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 Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION Start Time: _ _ __

Performance Step: 1 OBTAIN PROCEDURE (provided with handout)

Standard: Obtains AOP-001 and refers to Attachments 1 and 2.

Comment:

./ Performance Step: 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.

Standard:

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).

(

Evaluator Cue: Provide TC core map (page 8 of JPM) when TIC Core Map function of RVLlS accessed.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam RO A1-1 Rev 1

Appendix C Page 3 of? Form ES-C-1 PERFORMANCE INFORMATION

( ./ Performance Step: 3 RECORD VALUES FOR ALL OPERABLE AFFECTED AND SYMMETRIC THERMOCOUPLES USING THE RVLlS CONSOLE OR ERFIS. SYMMETRIC THERMOCOUPLES ARE THOSE IN THE SAME ROW.

Standard: 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).

Comment:

./ Performance Step: 4 DETERMINE THE AVERAGE OF SYMMETRIC THERMO-COUPLES, FOR EACH AFFECTED THERMOCOUPLE.

Standard:

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.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam RO A1-1 Rev 1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 5 CALCULATE THE DIFFERENCE BETWEEN EACH AFFECTED THERMOCOUPLE AND THE AVERAGE OF ITS SYMMETRIC THERMOCOUPLES.

Standard: Calculates difference of 4°F

(+/- 2°F between all affected TCs and their symmetric TCs.)

Reports that temperature difference is within 10°F.

Evaluator Cue: USCO acknowledges report.

END OF JPM Comment:

Stop Time: _ _ __

Terminating Cue: Difference between each affected thermocouple and it's symmetric thermocouples has been calculated.

./ - Denotes a Critical Step 2009A NRC Admin Exam RO A1-1 Rev 1

Appendix C Page 5 of 7 Form ES-C-1 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:

2009A NRC Admin Exam RO A1-1 Rev 1

Appendix C Page 6 of 7 Form ES-C-1 JPM CUE SHEET 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.

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.

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

~636

~

D 644 D E 644 50 640 E

~ ~:

F 50 644 G 644 H I 636 644 IH

~ ~~

J 640 50 K 640

~636 ~

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 644 640 644 G 640 640 H I 640 644 642 640 640 IH

~64a

~~

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 RODCONrROLA~DINDICAl'JON SYSTEM

(

(

R - ControJRod T ~ Thermocouple 1* -ThermQcouplesabandoned by EC 47997 AOP-001 Rev,* 32

Kf Y"<<oAJ-1 MALFUNCTION OF ROD CONTRciLAND1NDICATIONSYSTEM

( Attachmeot 2 - Adjacent and'$Ymmetric Therm,ocouple Locations Sh~et20f3, HOt..

NOTE

.. B10,E07, HOS, K08.* and POShave no symmetrio'loqatlons.

at Symmetricthermocoupl(;;ts arefhose,jo,the sam~'row; SYMMETRIO,I.:OOATIONS' GRID t--~--t-----.

I ' II TRAIN A B AOS*

GO 1* 615 S L, B05 Y 0 COS M C D03 M A E04 005

e. E T HOS T I F05 LOO.

R 0 Foa* K03 J N G06 F09 C S G08

'* Thermocouples abandoned by EC 47997

1. ,.DETERMINE thermocoQple IQ~atioo(s) 8,QjacenHQfthe misalign~ rod using core grid map ,',

(Sheet 1). AND CIRCLE location(s) in Table above. '

Rev. 32 Page41of47

>/(.£ Yilt) A I-I ,

I MALFUNCTION OF ROD CONTRO(ANO JNDI¢ATION\SYSTEM

(

Attachment 2 ... A~jacentancfSymmetric 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 Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 301005H401 Task

Title:

Determine Rod Misalignment Using JPM No.: 2009a NRC JPM Thermocouples SRO A 1-1 KIA

Reference:

G2.17 4.4 / 4.7 Examinee: NRC Examiner:

Facility Evaluator: Date: ----

Method of testing:

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

( INITIAL The plant was at 90 percent power, with a load decrease in progress, CONDITIONS: 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 Page 2 of? Form ES-C-1 PERFORMANCE INFORMATION

( Start Time: _ _ __

Performance Step: 1 OBTAIN PROCEDURE (provided with handout)

Standard: Obtains AOP-001 and refers to Attachments 1 and 2.

Comment:

./ Performance Step: 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.

Standard:

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).

Evaluator Cue: Provide TC core map (page 8 of JPM) when TIC Core Map function of RVLlS accessed.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A1-1 Rev 1

Appendix C Page 3 of? Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 3 RECORD VALUES FOR ALL OPERABLE AFFECTED AND SYMMETRIC THERMOCOUPLES USING THE RVLlS CONSOLE OR ERFIS. SYMMETRIC THERMOCOUPLES ARE THOSE IN THE SAME ROW.

Standard: 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).

Comment:

./ Performance Step: 4 DETERMINE THE AVERAGE OF SYMMETRIC THERMO-COUPLES, FOR EACH AFFECTED THERMOCOUPLE.

( Standard:

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.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A1-1 Rev 1

Appendix C Page 4 of? Form ES-C-1 PERFORMANCE INFORMATION

( ./ Performance Step: 5 CALCULATE THE DIFFERENCE BETWEEN EACH AFFECTED THERMOCOUPLE AND THE AVERAGE OF ITS SYMMETRIC THERMOCOUPLES.

Standard: Calculates difference of 4°F

(+/- 2°F between all affected TCs and their symmetric TCs.)

Reports that temperature difference is within 1Q°F.

Evaluator Cue: USCO acknowledges report.

Comment:

./ Performance Step: 6 OBTAIN AND EVALUATE TECH SPECS Standard: Obtains Tech Specs and refers to LCO 3.1.3.2 Determines that ACTION a. is applicable. (See Attached)

Evaluator Cue: USCO acknowledges report.

END OF JPM Comment:

Stop Time: _ _ __

Terminating Cue: Difference between each affected thermocouple and it's symmetric thermocouples has been calculated .

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A1-1 Rev 1

Appendix C Page 5 of 7 Form ES-C-1 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:

2009A NRC Admin Exam SRO A1-1 Rev 1

Appendix C Page 6 of 7 Form ES-C-1 JPM CUE SHEET 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.

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.

2009A NRC Admin Exam SRO 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

~636

~

D 644 D E 644 50 640 E

~ ~:

F 50 644 G 644 H I 636 644 IH

~ ~~

J 640 50 K 640

~636 ~

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

( TRAIN A 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 644 640 644 G 640 640 HI 640 644 642 640 640 IH

~640

~~

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 SRO A1-1 Rev 1

$~OA1-1 MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM

(

Attachment 2 Adjacent and Symmetric Thermocouple Locations w

Sheet 1 of 3 THERMOCOUPLE LOCATIONS 1 2 3 4 5 6 7 9 10 11 1213 14

.n ,,'"

A B * * * * ..

• J ',.. * ** t: f ...

C

.. H n,. ."

I

• I

,.........;'--+-,,",",

... : ...... :... T R D I I

I

... :... R T R E

• I

... : ... R T* R T F **

G T' T H

J K

L R T R T' M T R R T R N T R T R P R T R T R* Control Rod T - Thermocouple T"'- Thermocouples abandoned by EC 47997 AOP-001 Rev. 32 Page 40 of4?

1(fY MALFUNCTION OF ROD CONTROL AND INDICATIONSY$TEM Attachment 2 - 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 OSI~PI

.. Symmetric TC numbers (~ot 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 ---r----~----+-~

(

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. With more than one rodi noperab 1e ,due. to a rod control urgent fa 11 ure alarm or obvious electrical. prob 1emi 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 />.

d. 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

.. ce. an. d inse. rtto.n 1.i.mitS. Of ...s seq.ue. n . p.. ec. iCo. ti.o.*.n .3 . 1. 3. ,6. The i.* .. f.

THERMAL POWER level shall be restricted pursuant to I*

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 3.1~lis 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 operatjonuhd~r 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 FA~ 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 shanbecfeterm~ned 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 d a y s , * .,

(

SHEARON HARR IS* UN IT 1 .AmendlilentNo.~ 93

( 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 Ruptu~dPl1)es or fmsCrlC~s in l..argIPtp'$WhiC:h~t.e$ tnlea.'1eney Con Cooli~'SYSta"

, ~ '- " , ' "

Single Rod Cluster Control An.1y Witbd~waratFullPQYI.r 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 M~anfslll Housi-ng (~Cd.Clu$t.l" Control Assembly Ejection) ,

l 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 PC$lt.i~n .'

Indi~ati()n System $h~l1 b.QPE~LE anctcapableofdetaJ"llihingtheshutdown anc.t control rod positionJ.within t,l!$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 fn~{ red( $}1 net; ~ly byth'lIOvabl.in¢ort>d.t~" 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 1HE.L~ER within a ho,,". '

( b..

~th~

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Witb a ax1tlluat of one cta.lnd ilosit.fon indieat4J"pIJ" b.tnk fnQpet"lble . .

1... VeJ"ify thlt.n digital 'J"Od position 'jmth:ators .'OJ"** tn* * 'f~

bank I" OPUAlL.E...a that the.st; wi1;hd¥"~ ¥'Od aM tnl 1tut wi~mm red ot _ bank ~ttt1ft * .u.1-. Gf 11

,ucftotlwJ" at 1~ ~_ a~.01'" .

,,$ of

.2. Rtduc.TJfERMAL POWER to lusthirfSCS cflAreD" THSIUfALPcr<<!R .

witM,. ..hours. . . .... .

4.l. 3.~ . ben tiiuiul .'MHi*'G~,\t.ion .1M~~_'t ttian i_>.t.anli~ ..- .'a. \l'UA8t£ bYvlrftying tbat tnl O_nd, POlitjG. Indic;ation SY$t.mt tttIOiQ;talR.od .

PQitic., In4iQtion Sy~ ,. . . withfn12 $tlpl at lUitonc.plr'll hours except dU1"1nlt1. intl"_l,* wMnth. roctpolft1o.. dtvta:\fonenitot' 1.1.

inQPlu'el., thtn. ¢OlIIIpa~ tJieD_ndPositi'On Im11cltionSgst,. arldt.l1..

Digital RocLPc>sitionlndicationSyStlm at lea$t one.p.,. " hou" *

.. ~.' ";-, l~,

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SHEAAOtt IWWS ... UNIT 1. , 3141-U

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 001004H101 Task

Title:

JPM No.: 2009a NRC JPM Perform A Manual Shutdown RO A1-2 Margin Calculation KIA

Reference:

2.1.25 3.1/2.8 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 The plant has been operating at 75% power for 6 weeks CONDITIONS: Core burnup is 350 EFPD RCS boron concentration is 300 ppm NO rods are believed to be immovable 1 untrippable POWERTRAX is NOT available Task Standard:

OST-1036, Attachment 3, Manual SDM Calculation (Modes 1 and 2),

completed with SDM of 3818.:!:. 75 pcm Required Materials:

OST-1036, Shutdown Margin Calculation Modes 1-5 Rev. 39 Curve Book (Cycle 15)

General

References:

OST-1036, Shutdown Margin Calculation Modes 1-5 Rev. 39 Curve Book (Cycle 15)

Handouts:

OST-1036, Shutdown Margin Calculation Modes 1-5 Rev. 39 2009A NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: 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.

Time Critical Task: No Validation Time: 20 minutes 2009A NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION c** Start Time: _ _ _ __

Performance Step: 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)

Standard: OST-1036, Section 7.3, Attachment 3, and Curve Book Comment:

Performance Step: 2 Enters Reactor Power Level Standard: Refers to given conditions and enters 75%

Comment:

./ Performance Step: 3 Determine Rod Insertion Limit for power level Standard: Refers to Curve F-15-1 and determines TS limit for RIL to be 140 :t 2 steps Comment:

Performance Step: 4 Enters core Burn Up Standard: Refers to given conditions and enters 350 EFPD Comment:

./ - Denotes Critical Steps 2009A NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 Enters RCS Boron Concentration Standard: Refers to initial conditions and enters 300 ppm Comment:

NOTE: ATT 3, STEP 5 NOT PERFORMED SINCE VALUE IS INCLUDED AS PART OF ATTACHMENT.

./ Performance Step: 6 Determines Power Defect for current power level Standard: Refers to Curve C-15-3 and determines power defect to be 2265 .:t 50 pcm Comment:

( ./ Performance Step: 7 Determines Rod Worth for RIL position determined above Standard: Refers to Curve A-15-11 and determines rod worth to be 630

+ 25 pcm Comment:

Performance Step: 8 Enters worth of any additional immovable or untrippable rods Standard: Refers to given conditions and enters 0 Comment:

./ - Denotes Critical Steps 2009A NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 9 Determines Total Shutdown Margin Standard: Determines Total Shutdown Margin to be 3915:!: 75 pcm Comment:

Performance Step: 10 Signs off Section 7.3 steps Standard: Signs off steps as complete Comment:

Terminating Cue: When the candidate completes CST -1036, Attachment 3, Manual SDM Calculation, this JPM is complete.

Stop Time: _ _ _ _'

./ - Denotes Critical Steps 2009A NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION (SHADED AREA BELOW INDICATES DATA ALREADY PROVIDED)

Manual SDM Calculation (Modes 1 and 2)

1. Reactor power level. 75  %

2. Rod insertion limit for the above power level 140 +/- 2 steps on bank 0

3. Burn up (POWERTRAX/MCR Status Board). 350 EFPD

4. Present RCS Boron Concentration 300 ppm NOTE: Use absolute values of numbers obtained from curves.

5. Total worth of all control and shutdown banks, minus the worth of the most reactive rod for Fuel Cycle 15.

pcm (a )

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 2265 +/- 50 pcm (b)

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-15-11 630 +/- 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 ) ( b) (c ) (d) 3915 +/- 75 pcm (e )

./ - Denotes Critical Steps 2009A NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION

(

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 Page 8 of 8 Form ES-C-1 JPM CUE SHEET

(

INITIAL CONDITIONS:

• 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 INITIATING CUE: 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 Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 301013H401

(

Task

Title:

Determine Boric Acid Addition JPM No.: 2009a NRC JPM Following CR Evacuation SRQ A1-2 KIA

Reference:

G2.1.25 3.9/4.2 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 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: 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.

Time Critical Task: No Validation Time: 15 minutes 2009A NRC Admin Exam SRO A 1-2 Rev 1

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION C' Start Time: _ _ __

Performance Step: 1 OBTAIN PROCEDURE Standard: Obtains AOP-004 and refers to Section 3.2 Step 25 Comment:

Performance Step: 2 Obtain cold shutdown boron concentration using copy of latest OST-1036 in back of book.

Standard:

Evaluator Cue: (If candidate asks: This information is provided in the initiating cue.)

Required shutdown boron concentration is 1600 ppm Comment:

./ Performance Step: 3 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.

Standard: Utilizes formula on Nomograph E-2 and calculates between 8975 to 9075 gallons of boric acid to be added. Actual is 9027 gallons Comment: (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)

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A 1-2 Rev 1

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION

( ./ Performance Step: 4 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.

Standard: 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).

Comment:

Evaluator Cue: END OF JPM Stop Time: _ _ __

Terminating Cue: Change in BAT level calculated.

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A 1-2 Rev 1

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION c Job Performance Measure No.: 2009a NRC JPM SRO A1-2 DETERMINE BORIC ACID ADDITION FOLLOWING CR EVACUATION 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 SRO A 1-2 Rev 1

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET

(

INITIAL CONDITIONS: 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.

INITIATING CUE: 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

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 ROA-2 KIA

Reference:

G2.2.12 3.7/4.1 Examinee: NRC Examiner:

Facility Evaluator: Oate: _ _ __

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.

c 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:

• OST-1039 Rev 14

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

Initiating Cue: 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 Page 2 of 9 Form ES-C-1 PERFORMANCE INFORMATION Start Time: _ _ __

Performance Step: 1 OBTAIN PROCEDURE (Provided to candidate to allow candidate to write on the procedure. Curve book is on the Book Cart)

Standard: Obtains OST-1039 Comment:

Performance Step: 2 PRIOR TO READING THE VALUE OF DETECTOR CURRENT, ENSURE THE METER RANGE/RATE SWITCH IS IN THE 400 JlA/SLOW POSITION.

Standard: 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.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam RO A-2 Rev 1

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION

( ../ Performance Step: 3 RECORD ON ATTACHMENT 2 THE UPPER AND LOWER DETECTOR CURRENTS FROM ALL OPERABLE POWER RANGE CHANNELS AS READ AT THE NUCLEAR INSTRU-MENTATION CABINET.

Standard: 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.

Comment:

../ Performance Step: 4 RECORDS ON ATTACHMENT 2 THE 100 % POWER NORMALIZED CURRENT FOR EACH CHANNEL Standard: References Curve F-1S-8 (Revision 7) and records the 100 %

values on Attachment 2.

(

Comment:

../ Performance Step: 5 DIVIDE VALUE IN COLUMN A BY THE RESPECTIVE NORMALIZED CURRENT IN COLUMN B AND RECORD THE RESULT IN COLUMN C.

Standard: Takes value of Upper Detector Currents and divides by Normalized value for each channel and records values in Column C.

Comment:

../ - Denotes a Critical Step 2009A NRC Admin Exam RO A-2 Rev 1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION

( ./ Performance Step: 6 CALCULATE THE AVERAGE VALUE FOR THE UPPER AND LOWER NORMALIZED FRACTION AND RECORD IN COLUMN D OF ATTACHMENT 2.

Standard: 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.

Comment:

./ Performance Step: 7 USING THE FORMULA AND VALUES FROM ATTACHMENT 2 CALCULATE THE UPPER AND LOWER RATIOS Standard: 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.

Comment:

(

./ Performance Step: 8 PERFORM INDEPENDENT VERIFICATION OF ALL CALCULATIONS MADE ON ATTACHMENT 2 Standard:

Evaluator Cue: (If Candidate asks for independent verification)

For the purpose of this examination, there will be no independent verification of your work.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam RO A-2 Rev 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION

(

../ Performance Step: 9 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 Standard: Acceptable band is +/- .5% (rounded to .005) around 1.0264 (1.0214 to 1.0314).

=

LOWER (Greatest) 1.0264 QPTR is UNSAT Comment:

Evaluator Cue: When report is made that the QPTR is completed END OF JPM Stop Time: _ _ __

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 Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION

(

KEY A 8 C UPPER UPPER UPPER 100% POWER NORMALIZED UPPER DETECTOR NORMALIZED F(~ACTI~~

DETECTOR CURRENT CURRENT NOTE 1 N-41 INOPERABLE INOPERABLE INOPERABLE N-42 193.1 192.5 1.0031 N-43 217.6 218.1 0.9977 N-44 176.4 176.1 1.0017 SUM 3.0025/3 =

1.0008

( A 8 C LOWER LOWER LOWER 100% POWER NORMALIZED LOWER DETECTOR NORMALIZED FRACTION DETECTOR CURRENT CURRENT (NOTE 1)

N-41 INOPERABLE INOPERABLE INOPERABLE N-42 229.3 223.6 1.0254 N-43 237.1 240.6 0 .. 9854 N-44 209.9 212.8 0 .. 9863 SUM 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 Page 7 of 9 Form ES-C-1 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***.****.*

N41 176.1 200.2 N42 192.5 223.6 N43 218.1 240.6 N44 176.1 212.8

• 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 Form ES-C-1 VERIFICATION OF COMPLETION

(

\

Job Performance Measure No.: 2009a NRC JPM RO A2 PERFORM A QUADRANT POWER TILT RATIO CALCULATION 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-2 Rev 1

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET

(

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.

INITIATING CUE: 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 eRNI$:G6~nnel** * .* ~.** . *. * ** .*.~c= .*********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 The plant is operating at 100 percent power. Power Range N41 is

( CONDITIONS: 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:

• OST-1039 Revision 14

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

• Tech Specs Initiating Cue: 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.

Time Critical Task: No Validation Time: 25 minutes 2009A NRC Admin Exam SRO A-2 Rev 1

Appendix C Page 2 of 9 . Form ES-C-1 PERFORMANCE INFORMATION Start Time: _ _ _ _ '

Performance Step: 1 OBTAIN PROCEDURE (Provided to candidate to allow candidate to write on the procedure. Curve book is on the Book Cart)

Standard: Obtains OST-1039 Comment:

Performance Step: 2 PRIOR TO READING THE VALUE OF DETECTOR CURRENT, ENSURE THE METER RANGE/RATE SWITCH IS IN THE 400 J.JA/SLOW POSITION.

Standard: 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.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A-2 Rev 1

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION

( ./ Performance Step: 3 RECORD ON ATTACHMENT 2 THE UPPER AND LOWER DETECTOR CURRENTS FROM ALL OPERABLE POWER RANGE CHANNELS AS READ AT THE NUCLEAR INSTRU-MENTATION CABINET.

Standard: 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.

Comment:

./ Performance Step: 4 RECORDS ON ATTACHMENT 2 THE 100 % POWER NORMALIZED CURRENT FOR EACH CHANNEL Standard: References Curve F-15-8 (Revision 7) and records the 100 %

values on Attachment 2.

Comment:

./ Performance Step: 5 DIVIDE VALUE IN COLUMN A BY THE RESPECTIVE NORMALIZED CURRENT IN COLUMN B AND RECORD THE RESULT IN COLUMN C.

Standard: Takes value of Upper Detector Currents and divides by Normalized value for each channel and records values in Column C.

Comment:

l

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A-2 Rev 1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION

( ./ Performance Step: 6 CALCULATE THE AVERAGE VALUE FOR THE UPPER AND LOWER NORMALIZED FRACTION AND RECORD IN COLUMN D OF ATTACHMENT 2.

Standard: 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.

Comment:

./ Performance Step: 7 USING THE FORMULA AND VALUES FROM ATTACHMENT 2 CALCULATE THE UPPER AND LOWER RATIOS Standard: 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.

Comment:

./ Performance Step: 8 PERFORM INDEPENDENT VERIFICATION OF ALL CALCULATIONS MADE ON ATTACHMENT 2 Standard:

Evaluator Cue: (If Candidate asks for independent verification)

For the purpose of this examination, there will be no independent verification of your work.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam SRO A-2 Rev 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION

( ./ Performance Step: 9 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 Standard: Acceptable band is +/- .5% (rounded to .005) around 1.0264 (1.0214 to 1.0314).

=

LOWER (Greatest) 1.0264 QPTR is UNSAT Evaluator Cue: After the SRO Candidate reports that QPTR is UNSAT, direct the candidate to evaluate Tech Specs for compliance.

Comment:

c- 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 Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION KEY A B C UPPER UPPER UPPER 100% POWER NORMALIZED UPPER DETECTOR DETECTOR CURRENT NORMALIZED CURRENT F(~ACTI~~

NOTE 1 N-41 INOPERABLE INOPERABLE INOPERABLE N-42 193.1 192.5 1.0031 N-43 217.6 218.1 0.9977 N-44 176.4 176.1 1.0017 SUM 3.0025/3 =

1.0008

( A B C LOWER LOWER LOWER 100% POWER NORMALIZED LOWER DETECTOR NORMALIZED FRACTION DETECTOR CURRENT CURRENT (NOTE 1)

N-41 INOPERABLE INOPERABLE INOPERABLE N-42 229.3 223.6 1.0254 N-43 237.1 240.6 0.9854 N-44 209.9 212.8 0.9863 SUM 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 Form ES-C-1 PERFORMANCE INFORMATION

( HARRIS 2009 NRC SRO JPM A2 Curve F-X-8 HANDOUT Revision Number: NRC Exam NIS Current Setpoint Table uA. 100% power i!~r~!ij:;,: fi!I[ljR~U~j;G:Ii~bHelf;,:;~>:: ;,<,  :,1;;;;:;: :i\~,::,J;;Qalllllll~lt9m~di::rj{t;(l;l]1~:,; ~!t,!'!::;;aO))Q~ll~I~~!~J!~l;{jlf:;;

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 Form ES-C-1 VERIFICATION OF COMPLETION

(

Job Performance Measure No.: 2009a NRC JPM RO A2 PERFORM A QUADRANT POWER TILT RATIO CALCULATION 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 SRO A-2 Rev 1

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET c 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.

INITIATING CUE: 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 C 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 I-INSlow position.

2009A NRC Admin Exam SRO A-2 Rev 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.:

Task

Title:

Determine TEDE While Working in a JPM No.: 2009a NRC JPM High Airborne Area 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 c Measure will be satisfied.

INITIAL The unit is being shut down for refueling and a planned crud burst is in CONDITIONS: 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.

Task Standard: 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 Form ES-C-1 Worksheet

( 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 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.

Time Critical Task: No Validation Time: 10 minutes 2009A NRC Admin Exam RO/SRO A3 Rev 1

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION Start Time: _ _ __

NOTE: Steps in this JPM may be performed in any order.

Performance Step: 1 Determines internal exposure while wearing a respirator Standard: Determines internal exposure to be ZERO while wearing a respirator Comment:

./ Performance Step: 2 Determines external exposure while wearing a respirator Standard: Determines external exposure to be 173.3 mRem TEDE while wearing a respirator (520 mRem I hr x 20 min =173.3 mRem)

Comment:

Performance Step: 3 Determines TOTAL exposure while wearing a respirator Standard: Determines total exposure to be 173.3 mRem while wearing a respirator

=

(0 mRem internal + 173.3 mRem external 173.3 mRem total)

Comment:

./ Performance Step: 4 Determines internal exposure while NOT wearing a respirator Standard: Determines internal exposure to be 20 mRem while not wearing a respirator (2.5 mRem I hr x 8 DAC-hr =20 mRem)

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam RO/SRO A3 Rev 1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 5 Determines external exposure while NOT wearing a respirator Standard: Determines external exposure to be 86.7 mRem TEDE while not wearing a respirator (520 mRem / hr x 10 min = 86.7 mRem)

Comment:

Performance Step: 6 Determines TOTAL exposure while NOT wearing a respirator Standard: Determines total exposure to be 106.7 mRem while not wearing a respirator (20 mRem internal + 86.7 mRem external = 106.7 mRem total)

Comment:

./ Performance Step: 7 Determines individual's total exposure for the year Standard: Determines individual's total exposure for the year to be 3835 mRem (3485 mRem + 349 mRem = 3835 mRem)

Comment:

./ Performance Step: 8 Determines individual's total exposure for the year if the work is allowed Standard: 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 UNSAT performance.

Comment:

./ - Denotes a Critical Step 2009A NRC Admin Exam RO/SRO A3 Rev 1

Appendix C Page 5 of 7 Form ES-C-1

. PERFORMANCE INFORMATION

./ Performance Step: 8 Determines if the individual can perform the work without exceeding Progress Energy's Annual Administrative Dose Limit of 4000 mRem Standard: 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)

Comment:

Stop Time:

Terminating Cue: When all calculations have been completed and the determination that work can proceed, this JPM is complete .

./ - Denotes a Critical Step 2009A NRC Admin Exam RO/SRO A3 Rev 1

Appendix C Page 6 of7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009a NRC JPM RO/SRO A1-1 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 Page 7 of7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: 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.

INITIATING CUE: 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 Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 345001H602 Task

Title:

CLASSIFY AN EVENT JPM No.: 2009a NRC JPM SROA4 KIA

Reference:

2.4.41 2.3/4.1 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 The operating crew was performing a rapid shutdown of the plant when CONDITIONS: they were forced to initiate a manual reactor trip.

Task Standard: Event classified as an Site Area Emergency (2-1-3)

Required Materials: None General

References:

PEP-110 EAL Flowpath (EP-EAL is an allowed reference)

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

Initiating Cue: 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.

Time Critical Task: Yes Validation Time: 15 minutes 2009A NRC Admin Exam SRO A-4 Rev 1

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

Performance Step: 1 OBTAIN EAL FLOW PATH.

Standard: Obtains EAL Flow Path. (EP-EAL is an allowed reference)

Comment:

.;' Performance Step: 2 CLASSIFY EVENT Standard: 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

( Evaluator Cue: END OF JPM Stop Time:

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 Form ES-C-1 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:

(

2009A NRC Admin Exam SRO A-4 Rev 1

Appendix C Page 4 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: The operating crew was performing a rapid shutdown of the plant when they were forced to initiate a manual reactor trip.

INITIATING CUE: 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

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET

( CLASSIFICATION INFORMATION SHEET 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 c**

2009A NRC Admin Exam SRO A-4 Rev 1