operab. '.e ro. dare a1. 19.ned to within .. +/- 12 steps of the inoperable rod while maintaining the rod seq.ue. n .. ce. an. d inse .. rtto.n 1.i.mitS.

Of ... s .. p .. ec ... i.* .. f. iCo .. ti.o.*.n .3 .. 1 .. 3. ,6. The I* THERMAL POWER level shall be restricted pursuant to Spec; fi cat; on 3.1. 3. 6duri ng subsequentoperati on. or 3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then conti nueprovided that: a) A reevaluation of each accident analysis of Table performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these 'accidents

• See Special Test Exceptions Speci ficatiOrls 3.10.2 and 3.10.3. SHEARON HARRIS -UNIT 1 3/4 1-14 Amendment No. 25

( '-f. EyS/l" 1/ J -I REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Cant i nued) : , ,'".', ' remain va Hd for theduraUon of thesE conditions:

.. b) The SHUTDOWNMARGINrequirement at Specification 3 .. 1.1.1 is determ1nedat leastonGe per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: ....... ..... . c) A power distribution map is obtained from the movable incore detectors and Fa(Z) and are verified to be within their limits within 7.2houtS; and d) The THERMAL POWER level. i sreducedi;oless than or eqlJd 1 to 75% of RATED THERMAL POWER .withintnenext hour *andwlthin thefonowing 4 hoyrs the .High Neutront:l.ux TripSetpoj.ntis reduced to less than aregua 1: to ,85% of RATED THERMAL,POWEK.

SURVEILLANCE REQUIREMENTS , ;" / 4.1.3,.1.1 The position of each rod tobe withih the group demand limit by verifying the individualrodpositiofTs at least once per 12* . hours'except during time intervals wben the rod position deviation monitor is inoperable.

then verify the group positiol1sat least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 4.;];.3.1.2 Each rod not fu llyi nsertedin the .core s.hall.t>edetermfned t6be OPERABLE by movement of at. least 10 steps in anyone direction at least Qoce' per 92 days,* ., SHEARON HARR IS* UN IT 1 93

( ;l fASt..! 3.1"1 ACCIDENT ANAL.YSES REOUIRING REEVALUAftON 1N,111£ EVetT OF AN INOPERABlE, ROO Red Cluster C4ntrol Ass_1y InslrtionCharl¢terfstie$

Red, Cluster Contro1Asselilbly Mis.l ipent. l..oU..ofRaaetor,Coolantfms 5.11 or in tnlea.'1eney Con , '-" , ' " Single Rod Cluster Control An.1y Major Reactor Coolant. System Pipe Rupt.urn {t.o$s-of-Coolant Accident) , "Major Secondary Coolant Sytta Pipe Ruptun Rupture of a Control Red Orive Housi-ng Control Assembly Ejection) , SHEARON RARRIS .. UNIT 1

( REACTlvrrvC014TROL . SYSTEMS POSITIONIND!CATIOH SYSTEMS'" .OPERATING LIMiTING CONDITION .FOR;. OPERATION , 3 .. 1;.3.2 . The Digital R4<tPQsitionlnd1cat'fonSysWl Ind. tMOtUnd

.'

System anctcapableofdetaJ"llihingtheshutdown anc.t control rod positionJ.within t,l!$t,ps.. . AP"LICABI LITY: MODES 1,' and!. ArnOH: , /"', , " .. .' With a tlufmt.Ulof .one digital rodpod'ttoi1 f{S¢featol" per OinK fnop.raijle'

• ;' .' . 1. Oettu"mi n. the podtton Of. thlnoni ndieat red( $}1 net; at 1,Ist onee par 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and i DlllJediat<<t1y.rter . By', tllGtion .of the, tlonil'ldiclti n1Jre.a* \(f1 icl1 exc:Hds 24 sUPS in on'ldii"lct.iol'l

$inc. the lut det"l"IDinatlon" of the I"Od'l pesition.

Of". . . 2. tlGuee 'ntiltMAl..PMa tale$sthirfSa

ofDlU within a ho,,". ' . / b.. Witb a ax1tlluat of one cta.lnd ilosit.fon indieat4J"pIJ" b.tnk fnQpet"lble

.... . .' 1 ... . 2. VeJ"ify thlt.n digital 'J"Od position 'jmth:ators . 'OJ"** tn ** bank I" OPUAlL.E...a that the.st;

¥'Od aM tnl 1 tut red ot _ bank

• .u.1-. Gf 11 ,,$ of ,ucftotlwJ" at . Rtduc.TJfERMAL POWER to lusthirfSCS cflAreD" THSIUfALPcr<<!R . witM,. ..hours. . . .... . 4.l. . ben tiiuiul ttian

.. -.'a. \l'UA8t£ bYvlrftying tbat tnl O_nd, POlitjG. Indic;ation SY$t.mt tttIOiQ;talR.od . PQitic., In4iQtion , ... withfn12 $tlpl at lUitonc.plr'll hours except dU1"1nlt1.

intl"_l,*

wMnth. roctpolft1o

.. dtvta:\fonenitot' 1.1. inQPlu'el., thtn.

tJieD_ndPositi'On Im11cltionSgst,.

arldt.l1 .. Digital RocLPc>sitionlndicationSyStlm at lea$t one.p.,. " hou" * .. ";-, , SHEAAOtt IWWS ... UNIT 1. , 3141-U Appendix C Facility:

Task Title: KIA

Reference:

Job Performance Measure Worksheet Form ES-C-1 HARRIS Perform A Manual Shutdown Margin Calculation 2.1.25 3.1/2.8 Task No.: 001004H101 JPM No.: 2009a NRC JPM RO A1-2 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data Examinee:

NRC Examiner:

Facility Evaluator:

Date: ----Method of testing: Simulated Performance:

x Classroom X Simulator READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

INITIAL CONDITIONS:

Task Standard:

Required Materials:

General

References:

Handouts:

The plant has been operating at 75% power for 6 weeks Core burnup is 350 EFPD RCS boron concentration is 300 ppm NO rods are believed to be immovable 1 untrippable POWERTRAX is NOT available OST-1036, Attachment 3, Manual SDM Calculation (Modes 1 and 2), completed with SDM of 3818.:!:.

75 pcm OST-1036, Shutdown Margin Calculation Modes 1-5 Rev. 39 Curve Book (Cycle 15) OST-1036, Shutdown Margin Calculation Modes 1-5 Rev. 39 Curve Book (Cycle 15) OST-1036, Shutdown Margin Calculation Modes 1-5 Rev. 39 2009A NRC Admin Exam RO A 1-2 Rev. 1 Appendix C (' Initiating Cue: Time Critical Task: Validation Time: Job Performance Measure Worksheet Form ES-C-1 The USCG has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SOM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

No 20 minutes 2009A NRC Admin Exam RO A 1-2 Rev. 1 Appendix C c** Start Time: ____ _ Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: ./ Performance Step: 3 Standard:

Comment: Performance Step: 4 Standard:

Comment: ./ -Denotes Critical Steps Page 3 of 8 PERFORMANCE INFORMATION Form ES-C-1 OBTAIN PROCEDURE (OST-1036 will be provided to allow candidates to write on, Curve Book will be included as a reference in the Book Cart) OST-1036, Section 7.3, Attachment 3, and Curve Book Enters Reactor Power Level Refers to given conditions and enters 75% Determine Rod Insertion Limit for power level Refers to Curve F-15-1 and determines TS limit for RIL to be 140 :t 2 steps Enters core Burn Up Refers to given conditions and enters 350 EFPD 2009A NRC Admin Exam RO A 1-2 Rev. 1

( Appendix C Performance Step: 5 Standard:

Comment: Page 4 of 8 PERFORMANCE INFORMATION Enters RCS Boron Concentration Refers to initial conditions and enters 300 ppm Form ES-C-1 NOTE: ATT 3, STEP 5 NOT PERFORMED SINCE VALUE IS INCLUDED AS PART OF ATTACHMENT.

./ Performance Step: 6 Standard:

Comment: ./ Performance Step: 7 Standard:

Comment: Performance Step: 8 Standard:

Comment: ./ -Denotes Critical Steps Determines Power Defect for current power level Refers to Curve C-15-3 and determines power defect to be 2265 .:t 50 pcm Determines Rod Worth for RIL position determined above Refers to Curve A-15-11 and determines rod worth to be 630 + 25 pcm Enters worth of any additional immovable or untrippable rods Refers to given conditions and enters 0 2009A NRC Admin Exam RO A1-2 Rev. 1 Appendix C ./ Performance Step: 9 Standard:

Comment: Page 5 of 8 PERFORMANCE INFORMATION Determines Total Shutdown Margin Form ES-C-1 Determines Total Shutdown Margin to be 3915:!: 75 pcm Performance Step: 10 Signs off Section 7.3 steps Standard:

Signs off steps as complete Comment: Terminating Cue: ./ -Denotes Critical Steps When the candidate completes CST -1036, Attachment 3, Manual SDM Calculation, this JPM is complete.

Stop Time: ____ ' 2009A NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Page 6 of 8 PERFORMANCE INFORMATION (SHADED AREA BELOW INDICATES DATA ALREADY PROVIDED)

Manual SDM Calculation (Modes 1 and 2) 1. Reactor power level. 2. Rod insertion limit for the above power level 140 +/- 2 steps on bank 3. Burn up (POWERTRAX/MCR Status Board). 4. Present RCS Boron Concentration NOTE: Use absolute values of numbers obtained from curves. Form ES-C-1 75 % 0 350 EFPD 300 ppm 5. Total worth of all control and shutdown banks, minus the worth of the most reactive rod for Fuel Cycle 15. 6. Cycle 15 Power defect for the power level recorded in Step 1. (Refer to Curves C-X-1 to C-X-3). Curve used C-15-3 NOTE: HFP curves are used for power levels of 10% or greater. 7. Inserted control rod worth at the rod insertion limit recorded in Step 2. (Refer to Curves A-X-6 to A-X-11) . Curve used A-15-11 pcm ( a ) 2265 +/- 50 pcm ( b ) 630 +/- 25 pcm ( c ) 8. Worth of any additional immovable or untrippable rods (for each stuck rod, use the most reactive single rod worth (1524 pcm) or obtain individual withdrawn rod worth from the reactor engineer).

o pcm ( d ) 9. Determine the Total Shutdown Margin using the following formula: Total SDM C s = 6810 -2265 +/- 50 -630 +/- 25 -0 ( e ) ( a ) ./ -Denotes Critical Steps ( b) ( c ) ( d ) 3915 +/- 75 pcm ( e ) 2009A NRC Admin Exam RO A1-2 Rev. 1

( Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009a NRC JPM RO/SRO A1-1 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: 2009A NRC Admin Exam RO A 1-2 Rev. 1 Appendix C ( INITIAL CONDITIONS:

INITIATING CUE: ( Page 8 of 8 JPM CUE SHEET Form ES-C-1

• The plant has been operating at 75% power for 6 weeks

• Core burnup is 350 EFPD

• RCS boron concentration is 300 ppm

• NO rods are believed to be immovable

/ untrippable

• POWERTRAX is NOT available The USCO has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SDM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

2009A NRC Admin Exam RO A1-2 Rev. 1

( ( Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet Form ES-C-1 HARRIS Determine Boric Acid Addition Following CR Evacuation G2.1.25 3.9/4.2 Task No.: 301013H401 JPM No.: 2009a NRC JPM SRQ A1-2 NRC Examiner:

Date: ___ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. . INITIAL The Control Room has been evacuated and the MCB transfer to the CONDITIONS:

ACP has been completed.

Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 86% with a concentration of 7300 ppm. The RCS is currently 745 ppm. Task Standard:

Calculate cold shutdown boron addition in percent change of the boric acid storage tank. The % change should be 26 to 32 percent (or a final BAT level of 55 to 59 percent).

Required Materials:

SHNPP CURVE BOOK Calculator General

References:

AOP-004 Rev. 44, Curve Book nomograph E-2 and curve 0-2 Initiating Cue: Time Critical Task: Validation Time: You are the "Unit" SCO. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-1036 cold shutdown boron requirement of 1600 ppm. No 15 minutes 2009A NRC Admin Exam SRO A 1-2 Rev 1 Appendix C C' Start Time: ___ _ Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Evaluator Cue: Comment: ./ Performance Step: 3 Standard:

Comment: ./ -Denotes a Critical Step Page 2 of 5 PERFORMANCE INFORMATION OBTAIN PROCEDURE Obtains AOP-004 and refers to Section 3.2 Step 25 Form ES-C-1 Obtain cold shutdown boron concentration using copy of latest OST-1036 in back of book. (If candidate asks: This information is provided in the initiating cue.) Required shutdown boron concentration is 1600 ppm USING THE FORMULA ON THE BORON ADDITION NOMOGRAPH E-2 FROM THE CURVE BOOK, DETERMINE REQUIRED GALLONS OF BORIC ACID TO ACHIEVE REQUIRED RCS BORON CONCENTRATION.

Utilizes formula on Nomograph E-2 and calculates between 8975 to 9075 gallons of boric acid to be added. Actual is 9027 gallons (NOTE: If candidate uses 7000 ppm for BAT BA concentration from the nomograph instead of using 7300 ppm that was given the result will be 9493 gallons) 2009A NRC Admin Exam SRO A 1-2 Rev 1 Appendix C ( ./ Performance Step: 4 Standard:

Comment: Evaluator Cue: Stop Time: ___ _ Terminating Cue: ./ -Denotes a Critical Step Page 3 of 5 PERFORMANCE INFORMATION Form ES-C-1 USING THE BORIC ACID TANK CURVE 0-2 FROM THE CURVE BOOK, DETERMINE THE CHANGE IN BORIC ACID TANK LEVEL EQUIVALENT TO THE REQUIRED GALLONS OF BORIC ACID. Utilizes Curve 0-2 and obtains a change of 23.5 to 29.5 percent (or a final level of 57.5 to 61.5 percent).

Actual is 26.5% change (or 59.5% final). END OF JPM Change in BAT level calculated.

2009A NRC Admin Exam SRO A 1-2 Rev 1 c Appendix C Page 4 of 5 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009a NRC JPM SRO A1-2 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

DETERMINE BORIC ACID ADDITION FOLLOWING CR EVACUATION Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009A NRC Admin Exam SRO A 1-2 Rev 1 Appendix C ( INITIAL CONDITIONS:

INITIATING CUE: ( Page 5 of 5 JPM CUE SHEET Form ES-C-1 The Control Room has been evacuated and the MCB transfer to the ACP has been completed.

Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 86% with a concentration of 7300 ppm. The RCS is currently 745 ppm. You are the USCO. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-1036 cold shutdown boron requirement of 1600 ppm. 2009A NRC Admin Exam SRO A1-2 Rev 1 c Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet Form ES-C-1 HARRIS Perform A Quadrant Power Tilt Ratio Calculation G2.2.12 3.7/4.1 Task No.: 015004H201 JPM No.: 2009a NRC JPM ROA-2 NRC Examiner:

Oate: ___ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

INITIAL CONDITIONS:

The plant is operating at 100 percent power. Power Range N41 is inoperable.

AOP-001, Malfunction Of Rod Control And Indication System has been entered due to a misaligned control rod. Task Standard:

QPTR correctly calculated per OST-1039, Rev 14. Required Materials:

Calculator General

References:

OST-1039 Rev 14 Handouts:

Initiating Cue:

• OST-1039 Rev 14

• Curve Book (Ensure F-15-8 Revision 7 included and unmarked)

The USCG has directed you to perform a Manual QPTR utilizing OST-1039, Calculation Of Quadrant Power Tilt Ratio. All prerequisites have been satisfied.

The Power Range NIS readings are provided in the table below. For the purposes of the examination, there will be no independent verification of your work. Time Critical Task: No Validation Time: 20 minutes 2009A NRC Admin Exam RO A-2 Rev 1 Appendix C Start Time: ___ _ Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: ./ -Denotes a Critical Step Page 2 of 9 PERFORMANCE INFORMATION Form ES-C-1 OBTAIN PROCEDURE (Provided to candidate to allow candidate to write on the procedure.

Curve book is on the Book Cart) Obtains OST-1039 PRIOR TO READING THE VALUE OF DETECTOR CURRENT, ENSURE THE METER RANGE/RATE SWITCH IS IN THE 400 JlA/SLOW POSITION.

Locates Meter Range/Rate switches for NI-41, NI-42, NI-43, and NI-44 and verifies they are in the 400 JlA/SLOW position. (Switches do not have to be checked all at once but should be checked before reading is taken from a drawer.) NOTE: This step is not performed with conducting exam in a classroom setting. Readings will be provided to candidate.

2009A NRC Admin Exam RO A-2 Rev 1 Appendix C ( ../ Performance Step: 3 Standard:

Comment: ../ Performance Step: 4 Standard: ( Comment: ../ Performance Step: 5 Standard:

Comment: ../ -Denotes a Critical Step Page 3 of 9 PERFORMANCE INFORMATION Form ES-C-1 RECORD ON ATTACHMENT 2 THE UPPER AND LOWER DETECTOR CURRENTS FROM ALL OPERABLE POWER RANGE CHANNELS AS READ AT THE NUCLEAR MENTATION CABINET. Locates upper and lower detector current indications and records them on Attachment

2. NOTE: This step is not performed with conducting exam in a classroom setting. Readings will be provided to candidate.

RECORDS ON ATTACHMENT 2 THE 100 % POWER NORMALIZED CURRENT FOR EACH CHANNEL References Curve F-1S-8 (Revision

7) and records the 100 % values on Attachment

2. DIVIDE VALUE IN COLUMN A BY THE RESPECTIVE NORMALIZED CURRENT IN COLUMN B AND RECORD THE RESULT IN COLUMN C. Takes value of Upper Detector Currents and divides by Normalized value for each channel and records values in Column C. 2009A NRC Admin Exam RO A-2 Rev 1 Appendix C ( ./ Performance Step: 6 Standard:

Comment: ./ Performance Step: 7 Standard:

Comment: ( ./ Performance Step: 8 Standard:

Evaluator Cue: Comment: ./ -Denotes a Critical Step Page 4 of 9 PERFORMANCE INFORMATION Form ES-C-1 CALCULATE THE AVERAGE VALUE FOR THE UPPER AND LOWER NORMALIZED FRACTION AND RECORD IN COLUMN D OF ATTACHMENT

2. Adds the Upper Normalized Fractions and divides by 3 and enters in Column D. Adds the Lower Normalized Fractions and divides by 3 and enters in Column D. USING THE FORMULA AND VALUES FROM ATTACHMENT 2 CALCULATE THE UPPER AND LOWER RATIOS Divides the Maximum Upper Normalized Fraction by the Average Upper Normalized Fraction.

Divides the Maximum Lower Normalized Fraction by the Average Lower Normalized Fraction.

Enters the values on Attachment

2. PERFORM INDEPENDENT VERIFICATION OF ALL CALCULATIONS MADE ON ATTACHMENT 2 (If Candidate asks for independent verification)

For the purpose of this examination, there will be no independent verification of your work. 2009A NRC Admin Exam RO A-2 Rev 1

( Appendix C ../ Performance Step: 9 Standard:

Comment: Evaluator Cue: Stop Time: ___ _ Page 5 of 9 PERFORMANCE INFORMATION Form ES-C-1 THE UPPER RATIO OR THE LOWER RATIO, WHICHEVER IS GREATER, IS THE QUADRANT POWER TILT RATIO (QPTR). RECORD QPTR AND VERIFY QPTR IS LESS THAN OR EQUAL TO 1.02 Acceptable band is +/-.5% (rounded to .005) around 1.0264 (1.0214 to 1.0314). LOWER (Greatest)

= 1.0264 QPTR is UNSAT When report is made that the QPTR is completed END OF JPM Terminating Cue: After the USCO has been notified:

Evaluation on this JPM is complete . ../ -Denotes a Critical Step 2009A NRC Admin Exam RO A-2 Rev 1

( ( Appendix C UPPER DETECTOR N-41 N-42 N-43 N-44 LOWER DETECTOR N-41 N-42 N-43 N-44 Page 6 of 9 PERFORMANCE INFORMATION KEY A 8 UPPER UPPER 100% POWER DETECTOR NORMALIZED CURRENT CURRENT INOPERABLE INOPERABLE 193.1 192.5 217.6 218.1 176.4 176.1 SUM A 8 LOWER LOWER 100% POWER DETECTOR NORMALIZED CURRENT CURRENT INOPERABLE INOPERABLE 229.3 223.6 237.1 240.6 209.9 212.8 SUM Form ES-C-1 C UPPER NORMALIZED NOTE 1 INOPERABLE 1.0031 0.9977 1.0017 3.0025/3 = 1.0008 C LOWER NORMALIZED FRACTION (NOTE 1) INOPERABLE 1.0254 0 .. 9854 0 .. 9863 2.9971/3 = 0.9990 Highest Upper (N-42) 1.0031/1.0008

= 1.0022 (0.9972 to 1.0072) Highest Lower (N-42) 1.0254/0.9990

= 1.0264 (1.0214 to 1.0314) ./ -Denotes a Critical Step 2009A NRC Admin Exam RO A-2 Rev 1

( ( Appendix C .........

• .** .< N41 N42 N43 N44 Page 7 of 9 PERFORMANCE INFORMATION HARRIS 2009 NRC RO JPM A2 Curve F-X-8 HANDOUT Revision Number: NRC Exam NIS Current Setpoint Table uA, 100% power **T0P *. Pl.JRREN;r***.****.*

176.1 192.5 218.1 176.1 Form ES-C-1 200.2 223.6 240.6 212.8 *Table above is based on Rev 7 of curve F-15-8 ./ -Denotes a Critical Step 2009A NRC Admin Exam R0 A-2 Rev 1

( \ Appendix C Page 8 of 9 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009a NRC JPM RO A2 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Examiner's Signature:

PERFORM A QUADRANT POWER TILT RATIO CALCULATION SAT UNSAT Date: 2009A NRC Admin Exam RO A-2 Rev 1

( ( Appendix C INITIAL CONDITIONS:

INITIATING CUE: Page 9 of 9 JPM CUE SHEET

• The plant is operating at 100 percent power.

• Power Range N41 is inoperable.

Form ES-C-1

• AOP-001, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM has been entered due to a misaligned control rod. The USCO has directed you to perform a Manual QPTR utilizing OST-1039, Calculation Of Quadrant Power Tilt Ratio. All prerequisites have been satisfied.

The Power Range NIS readings are provided in the table below. For the purposes of the examination, there will be no independent verification of your work. PRNIS Readings

• • .* **... * ..* **** *. . *********UPPERREA;DING N41 INOPERABLE INOPERABLE N42 193.1 229.3 N43 217.6 237.1 N44 176.4 209.9

• All values were taken with the Range/Rate switch in 400 !-lA/Slow position.

2009A NRC Admin Exam RO A-2 Rev 1

( ( Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

HARRIS Task No.: 015004H201 Task Title: Perform A Quadrant Power Tilt JPM No.: 2009a NRC JPM Ratio Calculation SROA-2 KIA

Reference:

G2.2.12 3.7/4.1 Examinee:

NRC Examiner:

Facility Evaluator:

Date: ___ _ Method of testing: Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

INITIAL CONDITIONS:

The plant is operating at 100 percent power. Power Range N41 is inoperable.

AOP-001, Malfunction Of Rod Control And Indication System has been entered due to a misaligned control rod. Task Standard:

QPTR correctly calculated per OST-1 039, Rev 14. Required Materials:

Calculator General

References:

OST-1039 Rev 14 Handouts:

Initiating Cue: Time Critical Task: Validation Time:

• OST-1039 Revision 14

• Curve Book (Ensure F-15-8 Revision 7 included and unmarked)

• Tech Specs The USCG has directed you to perform a Manual QPTR utilizing OST-1039, Calculation Of Quadrant Power Tilt Ratio. IF calculations are outside acceptable tolerances THEN evaluate Tech Specs. All prerequisites have been satisfied.

The Power Range NIS readings are provided in the table below. For the purposes of the examination, there will be no independent verification of your work. No 25 minutes 2009A NRC Admin Exam SRO A-2 Rev 1 Appendix C Start Time: ____ ' Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: ./ -Denotes a Critical Step Page 2 of 9 . Form ES-C-1 PERFORMANCE INFORMATION OBTAIN PROCEDURE (Provided to candidate to allow candidate to write on the procedure.

Curve book is on the Book Cart) Obtains OST-1039 PRIOR TO READING THE VALUE OF DETECTOR CURRENT, ENSURE THE METER RANGE/RATE SWITCH IS IN THE 400 J.JA/SLOW POSITION.

Locates Meter Range/Rate switches for NI-41, NI-42, NI-43, and NI-44 and verifies they are in the 400 J.JA/SLOW position. (Switches do not have to be checked all at once but should be checked before reading is taken from a drawer.) NOTE: This step is not performed with conducting exam in a classroom setting. Readings will be provided to candidate.

2009A NRC Admin Exam SRO A-2 Rev 1 Appendix C ( ./ Performance Step: 3 Standard:

Comment: ./ Performance Step: 4 Standard:

Comment: ./ Performance Step: 5 Standard:

Comment: l ./ -Denotes a Critical Step Page 3 of 9 PERFORMANCE INFORMATION Form ES-C-1 RECORD ON ATTACHMENT 2 THE UPPER AND LOWER DETECTOR CURRENTS FROM ALL OPERABLE POWER RANGE CHANNELS AS READ AT THE NUCLEAR MENTATION CABINET. Locates upper and lower detector current indications and records them on Attachment

2. NOTE: This step is not performed with conducting exam in a classroom setting. Readings will be provided to candidate.

RECORDS ON ATTACHMENT 2 THE 100 % POWER NORMALIZED CURRENT FOR EACH CHANNEL References Curve F-15-8 (Revision

7) and records the 100 % values on Attachment

2. DIVIDE VALUE IN COLUMN A BY THE RESPECTIVE NORMALIZED CURRENT IN COLUMN B AND RECORD THE RESULT IN COLUMN C. Takes value of Upper Detector Currents and divides by Normalized value for each channel and records values in Column C. 2009A NRC Admin Exam SRO A-2 Rev 1 Appendix C ( ./ Performance Step: 6 Standard:

Comment: ./ Performance Step: 7 Standard:

Comment: ./ Performance Step: 8 Standard:

Evaluator Cue: Comment: ./ -Denotes a Critical Step Page 4 of 9 PERFORMANCE INFORMATION Form ES-C-1 CALCULATE THE AVERAGE VALUE FOR THE UPPER AND LOWER NORMALIZED FRACTION AND RECORD IN COLUMN D OF ATTACHMENT

2. Adds the Upper Normalized Fractions and divides by 3 and enters in Column D. Adds the Lower Normalized Fractions and divides by 3 and enters in Column D. USING THE FORMULA AND VALUES FROM ATTACHMENT 2 CALCULATE THE UPPER AND LOWER RATIOS Divides the Maximum Upper Normalized Fraction by the Average Upper Normalized Fraction.

Divides the Maximum Lower Normalized Fraction by the Average Lower Normalized Fraction.

Enters the values on Attachment

2. PERFORM INDEPENDENT VERIFICATION OF ALL CALCULATIONS MADE ON ATTACHMENT 2 (If Candidate asks for independent verification)

For the purpose of this examination, there will be no independent verification of your work. 2009A NRC Admin Exam SRO A-2 Rev 1

( c-Appendix C ./ Performance Step: 9 Standard:

Evaluator Cue: Comment: Page 5 of 9 PERFORMANCE INFORMATION Form ES-C-1 THE UPPER RATIO OR THE LOWER RATIO, WHICHEVER IS GREATER, IS THE QUADRANT POWER TILT RATIO (QPTR). RECORD QPTR AND VERIFY QPTR IS LESS THAN OR EQUAL TO 1.02 Acceptable band is +/-.5% (rounded to .005) around 1.0264 (1.0214 to 1.0314). LOWER (Greatest)

= 1.0264 QPTR is UNSAT After the SRO Candidate reports that QPTR is UNSAT, direct the candidate to evaluate Tech Specs for compliance.

Performance Step: 10 OBTAIN TECH SPECS Standard:

Obtains Tech Specs Comment: ./ Performance Step: 11 Refers to Tech Spec 3.2.4 Standard:

Determines that ACTION a. is to be applied Evaluator Cue: END of JPM Comment: Stop Time: Terminating Cue: Determines Tech Spec Action for QPTR exceeding 1.02 ./ -Denotes a Critical Step 2009A NRC Admin Exam SRO A-2 Rev 1

( Appendix C UPPER DETECTOR N-41 N-42 N-43 N-44 LOWER DETECTOR N-41 N-42 N-43 N-44 Page 6 of 9 PERFORMANCE INFORMATION KEY A B UPPER UPPER 100% POWER DETECTOR NORMALIZED CURRENT CURRENT INOPERABLE INOPERABLE 193.1 192.5 217.6 218.1 176.4 176.1 SUM A B LOWER LOWER 100% POWER DETECTOR NORMALIZED CURRENT CURRENT INOPERABLE INOPERABLE 229.3 223.6 237.1 240.6 209.9 212.8 SUM Form ES-C-1 C UPPER NORMALIZED NOTE 1 INOPERABLE 1.0031 0.9977 1.0017 3.0025/3 = 1.0008 C LOWER NORMALIZED FRACTION (NOTE 1) INOPERABLE 1.0254 0.9854 0.9863 2.9971/3 = 0.9990 Highest Upper (N-42) 1.0031/1.0008

= 1.0022 (0.9972 to 1.0072) Highest Lower (N-42) 1.0254/0.9990

= 1.0264 (1.0214 to 1.0314) ./ -Denotes a Critical Step 2009A NRC Admin Exam SRO A-2 Rev 1

( Appendix C Page 7 of 9 PERFORMANCE INFORMATION HARRIS 2009 NRC SRO JPM A2 Curve F-X-8 HANDOUT Revision Number: NRC Exam NIS Current Setpoint Table uA. 100% power Form ES-C-1

,<,

,1;;;;:;:

N41 176.1 200.2 N42 192.5 223.6 N43 21B.1 240.6 N44 176.1 212.B *Table above is based on Rev 7 of curve F-15-B ./ -Denotes a Critical Step 2009A NRC Admin Exam SRO A-2 Rev 1

( Appendix C Page 8 of 9 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009a NRC JPM RO A2 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

PERFORM A QUADRANT POWER TILT RATIO CALCULATION ( Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009A NRC Admin Exam SRO A-2 Rev 1 c C Appendix C INITIAL CONDITIONS:

INITIATING CUE: N41 N42 N43 N44 Page 9 of 9 JPM CUE SHEET Form ES-C-1

• The plant is operating at 100 percent power.

• Power Range N41 is inoperable.

• AOP-001, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM has been entered due to a misaligned control rod. The USCO has directed you to perform a Manual QPTR utilizing OST-1039, Calculation Of Quadrant Power Tilt Ratio. IF calculations are outside acceptable tolerances THEN evaluate Tech Specs. All prerequisites have been satisfied.

The Power Range NIS readings are provided in the table below. For the purposes of the examination, there will be no independent verification of your work. PRNIS Readings INOPERABLE INOPERABLE 193.1 229.3 217.6 237.1 176.4 209.9

• All values were taken with the Range/Rate switch in 400 I-INSlow position.

2009A NRC Admin Exam SRO A-2 Rev 1 c Appendix C Facility:

Task Title: HARRIS Job Performance Measure Worksheet Task No.: Determine TEDE While Working in a JPM No.: High Airborne Area Form ES-C-1 2009a NRC JPM RO/SROA3 KIA

Reference:

2.3.4 Examinee

NRC Examiner:

Facility Evaluator:

Date: ___ _ Method of testing: Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

INITIAL CONDITIONS:

Task Standard:

The unit is being shut down for refueling and a planned crud burst is in progress.

The RAB AO is being directed by the Control Room to enter an area to align several valves. He is the only AO available to perform this task. This individual was employed at North Anna earlier this same year. At North Anna he received a combined 3,486 mRem TEDE during routine and emergency repair work response.

In the same calendar year while working at HNP, he has received another 349 mRem TEDE. The estimated dose rate in the area is 520 mRem/hr. An airborne contamination concern also exists. It is estimated that it will take approximately 20 minutes to complete the alignment if he uses a respirator.

If he does NOT wear a respirator, the alignment will take only 10 minutes, but Radiation Protection projects that your internal exposure will be 8 DAC-hrs. Determination made that NOT wearing a respirator will result in a lower TEDE and that the individual can perform the task without exceeding Progress Energy's Annual Administrative Dose Limit. 2009A NRC Admin Exam RO/SRO A3 Rev 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 ( Required Materials:

None General

References:

DOS-NGGC-0004, NGGM-PM-0002, Radiation Control and Protection Manual Handouts:

JPM Cue Sheet Page 7 Initiating Cue: 1. Determine the resultant total effective dose equivalent for Time Critical Task: Validation Time: No both with a respirator and without a respirator.

2. Using the lowest dose determined in number 1, determine if the individual can perform the task without exceeding Progress Energy's Annual Administrative Dose Limit. 10 minutes 2009A NRC Admin Exam RO/SRO A3 Rev 1 Appendix C Start Time: ___ _ Page 3 of 7 PERFORMANCE INFORMATION Form ES-C-1 NOTE: Steps in this JPM may be performed in any order. Performance Step: 1 Standard:

Comment: ./ Performance Step: 2 Standard:

Comment: Performance Step: 3 Standard:

Comment: ./ Performance Step: 4 Standard:

Comment: ./ -Denotes a Critical Step Determines internal exposure while wearing a respirator Determines internal exposure to be ZERO while wearing a respirator Determines external exposure while wearing a respirator Determines external exposure to be 173.3 mRem TEDE while wearing a respirator (520 mRem I hr x 20 min = 173.3 mRem) Determines TOTAL exposure while wearing a respirator Determines total exposure to be 173.3 mRem while wearing a respirator (0 mRem internal + 173.3 mRem external = 173.3 mRem total) Determines internal exposure while NOT wearing a respirator Determines internal exposure to be 20 mRem while not wearing a respirator (2.5 mRem I hr x 8 DAC-hr = 20 mRem) 2009A NRC Admin Exam RO/SRO A3 Rev 1 Appendix C ./ Performance Step: 5 Standard:

Comment: Performance Step: 6 Standard:

Comment: ./ Performance Step: 7 Standard:

Comment: ./ Performance Step: 8 Standard:

Comment: ./ -Denotes a Critical Step Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-1 Determines external exposure while NOT wearing a respirator Determines external exposure to be 86.7 mRem TEDE while not wearing a respirator (520 mRem / hr x 10 min = 86.7 mRem) Determines TOTAL exposure while NOT wearing a respirator Determines total exposure to be 106.7 mRem while not wearing a respirator (20 mRem internal + 86.7 mRem external = 106.7 mRem total) Determines individual's total exposure for the year Determines individual's total exposure for the year to be 3835 mRem (3485 mRem + 349 mRem = 3835 mRem) Determines individual's total exposure for the year if the work is allowed Determines individual's total exposure for the year if the work is allowed to be 3941.7 mRem (3835 mRem + 106.7 = 3941.7) Note: If calculated wearing a respirator the total exposure for the year will be 4008.3 mRem and work cannot be performed.

The directions were to use the lowest dose and this represents UNSA T performance.

2009A NRC Admin Exam RO/SRO A3 Rev 1 Appendix C ./ Performance Step: 8 Standard:

Comment: Stop Time: Terminating Cue: ./ -Denotes a Critical Step Page 5 of 7 Form ES-C-1 . PERFORMANCE INFORMATION Determines if the individual can perform the work without exceeding Progress Energy's Annual Administrative Dose Limit of 4000 mRem Determines the individual can perform the work not wearing a respirator without exceeding Progress Energy's Annual Administrative Dose Limit of 4000 mRem (3835 mRem + 106.7 = 3941.7) When all calculations have been completed and the determination that work can proceed, this JPM is complete . 2009A NRC Admin Exam RO/SRO A3 Rev 1 Appendix C Page 6 of7 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009a NRC JPM RO/SRO A1-1 Form ES-C-1 Determine TEDE While Working in a High Airborne Area Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009A NRC Admin Exam RO/SRO A3 Rev 1 Appendix C INITIAL CONDITIONS:

INITIATING CUE: Page 7 of7 JPM CUE SHEET Form ES-C-1 The unit is being shut down for refueling and a planned crud burst is in progress.

The RAB AO is being directed by the Control Room to enter an area to align several valves. He is the only AO available to perform this task. This individual was employed at North Anna earlier this same year. At North Anna he received a combined 3,486 mRem TEDE during routine and emergency repair work response.

In the same calendar year while working at HNP, he has received another 349 mRem TEDE. The estimated dose rate in the area is 520 mRem/hr. An airborne contamination concern also exists. It is estimated that it will take approximately 20 minutes to complete the alignment if he uses a respirator.

If he does NOT wear a respirator, the alignment will take only 10 minutes, but Radiation Protection projects that your internal exposure will be 8 DAC-hrs. 1. Determine the resultant total effective dose equivalent for both with a respirator and without a respirator.

2. Using the lowest dose determined in number 1, determine if the individual can perform the task without exceeding Progress Energy's Annual Administrative Dose Limit. 2009A NRC Admin Exam RO/SRO A3 Rev 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: HARRIS Job Performance Measure Worksheet , Form ES-C-1 Task No.: 345001H602 CLASSIFY AN EVENT JPM No.: 2009a NRC JPM SROA4 2.4.41 2.3/4.1 NRC Examiner:

Date: ___ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

INITIAL CONDITIONS:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue: Time Critical Task: Validation Time: The operating crew was performing a rapid shutdown of the plant when they were forced to initiate a manual reactor trip. Event classified as an Site Area Emergency (2-1-3) None PEP-110 EAL Flowpath (EP-EAL is an allowed reference)

JPM Cue Sheets Pages 4 and 5 PEP-110 EAL Flowpath (EP-EAL is an allowed reference)

Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM. Yes 15 minutes 2009A NRC Admin Exam SRO A-4 Rev 1

( Appendix C Page 2 of S PERFORMANCE INFORMATION Form ES-C-1 Evaluator Note: Start Time for this JPM begins when the individual has been briefed and accepted the task Start Time: ___ _ Performance Step: 1 Standard:

Comment: .;' Performance Step: 2 Standard:

Evaluator Cue: Stop Time: OBTAIN EAL FLOW PATH. Obtains EAL Flow Path. (EP-EAL is an allowed reference)

CLASSIFY EVENT Identifies an Site Area Emergency (2-1-3), Two Fission Product Barriers BREACHED OR JEOPARDIZED.

The Fuel is BREACHED due to an increase >1.0ES CPM in 30 minutes. CNMT is BREACHED due to primary to secondary leakage in 'A' SG >10 GPM and an 'A' SG safety valve not shut END OF JPM Terminating Cue: Event classification stated to evaluator.

.;' -Denotes a Critical Step 2009A NRC Admin Exam SRO A-4 Rev 1

( Appendix C Page 3 of 5 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009a NRC JPM RO/SRO A1-1 CLASSIFY AN EVENT Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: Form ES-C-1 2009A NRC Admin Exam SRO A-4 Rev 1 Appendix C INITIAL CONDITIONS:

INITIATING CUE: ( Page 4 of 5 JPM CUE SHEET Form ES-C-1 The operating crew was performing a rapid shutdown of the plant when they were forced to initiate a manual reactor trip. Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM. 2009A NRC Admin Exam SRO A-4 Rev 1

( c** Appendix C Page 5 of 5 JPM CUE SHEET CLASSIFICATION INFORMATION SHEET Form ES-C-1 The plant was operating at 100% power when the following sequence of events occurred:

At 1029, 'A' SGTL was diagnosed on 'A' SG at 12.0 GPM At 1038, the operating crew began a reactor shutdown per AOP-038, Rapid Downpower At 1039, the GFFD was reading 1.5E1 CPM when the shutdown was commenced At 1101, a manual reactor trip was initiated due to high vibration on "A" RCP At 1103, the following indications exist immediately after the reactor trip:

• One Safety Valve on 'A' SG opened and did not reseat

• All MSIVs were manually closed

• The GFFD is reading 1.2E5 CPM 2009A NRC Admin Exam SRO A-4 Rev 1