Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML103090054
Person / Time
Site:	Indian Point
Issue date:	09/17/2010
From:	Silk D M; NRC Region 1
To:	; Entergy Nuclear Operations
	Hansell S
Shared Package
ML100980645	List: IR 05000286/2010301; ML102670379; ML102720572; ML103080903; ML103080910; ML103080920; ML103080923; ML103090017; ML103090020; ML103090036; ML103090054; ML103410223;
References
	TAC U01789
	Download: ML103090054 (243)
	v • d • e

{{#Wiki_filter:Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 1 of 15 ENTERGY JOB PERFORMANCE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 2000771601-1.doc Difficulty: 3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 2 of 15 JPM Title: Calculate a Power Reduction Reactivity Plan per POP-2.1 JPM Number: RO A-1-1 KA Number and Importance: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. I R03.9 Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: 20 Min Actual Time: __ 2-POP-2.1 Operations at Greater than 45% Power File: 2000771601-1 .doc Difficulty

3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 3 of 15 INITIAL CONDITIONS: The Beacon Computer is out of service for maintenance. The plant has been operating at 100% (1080 MWe) power for 175 days following a refueling outage. Core Burnup is 6419 MWD/MTU 32 Heater Drain Pump must be removed from service to repair a valve packing leak. The SM has directed a power reduction to 70% Reactor Power in 3 hours to remove the heater drain pump. Reactivity Summary Sheet is not available Current RCS Boron Concentration is 1200 ppm Current Control Bank D position 230 Steps INITIATING CUES: You are the ATC and the CRS has directed you to perform a Power Reduction Reactivity calculation using Attachment 5 of 3-POP-2.1.

TASK STANDARD: Attachment 5 of POP-2.1 complete. File: 2000771601-1.doc Difficulty

3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 4 of 15 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Obtain current copy of 3-POP-2.1 Candidate will be given the procedure

.3. Attachment 1 step 1 Enter Total MW change Enters 324 (+/- 1) MW Attachment 1 step 1 Enter Rate of Shutdown Enters approx 108 MW/hr (+/- 1) 5. Attachment 1 step 1 Enter Start Time Enters Current Time 6. Attachment 1 step 1 Enter End Time Enters Start Time + 3 hours. .7. Attachment 1 step 2 Determine Power Defect from Graph RV-1 Enter 400 (+/- 3) pcm 8. Attachment 1 step 3 Determine Xenon Worth from Graph 3D Enter 18 (+/- 0.5) pcm 9. Attachment 1 step 4 Calculate total of steps 2 & 3 Enter 382 (+/- 3.5) pcm 10. Attachment 1 step 5 Enter Target Rod Position Enter 190 steps (No tolerance. From table) .11. Attachment 1 step 5 Enter Integral Rod Worth at 190 steps Enter 76.96 pcm (No tolerance. From table) '12. Attachment 1 step 5 Enter Current Rod Position Enter 230 Steps 13. Attachment 1 step 5 Enter Integral Rod Worth at 230 Steps Enter 0 pcm File: 2000771601-1 .doc Difficulty: 3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 5 of 15 STANDARD S/U STEP DESCRIPTIONS I CUES & NOTES Enter 76.96 (note this Attachment 1 step 5 14. is a negative number) Calculate Reactivity due to rods Sum Steps 4 & 5 Attachment 1 step 6 15. Enter 305.04 (+/- 3.5)Calculate Reactivity needed from Boric Acid pcm Attachment 1 step 7 Calculate the total amount of boric acid 16. Enter 150 (+/- 2) gal Step 6 +-2.03 JPM Complete. File: 2000771601-1.doc Difficulty: 3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 6 of 15 No: 3-POP-2.1 Rev: 53 OPERATION AT --GREATERTJtAN<l5"7'oPOWER Page 35 of 40 ATTACHMENT POWER REDUCTION REACTIVITY (Page 1 of The preferred reactivity calculation for planned power r eductions is the Beacon Summary provided by Reactor Engineering This worksheet s erves as an alternate method for reactivity calculations

1.0 RECORD

the following: Total MW Change 3.;) t.{ }..j W Rate of SID i b<il MW /'nr Start Time C u nel'\1 End Time C<<oen t I,of 3 DETERMINE Power Defect from 3-GRAPH-RV-1 OR the dally reactivity sheet (+)

3) pcm DETERMINE Xenon worth as follows; I.E Xenon equilibrium is AND 3-GRAPH-RV-3D has current cycle THEN USE 3-GRAPH-RV-30I.E Xenon equilibrium is NOT OR 3-GRAPH-RV-3D does NOT have current cycle THEN REQUEST Xenon worth from Reactor

(-) If>{! O.S.) pcm 4.CALCULATE the total of S J eps 2 and 3. 3<fl 1',\ ""'00 =(+)___ Step 2 Step 3 4ol'j It\" II ANSWER KEY 2000771601-1.doc Difficulty

3 Time: 20 minutes Task Number: 2000770101 2-POP-2.1 Administrative Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 7 of 15 No: 3-POP-2.l Rev: 53 OPERATION AT --UREA I ER I RARZl5'1o POWER Page 36 of 40-ATTACHMENT POWER REDUCTION REACTIVITY (Page 2 of 5.DETERMINE Reactivity due to control rods using 3-GRAPH-RV-13 AND 3-GRAPH-RV-7B. -Target Rod Position Control Rod P o sition Steps Integral Rod Wo rth pcm Current Rod Position Steps -D pcm {-)

pcm 6.0 CALCULATE the React i vity needed from Boric Ac i d by summing Steps 4 and 5. +(-)1/,.1 (,. =(+) 6'-!

7.0 CALCULATE

the total amount of Boric Acid needed. I lff.f (II/A) __----'pcm/gal =' 6 0'/ pem / _---=J.;.... gal ISlA (, 0 ) Step (from 3-GAAPH-AV-14. Reactivity Control Parameters. QB. Reactor Engineering) IIANSWERKEY II ..J 2000771601-1.doc Diff i culty: 3 Time: 20 minutes Task Number: 2000770101 2-POP-2.1 Administrative Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 8 of 15 3-GRAPH-RV-1 Rev 20' J TOTAL POWER DEFECT (for use with 3-S0P-RPC-003) CYCLE 16 (Page 1 of 2) 0.0 -200.0 -400.0 1600 ppm ----.--i -600.0 ---==i 1200 ppm --*-----i --------l-800.0 E --.. !-1000.0 t-.--O '. .-..It -'200.0 I ..J W Q a: W o *14000. Q. ..--.-------.-1800.0 __ ______ _ ..__ ... _.0 PIlm -2000.0 -..... ------. -. -----..... -----. --."..-... .. -", -...-.. -.__.u _ ..------. -.. -2200.0 --:....2400.0 r:*: -::. . . -2600.0 1-"---'-' _____.___.____ *1347.6 pcm .1400.5 pcm *1458.7 pcrn *1523.5pcm . 1595.9pcm

1732.5 pcm
1604.3pcm . 16t!1.2 pcm *2299.8pcm
2349.7 pcrn . . . . " .__ .. . ' *2401.9 pcm o 10 20 30 40 SO 60 70 60 90 100 (! l' . Writlen POWER LEVEL (%) BOL BORON =\800 ppm 10 1000 ppm --MOL BORON = 800 ppm to 400 ppm Reviewed ApproveO B . . EOl BORON = 200 ppm to 0 Effective Date: .1-16 .

[IANSWERKEY II Time: 20 minutes File: 2000771601-1.doc Difficulty: 3 2-POP-2.1 Administrative Task Number: 2000770101 -ill Dl = Cfl" CD .. ZN cO 38 0" --.I CD--.I -, -"" .. CJ) NO 0-"" 0'0:-" --.I --.10 OC) o r:-'o 0(')'"Uc ..... VJ -i b3' _. N ::lo iii' 3 _. iii :J0:: (1)CD Cfl r.n tn tn f POWER("fo) 0 10 15 20 25 30 35 45 50 5S 60 65 70 75 80 85 90 95 100 L' 3-GRAPH-RV-1 20 TOTAL POWER DE ECT (for use with 3-S0P*R . C-003) CYCLE 16 (Page 2 2) BOL "'0-.Res BORON CONCENTRATI:>N (ppm) 1000 1200 1400 1600 1800 400 _1iQ!l sao 0.0 0.0. 0.0 0.0 0.0 0.0 0.0 *106.6 *100.2 '95.0 *90.7 *87.1 '108.6 *101.8 *207.3 *195.5 *185.7 *177.7 -170.9 g:-214.2 -20 .2 -200.9 -302.9 *286.4 *272.7 -2612 -251 .S -317.1 -.6 -297,4 *394.0

356.2 -329.3 -417.6 .2 -391.8 -481.4 -457.2 -436.8 "'9.5 -5162 5 -464.1 ..9t*-59 .1 -574.6 *647.2 -616.6 -590.5 *568.1 48.6 *565.6 *538.1 -514.8 -494.9 -477.6 -708.4 -68$.2 -ti63.6 -726.5 -693.0 -664.3 -639.5 -617.7 -802.5 -775.9 -75 1.1 -304.0 -767.7 -736.3 -709.1 -685.1 -895.5 -8sS.4 -837.4 *880.1 -MO. 9 *807.0 *777.3 -751.0 -987.7 -gs.i.o -922.6 -955.0 -912.9 *876.3 442 -815.6 *1079.2
looM -10.289 -963.9 *94<4.5 -909.9 *878.9 *1170.0. *1128.7 -1090.1 '110.2.2 -10.54.0. *10.11 .8 -974.5 -941.1 '1260.4 *1215.0 -11n.7
1174.7
10.782 -1036.1 -1002.1 -1350.3 .1306.7 ,'254.5 '1246.7 *1 .0. *11 43.7 -1100.8 *10822 *1 439.8 .1385.9 -1335.7 *1316.1 -1259.9 *1208.5 -1162.6 -1121.3 -162Q.a *1470.6

' 1388.9 -1327.2 -1272.4 -1223.5 -1179.4 -1617.7 -1554.9 -1496.2 *1458.9 ' 1393.6 *1335.5 *1283.5 -1236.6 -1708.1 -\6311.6 -1575.6 -1 528.0. -1397.6 -1342.5 *1292.7 *1793.9 -1721.7 '1654.4 523.5 *1458.7 -1400.5 *1881.2 '1804.3 -1T32.5 Wnn.n BY: C£=-.._Re.iewed By: _ _ _____ AppmYed By'.. . ..:... _ _ _ _ ____ Eftecllve 0816: .. : __..._____ _ _ n 0)-(") C 0)... n> 0) "'0 EOL 0:e n>0 100 200 0.0 0.0 0.0. -159.9 '157.0 n> -Jl0.7 *305.3 -3002 Q,-453.6 -445.8 *438,4 *579.5 -569.9 -U C *719.7 *70 7.4 *695.7 CO _.-1144.7 -8302 --a16.5 -965.5 *948.9 *833.0 ('t) 0 *1082.8 -1()64.0 -1197.3 *11762 -11562 '1309.6 -1286.3 -1264.0. -1420.3 -1394.6 -1370.0. -n> -1529.9 *1501.7 .1474.7 ....... 0) *1638.8 *1807.9 *1578.5 0'1(,,)*1747.3 -1713.7 -1681.6 ...<'_. -1855.8 -1819.3 *1784.4 -1964.4 -1924.9 -18872 -2073.2 -20'30.7 '1990.0. *2182.4 -2 136.7 -2093.0. -2292.0. -2243.0 -2196.a *2401.9 *2299.8 "'0 0) "C n> "'0 0 "'0 I N. Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 10 of 15 3*GRAPH*RV*3D Rev. Xenon Reactivity Inserted for Various Rates from 100% Power, Equilibrium Cycle 15 EOL (25.445 I' -. ----._-.. -.---Written by: f-----.-f--------1--.-1-. Reviewed by: .. -.-..j ------.. --.--;---..-. _Approvedby: EHective Date: 0 1 I-Reacto at Hot Full Power --r-. '2 4 6 - --I--.1--'--' --+----.. .-.-'-_. --...-+---+--...-...----I--.-......-.-f---...... ..--8 10 12 14 16 18 20 22 Hours After Start of Shutdown File: 2000771601-1.doc Difficulty: 3 Time: 20 Task Number: 2000770101 2-POP-2.1 C -Ill Ill::': C/l 7' CD . . ZN C 0 38 rr --I CD--I .... -' .. Q) NO 0-' 0'--I a. --10 DC) o r:->o "U::ii On' "Uc N-? w -I bo Q.CD:3 .. _. N :::l 0 _.Qj ::J .... c CD (I) C/l [f) tJ1 tJ1 f 3-GRAPH-RV-7 Rev.11 AT POWER CONTROL BANK WORTH AS FUNCTION OF BANK POSITION CYCLE 16 (For Use wi h POP-2.1) a EQUIUBRIUM XENON C NDiTIONS BANKPosmON EOl ""C BOL MOUEOL BOUMOl dl MOL o Step. Wftbdr'8Wfl 150 MWDIMTU 6000 MWDIMTU 1 000 MWO/MTU 18000 MWO/MTU 25017 MWOfMTU om.....,U.1 Integnl 0111....1101 'Dllhranllal Integ..1 In....' B4NKC BANKO Rod Worth Rod Wot1h Rod Worth Rod Wot1h Rod WotIh Rod Wor1I1 (pom/.top) (pcm) {pcmtl18p, (JII;l!I) (p<OnIslep) (pcm) om-t>ta, \nbIgraI RodWonh Rod Wortn (pemlstop) (pom' (") S>> S>> -C') (I) -S>> 0IftwM1Ial Rod Wco1h Inlegnol Rod WortII (I) (pcmI.lop) (pcm) 230 no 230 230 230 230 230 230 230 230 230 230 230 230 Z30 Z30 230 2.10 2:)() 2.30 230 230 230 230 230 227 22. 220 2 18 215 212 210 206 203 200 197 194 190 188 182 160 1 7 6 173 170 167 154 160 ""C WritlenB. o Reviewed ""C ApprOll8d _ .. _ Efleclive N 4096pcm 4485 pcm 0.00 0.62 1.24 2.07 2.36 2.80 3.24 3.53 3.56 3.58 3.80 3.60 3.59 3.59 3.57 3.54 3.51 3.49 3.48 3.4< 3.42 3.41 340 3.39 0 .00 3. It 6.22 10.37 15.97 24.36 32.76 38.36 52.62 63.31 74.00 B4.71! 9556 Hl9.!14 117.Q2 127.63 138.24 145.31 ISO.13 169.49 179.l14 100.00 200.27 213.88 0.00 0.28 0.57 0.95 1.20 158 1.95 2.20 2.47 2.66 2.66 3.01 3.16 3.36 3.42 3.51 3.511 3.66 3.73 3.110 3 .66 3.92 3.117 * .05 0.28 105 181 2.83 3A3 5.24 5.85 6.72 7.10 710 711 7.12 7.02 8.88 6.73 6.604 6.47 6.31; 6.22 6.13 6 .06 5.93 \O..1.43 2.85 4.75 7.91 12.S. 17.37 20.52 3066 38.25 45.8' 56.18 64.51 7. 94A9 105.00 112.02 127.04 138.30 149.67 161.43 173.29 189.11 0.00 0.32 0.63 1.05 1.38 1.83 2.29 2.60 3.01 3.31 3.62 3.79 3.97 4 2 1 4.26 4.40 '.44 ' .48 4.51 4.54 4.56 4.57 * . 59 0.00 1.58 3.15 5.26 8.92 14.40 19.89 23.55 35.98 45.31 54: 6<1 66.38 78.11 93.75 102.42 115.39 1211.37 137.D3 ISS.oo 166.48 181.96 195.66 209.35 227.62 0.00 0.51 1.02 1.69 215 2.a. 3.53 3.99 4.52 4.92 5.33 5.46 S59 sn &.75 5.72 5.69 5.tr7 5.56 5.51 5.'5 5.35 5.32 5.23 0.00 2.54 5.06 8.,6 14.14 22.66 31.\6 36.66 55.48 69.45 83.'2 100.06 116.71 138.90 150.34 18 7.49 184.85 196.09 218.32 234.l1li 251.88 287.66 283.71) 305.07 0 .00 9.33 15.54 24.22 37.2.1 5024 58.91 114.80 10422 123.63 166.27 19-4.71) 208.45 2211.06 249.71 .26-1.47 2119.19 3011.48 327.78 346.00 36423 388.53 :;0 (I) Q) C') to CD -" o =:::s 0:;0........ (]'IC')-""C S>>:::s "C (I) I ---Ill 3-GRAPH.RV-13 Rev.7 III = o BANK POSITION TO MAINTAIN[HFP TARGET FLUX DIFFERENCE n ZN Cye E16 0)C 0 38 230 n Written By rr--.AI' . c 0'" -...J (1) -...J --, ...... 220 Reviewed By:-./.' : ., m iii'Approved By:_._ __ . /./' ' NO 0 ...... 210 EHective Date: >" ..,.' CD 0' ___._ _1-,( ...-0)0:-" -...J 0-200 -...JO on l\l ." ...... o 190 o ...... ;:"".-180 CD..,--<--".. .-. ,......---. 1 7 0 J MOL :::0.... CD o ..Q.160 ""OC 01) g. 150 , Q) n , ('l) _.NO Vi-o=ii -;; 140 (0 -o On' .2 "Uc , ;:::::;: 130 ,/ 0:::0 o -CD ...... 11. ......0)-' BANK 0 POSTION (Steps Withdrawn) w o 120 (JIn-" /;; 110 SOL EOl Ql l! -<' 100 t--------"t---------t-;=::::::::::--t--------t--- 30 156 160 45 , 40 164 166 101 90 ." I "'r--... 50 172 172 157 Z 0) 181 179 169 80 EOl 70 190 186 181 /

80 201 195 193 "C 70 CD , C/l 90 211 205 204 .., 60 , ' 100 230 230 230 ." :b 3' 50 ." Q.(1) -I :I tr1 o I:3_. " N 40 N I :'0 o 40 SO 60 70 80 90 1 00 -a. .., _. Relative Power (%)Qi :J <"_c CD m (b (J)

I I Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 13 of 15 CONTROLLED 3-GRAPH-RV-14 Rev. 3 REACTIVITY CONTROL PARAMETERS -.. IP3 Cycle HI

2000 MWQIMI!.I& E.Qi. 6000 Cycle Burnup (MWD/MTUI

= 150 12000 25017 Specllled Boron Concenlrallon (ppm) '" 974 1194 100! 100 100 100 100 Relative Powerj%l" 100 -is.1 -29.8*10:9 Moderato,.lemperalure Coefflclenl (perrilFl. -'2.9 -12.7 -17.2 Isothermal Temperature Coefficient (pcm/F) = -'4.6 -33.' -221 .9 -173.9 -252.8 Moder.tor Temperature Defeet (pcm) .. -557.6 -S.9 -8.6 -S.8 -8.9 Doppler Power Coefficient (pcml"l. power) * -1.3 -1.3 -1.4 -1 .4 Doppler Temperature Coefficient (pemlF) .. -l1n.2 -1221.0 Do"ppler Power Defect (pcm) " -'177.3 -1173.8 -12.6 *14.7-13.8 -21.3 Total Power Coefficient (pcml"l. power). -1440.3 -1663.S -2349.7 Tota' Power Defect (pcmi .. *1606.0 -206.S -S9.1 Axial ReactlvilY Redistribution Defect (pcm) .. -190.0 -618.3 Control Banks Diff..rential Rod Worth -C bank and 0 bank (pcmlstep) .. Control Bank 0 AVer89" Differential Rod Worth 1 00 to 223 steps (pcmlstep) Control Bank D Power Worth (stepel%) " Hlgheet Worth Stuck Rod (pcm) " Dropped Rod Worth (pcm) = / . '-Bontloa WOr:lb (pcmigaJ) = Dilution Differentia. Power Worth (No Rod Motion) (9all%) Boration Differential Power Worth (No Rod Motion) (gaJIV.) ,. Differential Boron Worth (pcmlppm) " BoreUon (using 12_5 % Boric Acid) (gal/ppm) = Dilution (Pure Makeup Water) (gal/ppm) = Boron Dilution Worth (pcm/gal) = Other Parameters Pressurizer Level Pressurizer Pressure Sleam Dump Steam Flow 4.7 5.0 5.2 6.6 3.1 -4 948(N-ll) 100.0 -6.316 3.1 66 -0.096 -2_04 3.4 -4 100.0 -6.289 3.1 54 -0. 116 3.7 -4 100.0 -6.687 3.1 64 -0.104 *2.16 5.4 -4 762 (K-IO) 100.0 -8.199 3.0 645 -0.013 -2.73 144 108 141 1675 6.8 6.2 6.8 7.8 Hot -75 Cold -125 I"F , n 1% 6 ANSWER KEY \I 1% 6 pzr Level 1011 6 Press 1°F 6 Tavg 16 Press when solid -.1.75% Steam FlowfOF Temp. Error Above S'F Dead Band Using Ina above informa t ion, other conlrol parameters CaIl easily be derived if Ihe desired units are known. Linaar i nterpolation ollhe abOve data for other limes in core life (a particular core burnup) can be perlormed and obtain good accurat:y.

Reference:

Cycle 16 NuPQP Rev. 0 (WCAP-170S0-P). HOI lull power. ali rods out condillons are assumed In Ihe above. Wrinen By:: . Reviewed By:. Approved By:q+;E.Ellective Dale: ::r ,lg'oq Time: 20 minutes Difficulty: 3 File: 2000771601-1.doc Administrative 2-POP-2.1 Task Number: 2000770101 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 14 of 15 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 2000771601-1 .doc Difficulty: 3 Time: 20 Task Number: 2000770101 2-POP-2.1 Page 15 of 15 INITIAL CONDITIONS: The Beacon Computer is out of service for maintenance. The plant has been operating at 100% (1080 MWe) power for 175 days following a refueling outage. Core Burnup is 6419 MWD/MTU 32 Heater Drain Pump must be removed from service to repair a valve packing leak. The SM has directed a power reduction to 70% Reactor Power in 3 hours to remove the heater drain pump. Reactivity Summary Sheet is not available Current RCS Boron Concentration is 1200 ppm Current Control Bank D position 230 Steps INITIATING CUES: You are the ATC and the CRS has directed you to perform a Power Reduction Reactivity calculation using Attachment 5 of 3-POP-2.1 . File: Task Number:

Perform Reactor Vessel Venting Time Calculation per Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 0001251601-1 .doc Difficulty: 2 Time: 15 Task Number: 0001250501 3-FR-1.3 ---Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 2 of 8 JPM Title: Review Reactor Vessel Venting Time Calculation JPM Number: RO A -KA Number and Importance: 2.1.25 Conduct of Operations Ability to interpret reference materials such as graphs, tables RO -Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: 15 Min Actual 3-FR-1.3 Response to Voids in Reactor Vessel File: 0001251601-1 .doc Difficulty: 2 Time: 15 Task Number: 0001250501 3-FR-1.3 ". Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 3 of 8 INITIAL CONDITIONS: An event occurred 24 hours ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. Containment pressure 2.5 psig Containment temperature 160°F Containment hydrogen cone 1.0% RCS 1000 psig INITIATING CUES: You are the ATC and the CRS has directed you to perfom the Reactor Vessel Venting Time calculation in accordance with FR-1.3 Attachments 4 & 5. TASK STANDARD: Calculation reviewed and errors identified. File: 0001251601 -1.doc Difficulty

2 Time: 15 Task Number: 0001250501 3-FR-L3 Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 4 of 8 Denotes Critical Step STEP DESCRIPTIONS I CUES &NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Obtain Current Rev of Procedure Candidate will be given procedure

.3 Determine Containment Volume at STP (A) Calculates 2.41E6 to 2.43E6 .4 can be vented Determine Maximum Hydrogen volume that (8) Calculate 4.82E4 to 4.86E4 .5 Determine Hydrogen flow rate as a function of RCS pressure (C) 2900 to 2950 . 6 Calculate maximum venting time Calculate 16.3 to 16.7 minutes JPM Complete File: 0001251601-1.doc Difficulty

2 Time: 15 Task Number: 0001250501 3-FR-1.3 Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 5 of 8 Number: 3*FR-I.3 litle :

TO VOIDS I N REACTOR VESSEL Rev -; 5 i on Plumber : lJ 4 1 of 1) INSTRUCTIONS FOR DETERMINING VENTING TIME I I DETERMINE Containment at STP -A -( 2.61 xl 0 6 Ft 3 ) x _______ x __14.7 T where P (psig) -C ontainment pressure (psig) + 14 . 7 T ( OR) -Conta i nment temperature(OF) + 460 11.;)..A -( 2.61xl06 Ft 3 ) x 4!/Z°R 14.7 psia A -.'B. cfo

2. DETERMINE Milximulli Hydrogen volulIIe that can be vented -B. -B -(3$ --Containment Hydrogen Concentration) x A 100SB -_.-J'1 CL11 ,i u..Y....t:;'g;.u ()'--_ __F t 3

3. DETERM1NE Hydrogen flow rate as a funct10n of ReS pressure -e a. RCS pressure . bDETERMINE Hydrogen f l ow rate using Attachment

5. HYDROGEN FLOW RATE VERSUS RCS PRESSURE, Page 29. C a J1ot> -SCFM ANSWER KEY CALCULATE maximum venting Max i mum venting t i me Maximum v e nt i ng time -lit.? -END O F ATT A CHMENT* Page 2 8 o f 2 9 File: 0001251601-1

.doc Difficulty

2 Time: 15 Task Number: 0001250501 3-FR-1.3 I

Perform Reactor Vessel Venting Time Calculation per Page 6 of Nu m ber : Title : Revision Mumbfr: 3 -FR-I_3 RESPONSE 10 VOIDS IN R£AC10R v[SSH o !! (Attachment page 1 of 1) HYDROGEN FLOW RATE VERSUS ReS PRESSURE FLOIolRATE (SCFM) 0 250 500 7S 0 1000 1 2S 0 ]SO O 1 7S0 2 00 0 2 250 RC S PRe SS UR[ (P S IG) 8000 ANSWER KEY 5000 V '" ., c:' ./4000 //3 000 /./2 000 / 1000 / I" 0 V / V -END OF ..P age 2 9 of File: 0001251601-1 .doc Difficulty

2 Time: 15 Task Number: 0001250501 3-FR-1.3 Perform Reactor Vessel Venting Time Calculation per FR-I.3 Page 7 of 8 Any area of weakness observed?

YEsDNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: I Answer Key File: 0001251601-1 .doc Difficulty: 2 Time: 15 Task Number: 0001250501 3-FR-1.3 Page 8 of 8 INITIAL CONDITIONS: An event occurred 24 hours ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. Containment pressure 2.5 psig Containment temperature 160°F Containment hydrogen conc 1.0% RCS 1000 psig INITIATING CUES: You are the ATC and the CRS has directed you to perfom the Reactor Vessel Venting Time calculation in accordance with FR-1.3 Attachments 4 & 5. Task I , \ Perform a Peer Review of a Surveillance Test Page 1 of 8 ENTERGY (IP2) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 2000701602-1.doc Difficulty: 2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 ---Perform a Peer Review of a Surveillance Test Page 2 of 8 JPM Title: Perform a Peer Review of a Surveillance Test JPM Number: RO -A -2 KA Number and Importance: 1940012212 Equipment Control Knowledge of surveillance procedures. RO -3.7 Suggested Environment: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 20 Min Actual Time:

References:

3-PT -Q092B 32 Service Water Pump IP-SMM-DC-904 Surveillance Test Program File: 2000701602-1 .doc Difficulty: 2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 Perform a Peer Review of a Surveillance Test Page 3 of 8 INITIAL CONDITIONS 3-PT-Q092B 32 Service Water Pump Quarterly Test was completed. INITIATING CUES: You are the Spare RO and the CRS has directed you to perform a Peer Review of the Surveillance Test in accordance with IP-SMM-DC-904. Todays Date 6/11/2010 TASK STANDARD: Surveillance Test Reviewed and Errors Identified. File: 2000701602-1.doc Difficulty: 2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 Perform a Peer Review of a Surveillance Test Page 4 of 8 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Commence evaluation

1. 2. Obtain current copy of IP-SMM-904 CUE: Candidate given procedure Document Review on Attachment 10.2 3. Calibration due dates recorded Identifies dates recorded 4. Instruments within calibration Identifies dates within calibration

5. Changes documented by TPC Identifies NA 6. All required procedural steps completed Identifies step 4.2.7 NOT signed off 7. All steps NOT completed noted & explained in Comments Section Identifies step 4.2.7 not signed off 8. All corrections lined out, dated and initialed Identifies correction on page 12 is correctly lined out, dated and initialed

9. All Calculations Correct NOTE: On page 14 step 4.2.15 data is incorrectly transcribed.

The calculation is correct; however it is OOS Identifies calculations correct .10. All data properly transcribed Identifies step 4.2.15 pump discharge pressure not properly transcribed from page 12 to page 14 11. Required CRs, WOs, PFs, or CTSs etc initiated Identifies NA File: 2000701602-1 .doc Difficulty: 2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 , Perform a Peer Review of a Surveillance Test Page 5 of 8 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 12. Operability conclusions correct Identifies conclusions correct for the corrected data on _page 12. 13. Overall acceptance conclusions correct Identifies conclusions correct for the corrected data on page 12. JPM Complete File: 2000701602-1.doc Difficulty

2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 I Perform a Peer Review of a Surveillance Test Page 6 of 8 -E t ".." , 11 erp,y IPEC SITE MANAGEMENT QUALITY RELATED ADMINISTRATIVE PROCEDURE IP*SMM DC-904 Page Revision 3 20 of 20 MANUAL INFORMATIONAL USE ATTACHMENT 10.2 PEER REVIEW SHEET PEER REVIEW SHEET PROCEDURE NUMBER: 3 -\'IF Qltl.:> DATE PERFORMED: -I 0-I COMMEN T S: ./ v' ,/ ./ ./ r/ V* I,/"" I-{-5"", tf.').7 not

'# ts-+cp (lUW\ple-k) 7f(Yd,,/ trd"jCflbed -for" perfo' rl\Id hplV(l)t( tlv ANSWER KEY PEER REVIEWER: ;;e File: 2000701602-1 .doc Difficulty

2 Time: 15 minutes Task Number: 2000700102 IP-SMM-DC-904 Administrative Perform a Peer Review of a Surveillance Test Page 7 of 8 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 2000701602-1 .doc Difficulty
2 Time: 15 Task Number: 2000700102 IP-SMM-DC-904
, Page 8 of 8 INITIAL CONDITIONS 3-PT-Q092B 32 Service Water Pump Quarterly Test was completed. INITIATING CUES: You are the Spare RO and the CRS has directed you to perform a Peer Review of the Surveillance Test in accordance with IP-SMM-OC-904. Task I Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 1 of 8 ENTERGY JOB PERFORMANCE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 0350041602-1 Difficulty: 2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 ---Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 2 of 8 JPM Title: Perform a SG Tube Leak Determination using SG-1 JPM Number: RO -A-3 KA Number and Importance: 2.3.14 Radiological Controls Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. RO -3.4 Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: 15 Min Actual 3-AOP-SG-1 Steam Generator Tube Leak File: 0350041602-1 Difficulty: 2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 3 of 8 INITIAL CONDITIONS: Radiation Monitor 15 is in alert. The operating crew is responding in accordance with 3-AOP-SG-1 Steam Generator Tube Leak. Condenser air in leakage is 2.5 SCFM Given the attached Leakrate Log INITIATING CUES: You are the BOP and the CRS has directed you to estimate the SG Tube Leakage. TASK STANDARD: SG Tube Leakage calculated using 3-AOP-SG-1 Attachment
1. File: 0350041602-1 Difficulty

2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 4 of 8 Denotes Critical Step STANDARD S/U STEP DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation Candidate may use Enter data Attachment 1 or separate paper Determines

2. R-63 is 1.49 X j.Jci/cc 3. Calculate average R-63 Determines SG Tube 4. Calculate SG Tube Leakage for 1215 Leakage is 15.12 gpd Determines SG Tube Calculate SG Tube Leakage for 1230 5. Leakage is 15.36 gpd Determine delta leakrate is .24 gpd over last 15 minutes. .6. Calculate Delta Leakrate Extrapolated over one hour increase is .96 gpd/hr. Enters Rad Monitor or some equivalent to 5. Enter Rad Monitor in "Method Used" column indicate use of R-15 & R-63s to calculate leakrate.
JPM Complete File: 0350041602-1 Difficulty
2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 5 of 8 Page 1 of 1 If leak rate is unknown, take data every 15 minutes until leak rate is determined. If leak is 75 gpd, take data every 15 minutes. If leak 30 gpd but < 75 gpd AND unstable, take data every 15 minutes. If leak 30 gpd but < 75 gpd AND stable for at least 1 hour (::; 10% increase in 1 hour), take data every 2 hours. If leak < 30 gpd, take data once every 8 hours. R-63 **DELTA Current* Method Used To R-15 LEAKRATE Leakrate Time (!lCi/ee)
Determine*Date (!lCi/ee) gpm (gpd) gpm (gpd)/hr Leakrate A B 1.9 X 10.2 1.09 X 10.2 8.37 X 10-6 1215 Today 15.12 gpd 1.9 X 10.2 1.09 X 10.2 8.5 X 10-6 Today 1230 15.36 gpd 0.96 gpd/hr Answer Key The DATE is required to be recorded in the f i rst entry and when the changes: otherwise, the DATE may be left ** DELTA LEAKRA TE is determined by subtracting the previous period leakrate from the CURRENT LEAKRATE (extrapolate result out to one hour). Use a minus (-) to indicate decreasing leakrate. File: 0350041602-1 Difficulty: 2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 6 of 8 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 0350041602-1 Difficulty
2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Page 7 of 8 INITIAL CONDITIONS:
Radiation Monitor 15 is in alert. The operating crew is responding in accordance with 3-AOP-SG-1 Steam Generator Tube Leak. Condenser air in leakage is 2.5 SCFM Given the attached Leakrate Log INITIATING CUES: You are the BOP and the CRS has directed you to estimate the SG Tube Leakage. Task Page 8 of 8 Page 1 of 1 If leak rate is unknown, take data every 15 minutes until leak rate is determined. If leak is 75 gpd, take data every 15 minutes. If leak 30 gpd but < 75 gpd AND unstable, take data every 15 minutes. If leak 30 gpd but < 75 gpd AND stable for at least 1 hour 10% increase in 1 hour), take data every 2 hours. If leak < 30 gpd, take data once every 8 hours. * ** Time 1215 1230 R-63 Current **DELTA Method Used To R-15 *Date Leakrate LEAKRATE Determine A B gpm (gpd) gpm (gpd)/hr Today 8.37 X 10-6 1.09X 10.2 1.9X10*2 Today 8.5 X 10-6 1.09 X 10.2 1.9X 10.2 The DATE is required to be recorded in the first entry and when the date changes: otherwise, the DATE may be left blank. DELTA LEAKRA TE is determined by subtracting the previous period leakrate from the CURRENT LEAKRATE (extrapolate result out to one hour). Use a minus (-) to indicate decreasing leakrate. Leakrate FileTask Number
Review a Gross Leakrate Determination Calculation Page 1 of 10 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the autl1orization of the Manager, Nuclear Training. File: 2000051602.doc Difficulty: 3 Time: 20 Task Number: 2000050102 0-SOP-LEAKRATE-001 ---Review a Gross Leakrate Determination Page 2 of JPM Title: Review a Gross Leakrate Determination Calculation JPM Number: SRO-A 1-1 KA Number and Importance: 1940012107 Conduct of Operations -Ability to evaluate plant performance and make judgments based on operating characteristics, reactor and instrument SRO -Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: 20 Min Actual o SOP LEAKRA TE-001 RCS Leakrate Surveillance, Evaluation and Leak Identification File: 2000051602.doc Difficulty: 3 Time: 20 Task Number: 2000050102 O-SOP-LEAKRATE-OO 1 Review a Gross Leakrate Determination Page 3 of INITIAL CONDITIONS: The plant has been operating at 100% Power for 200 An increase in containment humidity has been The PC program for leakrate calculation is not An RO performed a Gross Leakrate Determination in accordance with LEAKRA Non-RCPB Leakage from previous evaluation 0.15 Previously identified leakage from previous evaluation 0.03 INITIATING CUES: You are the CRS and the SM has directed you to review the Gross Leakrate Determination. TASK STANDARD: Gross Leakrate Calculation reviewed and errors found. File: 2000051602 .doc Difficulty
3 Time: 20 Task Number: 2000050102 0-SOP-LEAKRATE-001 Review a Gross Leakrate Determination Page 4 of Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Obtain current copy of procedure Candidate will be given the procedure

3. Evaluate Manual Calculations See Below Attachment 1 Step 1 a Calculate Total Time Determine Total Time is 127 minutes NOT 137 minutes 5. Attachment 1 Step 1b Calculate Change in Mass due to Change in Pressurizer Level Determine 6.26 gallons is correct 6. Attachment 1 Step 1 c Calculate Change in VCT Mass due to change in level Determine 104.48 gallons is correct 7. Attachment 1 Step 1 d Calculate Change in RCS mass due to change in Tavg Determine
-8.64 is incorrect it should be + 8.64 gallons 8. Attachment 1 Step 2 Calculate Gross Leakage Determine 102.1 is incorrect; it should be 119.38 gallons 9. Attachment 1 Step 2 Calculate Gross Leakage LR1 Determine 0.74 gpm is NOT correct; it should be 0.94 10. Attachment 1 Step 3 Calculate Unidentified Leakage Determine 0.56 gpm is NOT correct; it should be 0.76 gpm 11. Attachment 1 Step 5 Candidate does Not Sign the form 12. JPM Complete File: 2000051602.doc Difficulty: 3 Time: 20 Task Number: 2000050102 O-SOP-LEAKRATE-OO 1 Review a Gross Leakrate Determination Page 5 of Res LEAKRATE SURVEILLANCE, No: O-SOP-LEAKRATE-001 Rav: 1 EVALUATION AND LEAK IDENTIFICATION Page 490'63 CALCULATING GROSS RCS (Page 1 of Date: T"DA '-f NOTE: PERFORM Ihis attachmenl only when PZR Is 2200 psi and 2245 psi, --Q.B. TAVO Is 563 of AND T AVO is within +/-1.5°F from T RI!JO. 1.RCS Manual Leakrate Calculation Worksheet: Circle one: Unit 2 ( ): Indicates mathematical sign must be observed. .) CALCULATE lolal time [1J Answer Key Final: Time i d. d l[ Initial: T1me Elapsed Time b) Change In R volume change. 'If '. \ ... -'---=FI=-na-:I-': PZR Level --:,i.J..:.,;7 ,;,.;.0____% Initial: PZR Level -_ej*..;..I..;..I ____ % Difference: H,_O ,,-'-,-\____'Yo X ( -62.6 gaU%) = (+) I., J (,. gal (0] [AJ c) Change In VCT Mass due to change in VeT Level [B], [E] is the normalized VCT volume change. Final: VCT Level Initial: VCT Level Difference: H 'i , 4 J % X (-19,1 gaV%) =(I-}I Q\/. tf,? gal IE] IS] d) Change In RCS Mass due to change in TAVE eel. CFJ is normalized RCS Water Volume change. Final: TAVE :5 C*q. C I OF Initial: T AVE :H S. '1 OF 8.L' Difference: (-) o.i .q OF x (86.444 g =:: 8. V i Ie] File: 2000051602.doc Difficulty: 3 Time: 20 Task Number: 2000050102 O-SOP-LEAKRA TE-OO 1 _____________________________________ __ i Review a Gross Leakrate Determination Page 6 of RCS LEAKRATE SURVEILLANCE, No: O-SOP-LEAKRATEoOO1 Rev: 1 EVALUATION AND LEAK IDENTIFICATION Page SOot 63 CALCULATING GROSS RCS (Page 2 of Answer Key 2.0 in System Volume Leakage {LRd 6, 1') gpm b) RECORD previously i dentif i ed Leakage (from previous Evaluation [LAsD: 0, C I ) gpm A poslUve number indicates a net removal of mass from the system. __gpm -00 lLRa] 1_---"'0'-,_'[LRa] RECORD (LR,l and (LR UnldenlmeoU on the applicable lines of step 5.0.
Use two decimal places to the right of the decimal point for the final value (I.e. 0.04 gpm). !E there is an unant i cipated gross ieakage increase of 0.05 gpm. QB it has been 7 days since section 4.4 or 4.5 was iast performed, THEN PERFORM section 4.4. or 4.5 RCS Leak Rate Evaluation as soon as practical.
a) REFER TO Section 4.3, for Review and Approval of G r oss Leakage Calculation. b) WHEN sac1lon 5.0 is c.Q/ll_tl!l!t:-, ---__ THEN PLACE co ted forms in appropriate CC Gross Leakage (LR,]: 0.1\ O.qy Q,')k , Reviewed by:--:=-:-:--- ______--:::---:- ________=-__ (CRS/SM) Print name Date File: 2000051602 .doc Difficulty
3 Task Number:
Time: 20 minutes 0-SOP-LEAKRATE-001 Administrative Review a Gross Leakrate Determination Calculation Page 7 of 10 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 2000051602 .doc Difficulty
3 Time: 20 Task Number: 2000050102 O-SOP-LEAKRA TE-OO 1 Page 8 of 10 INITIAL CONDITIONS:
The plant has been operating at 100% Power for 200 An increase in containment humidity has been The PC program for leakrate calculation is not An RO performed a Gross Leakrate Determination in accordance with LEAKRATE-001 Non-RCPS Leakage from previous evaluation 0..15 Previously identified leakage from previous evaluation 0.03 INITIATING CUES: You are the CRS and the SM has directed you to review the Gross Leakrate Determination. Task Number Page 9 of 10 r RCS LEAKRATE SURVEILLANCE, No: O-SOP-LEAKRA TE-001 Rev: 1 EVALUATION AND LEAK IDENTIFICATION Page 49 of 63 ATIACHMENT2 CALCULATING GROSS RCS LEAKAGE (Page 1 of 2) Date: T Dl)A \(, !:!QI!: PERFORM this attachment only when PZR is 2:. 2200 psi and 2245 psi, OR TAVG Is Z. 563 OF AND TAW is within +/-1 .5°F from T REF. 1.0 RCS Manual Leakrate Calculation Worksheet: Circle one: Unit 2 ( ): Indicates mathematical sign must be a) CALCULATE tolal time Final: Time I). : <+ Initial: Time W: IElapsed Time __ mlnutn b) Change in RCS mess due to change in PZR Level [AJ. [OJ Is normalized PZR volume change. \ * )-------cFl=-na--=-':----;PZR Level _"lc...:'l.;... C=-' _____ % Initial: PZR Level -_ 1/...:,.')-'1____-% Difference
H tJ \ % X (
62.6 g8U%) =(t) / .* J r... gal [0] [A) c) Change In VCT Mass due to change In VCT Level IS]. [E] is the normalized VCT volume change. Final: VCT Level initial: VCT Level DiHerence: H 5 47 % X (-19.1 \jBlf"/o)
=(0 IJBI [EJ [Bj d) Change in RCS Mass due to change in TAVE Ie]. [F] is normalized RCS Water Volume change. Final: TAVE 5V1.0 OF Initial: T AVE j %.'1 OF ) Difference
(-) D.I Ie] OF X (86.444 gall"F) = (-) ,; .t {/ gal [F] FileTask Number Page 10 of 10 RCS LEAKRATE SURVEILLANCE, No: O-SOP-LEAKRA TE-Q01 Rev: 1 EVALUATION AND LEAK IDENTIFICATION Page 50 of 63 CALCULATING GROSS RCS (Page 2 of 2.CALCULATE: Gross leakage (gpm) [LR1]: =[(Normalized values: ([0] + [E] + [F]) / 6 Time (minutes T)] == ([0] klL+ (E) + [F1.:1.J2L ) = I OJ., (G) gal. Change in System Volume '" I 0') .1 (G) gal. / T .. D. ) L{ gpm Gross Leakage [LRd a) RECORD Non-RCPB Leakage (from previous Eva l uation [LR2I): 6.1 '5-gpm b) RECORD previously Ident i fied Leakage (from previous Evaluation
[LR,D: (\ 0) gpm A positive number indicates a net removal of mass from the system. wi ' 3.0 CALCULATE Unidentified Leakage: Q.74 gpm-0.\ <; gpm-0. 0,) gpm.. D ,'; L* gpm[LR Unidelllltlell] RECORD [LR 1] and [LR Unidontlll.] on the applicable IIne6 of step 5.0.
Use two decimal places to the right of the decimal point for the final value (I.e. 0.04 gpm). IE there is an unantic i pated gross leakage increase of 0.05 gpm , OR It has been 7 days since section 4 .4 or 4.5 was last perlormed.
THEN PERFORM section 4.4 , or 4 .5 RCS Leak Rate Evaluation as soon as practical. a) REFER TO Seel i on 4 .3 . for Review and Approval of Gross Leakage Calculation. b) WHEN seelion 5.0 is completed, THEN PLACE completed forms in appropriate CCR binder. Gross Leakage [LR 1:_-, O,,-'________1 ,gpm Unidentified Leakage [LR unldontlfled!: O. 'l{., Performed by: '2.> ,'),:-1'-" (' p t A-d l i1t I./),df tr J Reviewed _______ __________(CRSlSM) Print name Signature Date ________________________________________ __ FileTask Number
Review Reactor Vessel Venting Time Calculation per Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 0001251602-1 .doc Difficulty: 2 Time: 15 Task Number: 0001250502 3-FR-1.3 ---Review Reactor Vessel Venting Time Calculation per FR-1.3 Page 2 of 8 JPM Title: Review Reactor Vessel Venting Time Calculation per FR-1.3 JPM Number: SRO A 2 KA Number and Importance: 1940012125 Conduct of Operations -Ability to interpret reference materials such as graphs, curves, tables etc. SRO -4.2 Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: 15 Min Actual 3-FR-I.3 Response to Voids in Reactor Vessel File: 0001251602-1 .doc Difficulty: 2 Time: 15 Task Number: 0001250502 3-FR-1.3 Review Reactor Vessel Venting Time Calculation per FR-1.3 Page 3 of 8 INITIAL CONDITIONS: An event occurred 24 hours ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. The TSC has calculated Reactor Vessel Venting Time in accordance with FR-1.3 Attachments 4 and 5 using the following information. Containment pressure 2.5 Containment temperature Containment hydrogen conc RCS pressure 1000 INITIATING CUES: You are the CRS and the SM has directed you to review the Reactor Vessel Venting Time calculation. TASK STANDARD: Calculation reviewed and errors identified. File: 0001251602-1.doc Difficulty
2 Time: 15 Task Number: 0001250502 3-FR-1.3 Review Reactor Vessel Venting Time Calculation per FR*I.3 Page 4 of 8 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Obtain Current Rev of Procedure Candidate will be given procedure 3 Determine Containment Volume at STP (A) Calculates 2.42E6 Determines TSC did not add 460 0 .4 Determine Maximum Hydrogen volume that can be vented (8) Note this is incorrect because previous calculation was incorrect.
Calculate 4.84E4 to 4.86 E4 5 Determine Hydrogen flow rate as a function of RCS pressure (C) 2850 to 2950 6 Calculate maximum venting time Note this is incorrect because previous calculation was incorrect. Calculate 16.4 to 17.0 minutes JPM Complete File: 0001251602-1 .doc Difficulty
2 Time: 15 Task Number: 0001250502 3-FR-1.3 Review Reactor Vessel Venting Time Calculation per FR-1.3 Page 5 of 8 Nullltltr:
3-FR -J.3 Tit Ie: RESPONSE TO VOIDS IN REACTOR VESSEL s 1011 Nulllber; {) Attachment 4 (Attachment page 1 of 1) INSTRUCTIO"S FOR PETERMINING VENTING TIME 1_ DETERMINE Contl1n.ent Yolu.e it STP -A -I 2. 61 xl 06 Ft 3 ) x ___..:.P___---,--X __..:z.4&J92 .....14.7 T P Ipslg) -Containment pressure Ipsig) + 14.7 TI*R) -Containment temperatureC*F) + 460 A -2 _6lxl 0 6 n3 ) x \1. :l x 14 .7 psia t,lD A DETERMINE Haxl.u. Hydrogenvolulle thlt cln be vented -B -(3; Containment Hydrogen Concentration) x ....B -3. DETERMINE Hydrogen flow rate as I functlon of ReS pressure -C a CHECK ReS pressure. D[TERM 1 NE Hydrogen flow rate using Attachment 5, HYDROGEN FLOW RATE VERSUS ReS PRESSURE. Page 29 . e -__ D .::....____ SCFM d.::....'1..:...::;.. U 4CALCULATE .axi.u. vent1ng Maximum venting time -C Answer Keyventing time -@ llnG. minutes ,
END OF ATTACHMENT f I Page 28 of 2 9 File: 0001251602-1
.doc Difficulty
2 Time: 15 minutes Task Number: 0001250502 3-FR-1.3 Administrative Review Reactor Vessel Venting Time Calculation per FR-1.3 Page 6 of 8 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information
File: 0001251602-1.doc Difficulty:
2 Time: 15 Task Number: 0001250502 3-FR-1.3 Page 7 of 8 INITIAL CONDITIONS: An event occurred 24 hours ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. The TSC has calculated Reactor Vessel Venting Time in accordance with FR-1.3 Attachments 4 and 5 using the following information. Containment pressure 2.5 psig Containment temperature 160°F Containment hydrogen conc 1.0% RCS 1000 psig INITIATING CUES: You are the CRS and the SM has directed you to review the Reactor Vessel Venting Time calculation. Task Page 8 of 8 Number: Title: Revis i on Number: 3-FR-1.3 RESPONSE TO VOIDS IN REACTOR VESSEL .0 Attachment 4 (Attachment page 1 of 1) INSTRUCTIONS FOR PETERMINING VENTING TIME DETERMINE Containment at STP -A A .. ( 2. 6] xl 0 6 Ft 3 ) x ____p'--____ x 4.............__.....9Z o R'--_ 14.7 T P (psig) -Containment pressure (psig) + 14.7 T(OR) -Containment temperature(OF) + 460 A -(2.6lx10 6 Ft 3 ) x __ __ 14.7 psia Ft 3 2. DETERMINE Hydrogen volume that can be vented -B B (3: --Containment Hydrogen Concentration) x A 100S B ___Ft 3_'"-t'--'-' 3. DETERMINE Hydrogen flow rate as a function of ReS pressure -C a. CHECK RCS pressure. DET£RMlNE Hydrogen flow rate using Attachment 5, HYDROGEN FLOW VERSUS ReS PRESSURE, Page 29. C JC;'CO SCFM CALCULATE maximu. venting Maximum venting time -C Maximum venting time & minutes II*. *END OF ATTACHMENT* Task
Review a Safety Function Determination Page 1 of 13 ENTERGY (IP2) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator:
Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 2000451602-1 .doc Difficulty
4 Time: 30 Task Number: 2000450102 OAP-34 Review a Safety Function Page 2 of JPM Title: Review a Safety Function Determination JPM Number: SRO-A-2 KA Number and Importance:
1940012237 Equipment Control Ability to determine operability and/or availability of safety related equipment. RO -3.6, SRO -4.6 Suggested Environment: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: Actual Time:
References:
OAP -34 Safety Function Determination Process Technical Specifications Section 3.8 Technical Specifications Section 3.5 File: 2000451602-1.doc Difficulty: 4 Time: 30 Task Number: 2000450102 OAP-34 Review a Safety Function Determination . Page 3 of 13 INITIAL CONDITIONS: Unit 3 is operating at 100% Power 12 hours ago 32 High Head Safety Injection Pump was taken out of service for bearing replacement and is expected to be returned to service within the next 4 hours. This was the only Active LCO at that time. 5 hours ago 32 EDG was declared in operable due to a failure of its jacket water pressure switch. The jacket water pressure switch continues to blow control power fuses. Return time for the 32 EDG is undetermined. The team has completed all actions of LCO-3.8.1. The STA prepared a Safety Function Determination in accordance with OAP-34. The STA has determined that the minimum equipment to mitigate an accident is operable and that no loss of safety function exists. INITIATING CUES: You are the CRS and the Shift Manager has directed you to review the Safety Function Determination. TASK STANDARD: The Safety Function Determination is reviewed and errors identified. File: 2000451602-1 .doc Difficulty: 4 Time: 30 Task Number: 2000450102 OAP-34 Review a Safety Function Determination Page 4 of 13 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation Review Data Entered on Form 2. Identify Tech Spec required Supported Systems entered in D Determine 3.5.2 and 3.8.9 are correct 3. Identify Systems supported by the system listed in D above entered in E Determine 3.7.5, 3.7.8, 3.7.9, 3.7.11, 3.7.13, 3.8.1, 3.8.4, 3.8.7 are correct 4. Identify all systems supported by the systems listed in Block E above Determines 3.4.4, 3.5.2.,3.7.8,3.7.12, 3.8.1, 3.8.9 are correct 5. Identify any systems redundant to those systems identified in D, E, and F above that are tracked by active LCOs entered in G Determine 3.5.2 is correct 6. Identify systems supported by systems listed in G above entered in H Determine None is correct 7. Identify the systems supported and affected by the systems listed in H Entered in I Determine None is correct 8. Identify redundant systems listed between blocks D, E, & F, and G, H, and I Determine 3.5.2 is correct 8. Review the minimum equipment required to mitigate an accident operable Determine Block K is NOT correct 9. Review Loss of Safety Function Determine Loss of Safety Function NOT correct File: 2000451602-1.doc Difficulty: 4 Time: 30 Task Number: 2000450102 OAP-34 Review a Safety Function Page 5 of STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U . 10. Do Not Sign Safety Function Determination Form Does Not sign Form JPM is Complete File: 2000451602-1 , doc Difficulty
4 Time: 30 Task Number: 2000450102 OAP-34 L Review a Safety Function Page 6 of \ No: OAP-034 Rev: 2 SAFETY FUNCTION DETERM'NAT'ON
\ PROCESS J Page 12 of 37 Safety Function (Page 1 of SAFETV FUNCTION Inoperable system: * \)'t ,.j i I R.t.nlne. CR Number: Safety Functlon(.) (S,C,H,P.Z,I), ref. Itep 6.3. C 7-'"I TS Sectlon(l) /3,A. \ -V Technical Sp4Iclflcation Related: V** 0 No Support sy.tem: (l;l' Ye. 0 No LI.t all syatem. supported by the Inoperable system Identified above: 3.S -W 84tList all systems supported by the sy.tems listed In block 0 above: ___3.7 13 -.... 3* 7.g --3 , '? I I 3,/ *'1 -_.. "j.t.1 1 3 .LI.t all sy.tem. supported by the system. listed In block E above: 3.'? \ 3 , 5 .. _.

, 317. C; " *IZ-Review the active LeO Log and list any systems redundant to those systems identified In blocks D, E, & F that are tracked by active LCOs: ---_._ 3.S .. _-2-._ -...-... -. . .. -.. .. ..---..._ ...----.....--..------_.... . ---. _._-_---------------------_ .---_ ... _ --. ---. A. 8. C. D. E. F. G. J Time: 30 minutes File: 2000451602-1.doc Difficulty:

4 Task Number: 2000450102 OAP-34 Administrative

Review a Safety Function Page 7 of i No: OAP-034 I I SAFETY FUNCTION DETERMINATION r---.----. PROCESS L-i Page 13 of 37 _____1 ATTACHMENT Safety Function (Page 2 of SAFETY FUNCTION DETERMINATION H. List the sYlt.ml lupported by the Iy.tema lIated in block G above: Not--1b _. I. Llet the syeteme supported AND affected by the .yetem. lilted in block H above: J. Identify redundant system. fisted between blocks D. E. & F G_ H.4i I above: 3*5 .. K. II the minimum equipment required to mitigate an accident 0 No If the minimum equipment required to I. not 0 able the lOI' of Safety Function exists. /. _ L_ Don. Lo.e of Safety Function exist? 0 Yel

-ltiCofrt'Ct "
Lo** of Safety Function exletl , then rform t h tlons of the Leo in wl1lch the Lo** of Safety Functton exllts. M_ Revlewl Approval:
Prepa r ed by: (S TA) ,5h)U II? -.1\1\ *v Name Ignarure .f: 'bc, kId D a le Reviewed by: SM/CRS/FSS SAO (Cur r ent) ---Name , -S i gnat u re i Date Time: 30 minutes Difficulty
4 File: 2000451602-1.doc Administrative OAP-34 Task Number: 2000450102

---Review a Safety Function Page 8 of SAFETY FUNCTION _ ___ R_e_v: 2 i PROCESS I Page 9 of 37 6.Minimum Equ i pment Required The minimum number of systems required to be operable to mitigate an accident. The Applicable Safety Analysis section of TS Bases contains information concerning the minimum equipment required to mitigate an accident. The minimum safeguards equipment required to mitigate a design basis accident is (Modes 1 through 4): 2 Emergency Diesel .-. -.... ..2 Safety Injection Pumps 1 Residual Heat Removal Pump 1 Containment Spray Pump AND 3 Containment Fan Cooler Units OR
2 Containment Spray Pumps AND 0 Containment Fan Cooler Units OR 0 Containment Spray Pumps AND 5 Containment Fan Cooler Units 2 Essential Service Water Pumps 1 Auto start Auxiliary Feedwater Pump (Motor Driven) 1 Non-Essential Serv i ce Water Pump 1 Component Cooling Water Pump, and 1 Recirculation Pump In Modes 5 and 6, operations are conducted via risk assessment and as specified in the Techn i cal Specification Shutdown Sections.
The minimum equipment required is determined based on Technical Specifications , plant status, and plant configuration. 6.Safety Function A function described or specified in the Technical Spec i fication Bases Section "Applicable Safety Analysis", FSAR -Chapter 14 , Design Basis Documents, or Acc i dent Analysis Design Basis Documents performed by a system structure , or component (SYSTEM) to mitigate an accident. The critical safety functions are (S,C,H,P,Z,I): sub-criticality , core cooling, heat sink,RCS integrity , conta i nment integrity. and RCS inventory. File: 2000451602-1.doc Difficulty
4 T i me: 30 minutes Task Number: 2000450102 OAP-34 Administrative Review a Safety Function Page 9 of . bo: OAP-034 _ __SAFETY FUNCTION DETERMINATION PROCESS __.__ipage 7 0'_3_7__ 4.2.REVIEW the active LCOs. to identify any systems that are redundant to those entered in D, E, or F. 4.2.5.1 RECORD these systems in "G" of Attachment

1. IDENTIFY all systems supported by systems entered in G. 4.2.6.1 RECORD identified systems in "H" of Attachment

1. 4.IDENTIFY all systems supported by systems entered in H. 4.2.7.1 RECORD these systems in "I" of Attachment 1, 4.2.ENTER any redundant systems identified during the evaluation in oJ" of Attachment

1. 4.2.lE redundant systems have been identified, THEN DETERMINE if the minimum equipment required to mitigate an accident is operable.
4.2.9.1 INDICATE the determination in 'K' of Attachment
1. 4.2.10 IF the minimum equipment required to mitigate an accident is NOT operable or a safety function assumed in the accident analysis can not be performed.
THEN a LOSS OF SAFETY FUNCTION exists. . 4.. 2.10.1 INDICATE this determination in "L" of Attachment 1.,' ¥. 4.2.11 IF a LOSS OF SAFETY FUNCTION exists. OR is indeterminate. THEN ENTER LCO 3.0.2 for the supported system(s). Difficulty: Time: 30 minutes File: 2000451602-1.doc Administrative OAP-34 Task Number: 2000450102 Review a Safety Function Page 10 of Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 2000451602-1.doc Difficulty: 4 Time: 30 Task Number: 2000450102 OAP-34 Page 11 of 13 INITIAL CONDITIONS: Unit 3 is operating at 100% Power 6 hours ago 32 EDG was declared in operable due to a failure of its pre-lube pump. The team has completed all actions of LCO-3.8.1. The pre-lube pump is expected back within the next 6 hours. This is the only Active LCO at time zero. 4 hours ago 31 AFW pump was declared inoperable due to breaker control power fuses continuing to blow. The STA prepared a Loss of Safety Function Determination in accordance with OAP-34. INITIATING CUES: You are the CRS and the Shift Manager has directed you to review the Safety Function Determination. Task Number Page 12 of 13 i , L. SAFETY FUNCTION DETERMINATION PROCESS ATIACHMENT1 [ No: I Page 12 of 37 Rev: 2 Safety Function Determination (Page 1 of 2) A. Inoperable system: SAFETY FUNCTION DETERMINATION
e f. 'A t. ..\ \)i t ;.'i' \ Reference CR Number: Safety Functlon(&) (S,C , H,P.Z,I), ref. step 6.3. TS Sectlon(l)
C t--t -z. /3,8" l :r B. Technical Specification Related: Ve. 0 No Support system: Yes 0 NoList al\ system. supported by the Inoperable Iystem IdentIfied above: 3 , 5 ,'----' ____ .-_._-_.* E. List all systems supported by the systems listed In block D above: ___..3. 7 , 13 -_. -_.__. 3*7 .g *...-3 ,%
I 3./*'1 ? 7. 3 I i 1List all systems supported by the systems listed In block E above: __ l\.f I"i 3.? \ 3 1 5 .2-"3 *___._-.---. .----...3.7. 'i -Review the active LeO Log and list any systems redundant to those systems identified in blocks D. E. & F that are tracked by active LCOs: _ "__ ___._ 0>. ._ "_ _ ._----_._-_._----_.....*.* ___ ..... __ _ ** __ _ A--..-------.. _.-.-.... -..---...-. ----. _ _

_____ ' __A __ -------_ .. ---_._---_ . .-..-----. FileTask

Page 13 of 13 \ No: OAP-034 Rev: I i SAFETY FUNCTION DETERMINATION r.=---------------

.L-PROCESS I Page 13 of 37 ____ 1 ATTACHMENT 1 Safety Function Determination (Page 2 of 2) SAFETY FUNCTION DETERMINATION H. Llsllhe syslems supported by the systems listed In block G above: Not-.i*.. List the systems supported AND affected by the systems listed In block H above: -. ---'---'Identify redundant systems fisted between blocks D. E. & F AND G. H.& , above: Is the minimum equipment required to mitigate an accident operable? !B'Yes 0 No If the minimum requlrsd to mitigate an accident Is not operable then a LOll 01 Safety Function exists. ./ Does a Loss 01 Safety Function exist? o Ves MNo If a Loss of Safety Function exists, then perform the Actions of the leO in which the loss of Safety Function exists. Review/Approval: Prepared by: .5 k 4 \e.c.v,I\'!'.....Q. ,.:.\.J II ,V' 1?i.... . ___._ (STA) Name Signature Date ReViewed by: SM/CRS;FSS ! " SRO (Cu rrent) -----Name-*--------------s;gnature-- -Task
Review a Manual Gaseous Rad Waste Release Permit Page 1 of 8 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee ID #: Evaluator:
Date: SAT UNSAT This ,JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 2000181602-1 Difficulty: 3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 ---Review a Manual Gaseous Rad Waste Release Permit Page 2 of 8 JPM Title: Review a Manual Gaseous Rad Waste Release Permit JPM Number: SRO-A-3 KA Number and Importance: 1940012306 Ability to approve release permits. I SRO 3.8 Suggested Environment: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 15 Min Actual Time:
References:
3-S0P-WDS-13 Gaseous Waste Releases File: 2000181602-1 Difficulty: 3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 , Review a Manual Gaseous Rad Waste Release Permit Page 3 of 8 INITIAL CONDITIONS: Preparations are in progress to release 31 Large Gas Decay Tank The Tank is currently at 100 psig Gas Decay Tank Unpressurized Volume 525 Fe Grab Sample Number 35610 Concentration of Noble Gases 1.3 X 10-3 !-ICi Current Radiation Monitor 27 Reading is 10 !-ICi/sec Permit Number is 17 The BOP calculated a manual Release Permit INITIATING CUES: You are the CRS and the SM has directed you to review the Gaseous Waste Release Permit TASK STANDARD: Release Permit reviewed and errors found. File: 2000181602-1 Difficulty
3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13
, Review a Manual Gaseous Rad Waste Release Permit Page 4 ofa
Denotes Critical Step DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below STEP Commence evaluation
1. Ensures given data 2. Review Entered given data properly entered Deterrnine Total Activity Not Correct . 3. Calculate Total Activity Correct Value 1.31 X 10 5 IJ Ci Determine Available

4. Calculate Available Release Rate Release Rate Correct Determines Maximum Allowable

5. Determine Maximum Allowable Release Rate Release Rate is correct Selected release rate 6. Check Select Release Rate conservative is conservative Determine associated conservative percent lift Selected percent lift 7. setting from Attachment 11 setting is correct Calculated
_ lDetermine calculated leakrate NOT correct Correct Value 15.9 IJCi/sec Does Not sign the 9. Calculations are not correct JPM File: 2000181602-1 Difficulty: 3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 Review a Manual Gaseous Rad Waste Release Page 5 of No: 3-S0P-WDS-013 Rev: 26 GASEOUS WASTE RELEASES Page 36 of 55 ATTACHMENT GASEOUS WASTE RELEASE PERMIT (Page 1 of Tank! Current System (1) '31 i.h 1>r DateiTime (2) IDVI'N }lto o Permit No. (3)_-='_' ___ Date Time Concentration 01 .. Volume (4) 5.1 1) 1t 3 Inilial Pressure (5) '00 psig Noble Gas (C)(6)_-'I-',.... __Time I (., D T OR R-12 Monllor Grab Date T b'M 'l . l. no'S Activity (A)(a) :r UCi Noble Gas Iodine 131 Aclivity (8a) tJA-!lCi/ee ,t\ VC Purge Only Calculated Release Rate (R}(9 \_-'--" 7'"_.rCi/sec Available Release Aate (0)(10) Discharge Monitor (11 )__->;)'"--1'--____ Actual Alarm Selpoinl (12) 3. 1>B).(o 5 !lCi/sec ,. () 'liD j R* 12 Auto Closure/Alarm Setpoints: Calculated (15) __ Actual (16) UA uCi/cc IE discharge monitor is OOS, COMPLETE the following: Calculated alarm setpoin! __--'UCiisec Alert UCi/sec Monitor (17)__tJ",,-b.e--_Placed out service@ t.J"'__. .:..__..:.:::..:L: Date Time N ,--,-Time (Noble Gas) Vent Sample: (18) Sample II f.,) A. Date__.!..C br__ IJ A Results (19) N A uC i/cc Vent flow rate (20) " elm Continuous Release Rate (CR)(21 )_---'l>;::..-!t-.-"-__Release Calculations verified by (22) ____-'tJ""-I br!:!.-_______________Release Path Valve Alignment Verified (23) ___ _________________ CRS/SM Discharge Au1horized (24 CAS/SM Release Stan (25)_---:::--_ Dale Time Final Pressure (26) _______psig Release Stop (27)_--::::---_ Date Time Calculations Results: S (28} ______ Emax (29) 500?> RCV-014 Setting (31)_----1 4 L.l O L-__% open Commenls:(32),___________________ _ ____________ _ File: 2000181602-1 Difficulty
3 Time: 15 minutes Task Number: 2000180102 3-S0P-WDS-13 Administrative f Review a Manual Gaseous Rad Waste Release Permit Page 6 of 8 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information
File: 2000181602-1 Difficulty

3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13
.' Page 7 of 8 INITIAL CONDITIONS: Preparations are in progress to release 31 Large Gas Decay Tank The Tank is currently at 100 psig Gas Decay Tank Unpressurized Volume 525 Fe Grab Sample Number 35610 Concentration of Noble Gases 1.3 X 10-3 Current Radiation Monitor 27 Reading is 10 !-lci/sec The BOP calculated a manual Release Permit INITIATING CUES: You are the CRS and the SM has directed you to review the Gaseous Waste Release Permit FileTask Number .. Page 8 of 8 No: 3-S0P-WDS-013 Rev: 26 GASEOUS WASTE RELEASES Page 36 of 55 ATTACHMENT GASEOUS WASTE RELEASE PERMIT (Page1of1) Tankl System (1) 3/ L 6 1)f Current DatelTime (2) 'T D O I'<Y hoo Permit No. (3)_...:...10-:' ___ Date Time Concentration 01 I .. Volume (4) 5 ;).1) 1t 3 Initial Pressure (5) 100 pslg Noble Gas (C)(6) t . '3 )(,W' ? uCilcc Grab Sample:(?) Sample # 35[,/0 Date TbDA Y Time I QB R-12 Monitor Activity (A) (B) t .1 k'k f f) oJ flCl Noble Gas Iodine 131 Activity (Ba)_...I:rJ:.t.!J'xL..-._---lUcilCC VC Purge Only Calculated Release Aate (R}(9) '3 uCiisec Available Release Rate (OHIO) uCilsec D i scharge Monitor {I 1),__..J;;}.t.-J-L- ____ Actual Alarm Setpoint (12) 3. l>B );(o J.l.CilS8C . ,,?;J Calculated alarm setpoint _______JJ.lCilsec Alert selpoint (14) I f Yi l ,; R-12 Auto Closure/Alarm Setpoints: Calculated (15)__.ctJ'--"-()..:....-_--'UCilcc Actual (IS) 4) A !E discharge monitor is 005 , THEN COMPlETE the following:
Monitor (17)__tJoc..:;:.I'>._-piaced out service 10 __.:..:tv::;..'
""h__ __---'t-?L.:-..Cflr:...!.- __ Date Time
Vem Sample: (18) Sample __ Date__
__Time kl A ResUlts (19) tJ A flCilcc (Noble Gas)
Ventllow rale (20) " elm Continuous Release Rate (CR)(21 )_-..LtJ=--.!..
f!r...:.-.__--JUCllsec Release Calculations verified by (22)____.... _______________ _ Relea.S8 Path Valve Alignment Verifled (23),________________ _ ____ CRSISM Oischarge Authorized (24) __ ____ Release Start {25)_--:=__ _ ___ CRS/SM Dale Time Final Pressure (26) ______psig Release Stop (27)____ _--=__ Dale Time Calculations Resul1s: S (28}_...__.__ Emax (29) 5 DO _________ RCV-014 Setting (31)_--1 4 ... 0'--__% open ) Comments:(32)_____ __________ ________ FileTask
Classify E-Plan Event and Complete Part 1 Form Page 1 of 7 ENTERGY (IP2) JOB PERFORMANCE MEASURE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: Difficulty
Time: minutes Task Number Procedure Ref category
---* Classify E-Plan Event and Complete Part 1 Form Page 2 of 7 JPM Title: Classify E-Plan Event and Complete Part 1 Form JPM Number: SRO A-4 KA Number and Importance: 1940012441 Emergency Procedures/Plan -Knowledge of the emergency action level thresholds and classifications. SRO-4.6 Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: Actual IP-EP-120 Emergency Classification IP-EP-115 Emergency Plan Forms IP-EP-210 Central Control Room IP-EP-410 Protective Action Recommendations File: Difficulty: Time: minutes Task Number: Procedure Ref category Classify E-Plan Event and Complete Part 1 Form Page 3 of 7 This is a TIME CRITICAL JOB PERFORMANCE MEASURE. YOU HAVE 15 MINUTES FROM THE TIME YOU ARE TOLD TO BEGIN UNTIL YOU CLASSIFY THE EVENT YOU HAVE 15 MINUTES FROM THE TIME YOU CLASSIFY THE EVENT UNTIL YOU COMPLETE THE RADIOLOGICAL EMERGENCY DATA FORM. INITIAL CONDITIONS: The Reactor and Turbine have tripped. Safety Injection automatically initiated due to a large break LOCA inside containment. The following plant conditions exist: The team is responding in E-O, Reactor Trip or Safety Injection. Containment Isolation Phase A and B have been confirmed. 31 and 32 Containment Spray Pumps failed to start and attempts to start pumps was unsuccessful. 34 Containment Fan Cooler Unit was inoperable prior to the event due to circuit breaker maintenance Containment Pressure is 38 psig and stable R-25 reading 19 R/hr and R-26 reading 21 R/hr RVLlS , Natural Circ Range reading 44% METEOROLOGICAL CONDITIONS: Wind Speed: 3.5 Wind Direction: 120 degrees @ 10 Stability Class: The Shift Manager is unable to get back to the control room. The MIDAS Computer is out of service for maintenance. INITIATING CUES: You are the CRS and you must classify the event and complete the required Radiological Emergency Data Form as required by the Emergency Plan. TASK STANDARD: Emergency Event properly classified and Emergency Data Form Part 1 properly completed. File: Difficulty: Time: minutes Task Number: Procedure Ref category Classify E-Plan Event and Complete Part 1 Form Page 4 of 7 Denotes Critical Step STEP DESCRIPTIONS t CUES &NOTES STANDARD StU Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation
The SM shall evaluate Plant Status Sheet to determine IF aGE, SAE, ALERT or NUE classification applies, AND IF so, determine the highest classification and declare it. Note: Declaration must be made within 15 minutes of start of JPM Time Declaration Made: EAL (4.1.4) GENERAL .3. Complete and Approve "New York State Radiological Emergency Data Form, Part 1" Note: MUST BE COMPLETED WITHIN 15 MINUTES OF DECLARATION Time IP-EP-115 Form 1 completed:
Complete IP-EP-115 Form 1 4. Refer to procedure IP-EP-21 0, Attachment 9.1 (SM / POM / ED Checklist) Attach 9.1 5. Initiate County, State and NRC notification per IP-EP-115, Form EP-4, 5 or 6 as applicable CUE: Acknowledge as communicator when requested to commence notifications. Request for CCR comunicator File: Difficulty
Time: minutes Task Number: Procedure Ref category I Classify E-Plan Event and Complete Part 1 Form Page 5 of 7 New York State Indian Point Energy Center RADIOLOGICAL EMERGENCY DATA FORM -PART 1 Notification
_[_I This is the Indian Point Energy Center with a Part 1 Noti1ication on:
1. 2. 4. 6. 6. 7. 8. 9. 10-¥: j Reactor Status: This is an: EXERCIS ACTUAL EMERGENCY at: UNIT 2 BOTH Unit 2 f:Jperalloni!D (Date) (Time) (24 hr clock) Shutdown Unit 3 Operational 9) (Date) '1DOft \{ (Tim e) t'.Y Uc::i.\ TI l-ib (24 hr clock) Shutdown Emergency A. Unusual Event B. Alert C. Site Area Emergency ClaSllification is: 1> Co: G eneral E. Emergency Tennlnated This Emergency Classification declared on: 'TllDMI at DF (Date) (T1 me 2 4 hr EAL#: "-1.1.4 Con.fi"I1lI'O lot}. -th2'n "n,nlrf\\AM ..d qguftrltftf 1!J2'hr(;!, C.iab\t' I\"l{ It\6tc l>+ $w I a ldo l'f.).ble 4, tJ R'i!lease of Radioi!ctlve Materials due to the
!;;V!!nt: f>.. B. Release BELOW Federal limits To Atmosphere To Water C. Release ABOVE Federal limits To Atmosphere To Water D. Unmonitored release requiring evaluation Wind !21;!!lllg' 3.5 Meters/Sec a\ elevation 10 meters WlnQ Direction' (Frgml Degrees at elevation 10 meters Answer Key A @B D E F G The followtng Protective Actions are recommended 10 be implemented a5 soon as practicable
A. NO NEED for PROTECTIVE ACTIONS outside the site boundary and IMPLEMENT the KI PUIN for the following Sectors C. SHELTER-IN-PUlCE and IMPLEMENT the Kf PUIN for the fol lO wing Sectors *-( All remaining Arens MONITOR the EMERGENCY ALERT around 5-miles downwin V . 5 miles around 10'miles downwind Entire EPZ ¥-In Ihe followtng S ectors:Q) 6) 4 5 6 7 8 9 10 11 12 13 14 15 @ NOTE: OFFSITE AUTHOBITIES CQN§IQER :2HELTf,;R*IN*PLl!QE
+ IAKJ;; KIIE EVAQUATION 1:2 N OT Reported by -Communicator: Telephone
(Communicator's Name) Emergency Director Approval: DatefTime: TbD,..\f (Oirecror's Name) Page 1 of 1 Fonn EP-l. Rev 3 File: Difficulty:
Time: minutes Task Number Procedure Ref category Classify E-Plan Event and Complete Part 1 Form Page 6 of 7 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: Difficulty
Time: minutes Task Number: Procedure Ref category Page 7 of 7 This is a TIME CRITICAL JOB PERFORMANCE MEASURE. YOU HAVE 15 MINUTES FROM THE TIME YOU ARE TOLD TO BEGIN UNTIL YOU CLASSIFY THE EVENT YOU HAVE 15 MINUTES FROM THE TIME YOU CLASSIFY THE EVENT UNTIL YOU COMPLETE THE RADIOLOGICAL EMERGENCY DATA FORM. INITIAL CONDITIONS:
The Reactor and Turbine have tripped. Safety Injection automatically initiated due to a large break LOCA inside containment. The following plant conditions exist: The team is responding in E-O, Reactor Trip or Safety Injection. Containment Isolation Phase A and B have been confirmed . 31 and 32 Containment Spray Pumps failed to start and attempts to start pumps was unsuccessful. 34 Containment Fan Cooler Unit was inoperable prior to the event due to circuit breaker maintenance Containment Pressure is 38 psig and stable R-25 read ing 19 R/hr and R-26 read ing 21 R/hr RVLlS, Natural Circ Range reading 44% METEOROLOGICAL CONDITIONS: Wind Speed: 3.5 Wind Direction: 120 degrees @ 10 Stability Class: The Shift Manager is unable to get back to the control room. The MIDAS Computer is out of service for maintenance. INITIATING CUES: You are the CRS and you must classify the event and complete the required Radiological Emergency Data Form as required by the Emergency Plan. Task Number
Emergency Borate Page 1 of 9 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 0040421601-5.doc Difficulty: 2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 ---Emergency Borate Page 2 of 9 JPM Title: Emergency Borate JPM Number: S-1 (a) KA Number and Importance: 000024A120 Ability to operate and/or monitor the following as they apply to the Emergency Boration: -Manual boration valve and indicators RO -3.2, SRO -3.3 Suggested Environment: Simulator Actual Testing Environment: Alternate Path: YES Time Critical: NO Estimated Time: 10 Min Actual Time:
References:
ONOP-CVCS-3 File: 0040421601-5 .doc Difficulty
2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 3 of 9 INITIAL The reactor has just tripped. 31 BATP is aligned to the blender. All actions in E-O, Steps 1-4 and ES-O.1, Steps 1 through 3 have been completed. Current Boron concentration is 1148 ppm INITIATING CUES: You are the ATC and the CRS has directed to emergency borate per CVCS-3 up to and including the completion of Step 17.a due to multiple stuck rods. TASK STANDARD:
The RCS has been Emergency Borated per ONOP-CVCS-3 up to and including the completion of step 17.a. File: 0040421601-5.doc Difficulty: 2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 4 of 9 Denotes Critical Step STEP DESCRIPTIONS / CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below STANDARD S/U 1 Obtain correct procedure ONOP-CVCS-3 2 Check Charging Pump running Observe Charging Pump RUNNING 3 4 6 . 7 -8 . 9 . 10 . 11 . *12 ' Check MCC-36A and 368 available OPEN Emergency Bot'ation Valve CUE Inform operatorthat MOV-333 win NOT .OPEN .. borate using Normal BoratiOn .. .. Place Boric Acid Transfer Pumps in Fast Speed ReStart Trariafar PUmps I -' Place FCV-110A, Boric ACid Flow Control Blender, controller in Manual EnsW8 FCV-1110A, l Boric Acid FloW Control Blender, controller is fUlly openPlace FCV-111A Makeup H20 to BoriC Acid Blender. controllet in Manual Ensure FCV..111A,
Boric Acid Flow Control Blender, controller is closed Place Makeup Mode Selector switCh in Turn Makeup Control Switch to Start and Return to NOflTlal Verify MCC-36A and 368 energized Places CHoMOV 333 to OPE ObserVes Valve does not ODen . Rotates SwitcheS Fast position -. Rotate .*. . ,;;, ." Raise r.< to i***. Move fir bar to taft Open :RaIse T bar 8wittb to Manual POsItion -? :::".-MoveT'bar (. Open RotateSwitch.
Manual Position Rotate SWitCh to Start then back to .Ngrmal t I J-File: 0040421601-5.doc Difficulty
2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 Emergency Page 5 of STEP DESCRIPTIONS t CUES & NOTES STANDARD StU 13 Check Ff-11OA flOw Indicated Observe FIQw Is indicated 14 Cfoie Boric Acid storage Tank Recirculation Valves HCV-104 &HCV-105 Locatad on P ane l SFF . (Panel SFF) to '. I' 15 Transfer operating
(:hai"ging pump speed to manWif and Increase speed to MAX I MUM ,.u. ..... to u net_ ,... a . .:.incre_ .. 0,,_ to Maximum : . *;1 16 Check Pressurizer pressure LESS THAN 2335 psig Verify Pressurizer pressure < 2335 psig 17 Check status of reactor Verify reactor subcritical 18 Check RCS temperature >500°F Verify RCS >500°F 19 Check RCS temperature >540°F CUE: Cue Candidate is 535°F Observe RCS approximately 535°F 20 If any rod is greater than or equal to 20 steps emergency borate per attachment 4 Observes 2 rod fully withdrawn
21. Determine boration time NOTE: Minimum Boration Time 142 seconds for temperature.
Candidate may continue with procedure and add 142 seconds with the time for stuck rods (34 min). for a total of 36 minutes and 22 seconds. CUE: (Time Compression) Inform candidate that the calculated time has passed. Determines minimum of 142 seconds 22 Determine status of Control Rods Determine 2 Rods > 20 Steps File: 0040421601-5 .doc Difficulty: 2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 6 of 9 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU 23 Determine amount of boron concentration increase required NOTE: 212 ppm for each additional rod greater than one Calculate 212 ppm boron concentration increase required .24 Determine boration time required NOTE: 34 min for each additional rod greater than one NOTE: Minimum Boration Time 142 seconds for temperature and the time for stuck rods (34 min). for a total of 36 minutes and 22 seconds. If candidate stops and is waiting for time to elapse, CUE: (Time Compression) Inform candidate that additional 34 minutes has passed Determine 34 additional minutes required OR Determine total time 36 min 22 Seconds Examiner can terminate JPM at this time 25 Direct Watch Chemist to sample RCS boron concentration CUE: Acknowledge as Watch Chemist Direct Watch Chemist to sample RCS for boron concentration 26 Determine if boration completed CUE: (Time Compression) Inform candidate that additional 34 minutes has passed Determine expected boration time completed OR required boron concentration achieved 27 Place boric acid transfer pumps to SLOW Rotate speed switch to slow position 28 Turn Makeup Control Switch to Stop Rotate Makeup Control Switch to Stop 29 Open Boric Acid Storage Tank Recirculation Valves to approximately 25% Rotate valve potentiometer to 25% JPM Complete File: 0040421601-5.doc Difficu Ity: 2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 7 of 9 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 0040421601-5 .doc Difficulty
2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 8 of 9 Simulator Setup Reset to any 100% IC Insert Malfunctions for Stuck Rods MAL-CRF004AJ (CBB -Rod H12) -UNTRIPPABLE MAL CRF004AZ (CBD -Rod K2) -UNTRIPPABLE SWI CVC016C ON -MOV-333 Fails to Open SWI CVC016D OFF -MOV-333 Fails to Open Manually trip the reactor. Open Atmospheric Steam Dumps to cooldown to approximately 535°F Secure Auto Makeup. File: 0040421601-5
.doc Difficulty
2 Time: 10 Task Number: 0040420501 ONOP-CVCS-3 Page 9 of 9 INITIAL

1. The reactor has just tripped. 2. 31 BATP is aligned to the blender. 3. All actions in E-O , Steps 1-4 and ES-O.1 , Steps 1 through 3 have been completed. INITIATING CUES: You are the ATC and the CRS has directed to emergency borate per CVCS-3 up to and including the completion of Step 17.a due to multiple stuck rods. File: 0040421601-5
.doc Task Number: 0040420501 Transfer to Cold Leg Recirculation Page 1 of 10 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager , Nuclear Training . File: 0130151601-1 .doc Difficulty: 4 Time: 20 Task Number: 0130150501 ES-1 .3 Transfer to Cold Leg Recirculation Page 2 of 10 JPM Title: Transfer to Cold Leg Recirculation JPM Number: S-2(b) KA Number and Importance: 000011A111 Ability to operate and/or monitor the following as they apply to a Large Break LOCA: -Long-term cooling of core RO -4.2 SRO -4.2 Suggested Environment: Simulator Actual Testing Environment: Alternate Path: YES Time Critical: YES Estimated Time: 20 Min Actual Time: ___
References:
3-ES-1.3 Transfer t Cold Leg Recirculation File: 0130151601-1.doc Difficulty: 4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Recirculation Page 3 of 10 INITIAL CONDITIONS: A Large Break LOCA occurred approximately 25 minutes ago. The RWST LOW LOW Level alarm has just illuminated. SI has been RESET per RO-1 and procedure E-1, Steps 1 through 19 actions have been completed with Containment Spray reset. 4All actions of RO-1 are complete. INITIATING CUES: You are the ATC and the CRS has directed you to transfer to Cold Leg Recirculation per ES-1 .3, steps 1 through 12. TASK STANDARD: Cold Leg Recirculation established prior to RWST level lowering below 1.5 feet with recirculation flow to the core approximately 360 gpm. File: 0130151601-1 .doc Difficulty
4 Time: 20 Task Number: 0130150501 ES-1 .3 Transfer to Cold Leg Recirculation Page 4 of 10 Denotes Critical Step STEP 1 2 3 4 5 6 7 8 9 10 DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Obtain correct procedure Review Caution and Note prior to Step 1 Determine if transfer to Cold Leg Recirc is required CUE: Containment Level is trending up on Recorders LR-1253 and LR-1254 RESET SI Check SI RESET RESET Containment Spray Align SI Recirc Switches #1 and #3 Energize the following valves on MCC-36A and MCCC-36B:
AC-MOV-743, 744 and SI-MOV-894A AC-MOV-1870, SI-MOV-882 and SI-894B,894D CUE: Acknowledge as NPO Booth Operator: Energize valves Establish communications with PAB 73 ft. and prepare for operation of SWN-35-1 and 35-2 CUE: Acknowledge as NPO Check status of Recirc Switch #1 STANDARD ES-1.3, Step 1 Caution and Note reviewed Verify both RWST Low-Low Level alarms LIT and VC Sump trending up Verfy SI reset Verify SI Actuated light extinguished VC Spray reset per initiating cue Place Recirc Sw #1 and #3 to ON Dispatch NPO to energize valves on MCC 36A and 36B Dispatch NPO to PAB, 73 ft. Verify Recirc Switch #1 function complete light LIT S/U File: 0130151601-1 .doc Difficulty
4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Page 5 of STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 11 Check status of Recirc Switch #3 NOTE: Function Complete light is not expected when candidate reaches this step. This is due to time to energize valves 882 and 744. RNO actions states when valves are energizes then ensure valves are closed. Candidate should not place RHR pumps is Trip Pull Out since they will not be running. Verify Recirc Switch #3 function complete light LIT 12 Check RCS pressure less than intact SG pressure Verify RCS pressure less than intact SG pressure 13 Stop both Motor Driven Auxiliary Feed pumps Place 31 I 33 ABFP in PULLOUT 14 Initiate performance of Attachment 1 CUE: Additional Team operator will perform parallel actions of Attachment 1 BOOTH OPERATOR:
Verify 459,460,200 A,B, C closed, stop running Charging pump(s), place all Pressurizer heaters in OFF. Notify operator that Attachment 1 complete Direct performance of Attachment 1 15 Check status of SWN-FCV-1111 and 1112 CUE: FCV-1111 and 1112 are CLOSED Dispatch NPO to verify 1111 and 1112 CLOSED 16 Align SI Recirc Switch #2 Place Recirc Sw #2 to ON 17 Check status of Recirc Switch #2 Verify Recirc Switch #2 function complete light LIT 18 Establish communications with PAB 73 ft. CUE: Acknowledge as NPO Request NPO to standby CCW Hx's 19 Check RHR Hx CCW Shutoff Valves OPEN. CUE: Acknowledge as NPO Verify 822 A and 822B OPEN 20 Manually START 32 Recirc pump Observes 32 Recirc pump NOT running File: 0130151601-1 .doc Difficulty: 4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Recirculation Page 6 of 31 Verify Recirculation Trains not affected by sump blockage -Low Head Injection Line Low Flow alarm -SI Pump Suction Low Pressure alarm -Indications of erratic / reduced flow -Abnormal sum level indication Determine Minimum Core Recirculation Flowrate Verify indications of sump blockage do NOT exist Throttle to maintain 360 gpm on lowest available indicator & NOTES STANDARD Observes 31 Recirc pump NOT running S/U File: 0130151601-1.doc Difficulty
4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Recirculation Page 7 of 10 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU JPM Complete File: 0130151601-1
.doc Difficulty
4 Time: 20 Task Number: 0130150501 ES-1 .3 Transfer to Cold Leg Recirculation Page 8 of 10 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 0130151601-1.doc Difficulty: 4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Recirculation Page 9 of 10 Simulator Setup Initiate Simulator to any 100% power IC Insert Malfunctions:
MAL-RCS001A
-100%
MAL-CNS003A
-Trip -Recirculation Pump 31 Trip
MAL-CNS0038
-Trip -Recirculation Pump 32 Trip Run Simulator Perform all actions of E-O, RO-1, E-1 Wait until RWST Low Low level alarms annunciate. Freeze the Simulator Take a Snapshot if JPM is to be used more than once. File: 0130151601-1.doc Difficulty: 4 Time: 20 Task Number: 0130150501 ES-1 .3 Page 10 of 10 INITIAL
1. A Large Break LOCA occurred approximately 25 minutes ago. 2. The RWST LOW LOW Level alarm has just illuminated.

3. SI has been RESET per RO-1 and procedure E-1, Steps 1 through 19 actions have been completed with Containment Spray reset. 4. All actions of RO-1 are complete.
INITIATING CUES: You are the ATC and the CRS has directed you to transfer to Cold Leg Recirculation per ES-1.3, steps 1 through 12. Task
Respond to Pressurizer Controlling Pressure Channel Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator: 8M UN8AT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager , Nuclear Training . File: 0100081601-1 Difficulty: 3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 ---Respond to Pressurizer Controlling Pressure Channel Failure High Page 2 of 9 JPM Title: Respond to Pressurizer Controlling Pressure Channel Failure High JPM Number: S-3(c) KA Number and Importance: 010000A202 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: -Spray valve failures RO -3.9 SRO -3.9 Suggested Environment: Simulator Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: Actual Time:
References:
3-AOP-INST-1 Instrument or Controller Failures File: 0100081601-1 Difficulty: 3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel Failure High Page 3 of 9 INITIAL CONDITIONS: The plant is at 100% Power INITIATING CUES: You are the ATe. TASK STANDARD: Plant stabilized with appropriate failed equipment removed from service per the applicable procedure. File: 0100081601-1 Difficulty
3 Time: 20 Task Number: 0100080501 3-AOP-INST
-1 Respond to Pressurizer Controlling Pressure Channel Page 4 of 9
Denotes Critical Step S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below STANDARD DESCRIPTIONS I CUES & NOTES STEP 1. Commence evaluation Determine PRZR pressure not Identify Failure/Stabilize Plant NORMAL.2. Place PRZR pressure control in MANUAL Check All Control Systems Rod Control -Not Affected PRZR Level Control-Not Affected MBFP Speed Control -Not Affected Check indications for 3. all control systems SG Level Control-Not Affected SG Pressure Control -Not Affected PRZR Pressure Control -IS AFFECTED Determines an instrument failure Determine an Instrument Failure has occurred has occurred;
4. redundant PT-455 Failed High indications and controller response Transition to procedure section for PRZR Selects proper Pressure Failure 5. procedure step from table Procedure Step 4.83 (Page 35) Adjust Master Manually operate Heaters and Sprays as Pressure controller . ;6. necessary to maintain desired pressure to close spray valves and energize heaters 7. Determine PI-457 has not failed Observes Indication

8. Determine PI-474 has not failed Observes Indication File: 0100081601-1 Difficulty

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel P age 5 0 f STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 9. Place Pressurizer Pressure Defeat Switch in DEFEAT 1 & 4 (Rack B-6) CUE: A spare operator will monitor the flight panel Rotates Switch to DEFEAT 1 & 4 position 10. Place Delta T Defeat Switch T/411A in Defeat Loop 1 (Rack B-8) Rotates Switch to Loop 1 position 11. Place Pressurizer Pressure Recorder to channel 2 or 3 Rotates Switch to channel 2 or 3 position 12. Return Heaters and Sprays to Auto Place Master Pressure Controller to auto 13. Refer to Technical Specifications. CUE: The CRS is reviewing Tech Specs 14. Observes Note before step Reviews Note 15. Check Redundant Bistables for failed channel NOT tripped Using Attachment 6 Table 1 Check Bistable Status lights extinguished (Panel SOF) 16. Observe NOTE before step Reviews Note 17. Place the bistables to trip for failed channel in Rack Red A-4
Loop 1 Overtemp Trip

Loop 1 Hi Press Trip

Loop 1 Lo Press Trip

Loop 1 Unblock SI

Loop 1 SI Places bistable trip switches in the UP position Evaluator can terminate the JPM at this time 18. Check all bistable status lights for failed instrument listed in Attachment 6 Table 3 illuminated Observes all status lights illuminated File: 0100081601-1 Difficulty
3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel P age 6 0 f 9 STEP DESCRIPTIONS I CUES &NOTES STANDARD S/U JPM Complete File: 0100081601-1 Difficulty:
3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel Failure High Page 7 of 9 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information
File: 0100081601-1 Difficulty

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel Failure High Page 8 of 9 Simulator Setup Initialize Simulator to any 100% power Ie Insert Malfunction MAL-PRS005A Final Value 2500 psig Ramp -15 seconds Take a snapshot if JPM is to be used more than once. File: 0100081601-1 Difficulty:
3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Page 9 of 9 INITIAL CONDITIONS: The plant is at 100% Power INITIATING CUES: You are the ATe. Task Number
JPM No. 104A Initiate a Bleed and Feed of the RCS (Alternate Path) Page 1 of 6 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: (JPM104A.doc) Difficulty: 4 Time: 20 minutes Parent Task # 0000130501 FR-H.1 REV: 2 ---JPM No. Initiate a Bleed and Feed of the (Alternate Page 2 of 6 JPM Title: Initiate a Bleed and Feed of the RCS JPM Number: S-4(j) KA Number and Importance: OOWE05A101 Ability to operate and/or monitor the following as they apply to the Loss of Secondary Heat Sink: -Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features RO -4.1 SRO -4.0 Suggested Environment: Simulator Actual Testing Environment: Alternate Path: YES Time Critical: NO Estimated Time: Actual Time:
References:
3-FR-H.1 Loss of Secondary Heat Sink File: (JPM104A.doc) Difficulty: 4 Time: 20 minutes Parent Task # 0000130501 FR-H.1 REV: 2 JPM No. Initiate a Bleed and Feed of the (Alternate Page 3 of 6 INITIATIAL 1A loss of feedwater has occurred. Steps 1-4 of E-O are complete. A transition to ES-O.1 was made at Step 4. A transition to FR-H.1 was made due to a RED path on the Heat Sink CSF. The fold out page requirements for bleed and feed are met. INITIATING CUE You are the ATC and the CRS has directed you to perform a Bleed and Feed of the RCS per FR-H.1 , Starting at Steps 9. TASK STANDARD: RCS Bleed and Feed established per FR-H.1 File: (JPM104A.doc) Difficulty
4 Time: 20 minutes Parent Task # 0000130501 FR-H.1 REV: 2 JPM No. Initiate a Bleed and Feed of the (Alternate Page 4 of 6 Denotes Critical Step STANDARD DESCRIPTIONS t CUES & NOTES STEP StU FR-H.1, Step 9 1. Obtain correct procedure

2. Caution reviewed Review Caution prior to Step 9 Step 9 Depress manual SI . 3. pushbuttons
-both Manually actuate Step Manually CLOSE . 4. all MSIVs Check all MISVs Step 5. TRIP all RCPs Check all RCPs STOPPED Observes Thermal Step 11 Barrier CCW Check RCP Seal Cooling Header Low Flow alarm clear and
Thermal Barrier CCW Header Low Flow 6. RCP Thermal alarm clear Barrier Cooling

RCP Thermal Barrier Cooling Return High Return High Temp Temp alarm clear alarm clear Step 12a Observes CCW 7. available to pumps Check Charging Pump Status Observes no Step 12b 8. charging pumps Check Charging Pumps Running Step 12b RNO Rotate LCV-112B switch to OPEN Align Charging to RWST . 9. and LCV112C Open LCV-112B switch to CLOSE Close LCV-112C Place controller in Step 12b RNO(3) manual and adjust Prepare all available charging pumps for start 10. potentiometer to

Set 31 Pump to approx 15% approximately 15

Set 32 and 33 Pumps to approx 10 -15% 25% File: (JPM104A.doc)
Difficulty: 4 Time: 20 minutes Parent Task # 0000130501 FR-H.1 REV: 2 JPM No. Initiate a Bleed and Feed of the (Alternate P age 5 0 f6 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 11. Step 12c(2) Check 142 Fully Open Observes valve fully open 12. Step 12c(3) Open 204B Observes valve is open 13. Step 12c(4) Start all available charging pumps and increase speed to maximum Rotate breaker control switches to START and speed controller to maximum 14. Step 13a Check status of SI purnps Observe all SI pumps running 15. Step 13b(1) Verify Safeguard Valve Off-Normal Position alarm CLEAR Observe alarm clear 16. Step 13b(2 & 3) Verify BIT discharge and inlet valves OPEN Verify 1835A I B and 1852A I B OPEN 17. Step 13b(4) Verify High Head Stop valves OPEN Verify 856J I H I C I EOPEN 10 Step 14a Check power available to PORV block valves Verify power to MOV-535 and 536 11 Step 14b Check both Pressurizer PORV Block Valves OPEN Check MOV-535 and 536 OPEN .12 Step 14c OPEN both Pressurizer PORVs PCV-455C and 456 OPEN 13 Step 15 Verify adequate RCS bleed path Observe 456 CLOSED File: (JPM104A.doc) Difficulty: 4 Time: 20 minutes Parent Task # 0000130501 FR-H.1 REV: 2 JPM No. Initiate a Bleed and Feed of the (Alternate Pa 6 of 6 STEP DESCRIPTIONS I CUES & NOTES STANDARD NOTE: If operator implements Attach 3, inform him I her a spare operator will perform it JPM Complete File: (JPM104A.doc) Difficulty: 4 Time: 20 minutes Parent Task # 0000130501 FR-H.1 REV: 2 JPM No. Initiate a Bleed and Feed of the (Alternate Page 7 of 6 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: (JPM104A.doc) Difficulty
4 Time: 20 minutes Parent Task # 0000130501 FR-H .1 REV: 2 Simulator Setup Initialize to any 100% Power IC Insert Malfunctions:
MAL CFW001A -Trip -31 AFW Pump Trip MAL CFW001 B -Insert -32 AFW Pump Trip MAL CFW001 C -Trip -33 AFW Pump Trip SWI-RCS023D -OFF -PORV 456 Open Position OFF SWI-RCS023C -ON -PORV 456 Closed Position ON MAL TUR002A -Insert -Electrical Turbine Trip Failure MAL TUR002B -Insert -Mechanical Turbine Trip Failure Remove Turbine Trip Failure when SG levels decrease to < 25% WR Trip both MBFPs and allow simulator to run and trip on low SG level. INITIATIAL CONDITIONS A loss of feedwater has occurred. Steps 1-4 of E-O are complete. A transition to ES-O.1 was made at Step 4. A transition to FR-H.1 was made due to a RED path on the Heat Sink CSF. The fold out page requirements for bleed and feed are met. INITIATING CUE You are the ATC and the CRS has directed you to perform a Bleed and Feed of the RCS per FR-H .1 , Starting at Steps 9.
Start a Hydrogen Recombiner Page 1 of 8 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee ID #: Evaluator:
Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 0280011601-1.doc Difficulty: 3 Time: 15 Task Number: 0280010501 3 SOP-C8-7 Start a Hydrogen Recombiner Page 2 of 8 JPM Title: Start a Hydrogen Recombiner JPM Number: S-5(e) KA Number and Importance: 028000A401 Ability to manually operate and/or monitor in the control room: -HRPS controls RO -4.0 SRO -4.0 Suggested Environment: Simulator Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 15 Min Actual Time: ___
References:
3-S0P-CB-007 H2 Recombiner Operation File: 0280011601-1 .doc Difficulty
3 Time: 15 Task Number: 0280010501 3 SOP-CB-7 .
Start a Hydrogen Recombiner Page 3 of 8 INITIAL CONDITIONS: A Large Break LOCA occurred 2 days All actions of ES-1.4 Transfer to Hot Leg Recirculation have been The Operating Crew Transitioned back to ES-1 .3, Transfer to Cold Containment Hydrogen has slowly risen to 1.Current VC Pressure -2 Pre-LOCA VC Pressure -0 Pre-LOCA VC Temperature -31, 32, and 35 Fan Cooler Units are in Offsite power is INITIATING CUES: You are the BOP and the CRS has directed you to place the 31 Hydrogen Recombiner in service. TASK STANDARD: 31 Hydrogen Recombiner is in service. File: 0280011601-1 .doc Difficulty: 3 Time: 15 Task Number: 0280010501 3 SOP-C8-7 Start a Hydrogen Recombiner Page 4 of 8
Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation
2. Energize 31 H2 Recombiner by placing breaker in ON CUE: NPO reports breaker closed Directs NPO to close the breaker for 31 H2 Recombiner on MCC-36C 3. Verify Control Power Available light is lit on Hydrogen Recombiner Panel CUE: Control Power White Light is Lit Observes Control Power Light 4. Verify Manual Heater Power Adjust potentiometer is set to 000 Rotate potentiometer fully counterclockwise

5. Verify Heater Mode Selector Switch is in Manual Observes Switch in Manual 6. Note the following
Current VC Pressure

Pre-LOCA VC Pressure

Pre-LOCA VC Temperature CUE: If Simulating this ...IPM

Current VC Pressure -2 psig

Pre-LOCA VC Pressure -a psig

Pre-LOCA VC Temperature
-98°F Record parameters .7. Determine Pressure Correction Factor (Cp) using Attachment 2 Determine Cp 1.165 +/-.005 8. Record Cp on Attachment 4 Enters 1.165 +/- .005 on Attachment 4 9. Determine Required Heater Power on Attachment 4 (Cp X 42.3 KW) Determine approximately 49.3 +/- 0.3 KW File: 0280011601-1 .doc Difficulty: 3 Time: 15 Task Number: 0280010501 3 SOP-C8-7 Start a Hydrogen Recombiner Page 5 of 8 STEP .10. .11. '12 .13. .14 DESCRIPTIONS I CUES & NOTES Place Recombiner Control Switch in Start and Release CUE: Green Light OFF Red Light ON Slowly Adjust Manual Heater Power until 5 KW is indicated on Heater Power Meter and Hold for 10 minutes CUE: Meter indicates 5 KW Time Compression 10 Minutes has elapsed Slowly Adjust Manual Heater Power until 10 KW is indicated on Heater Power Meter and Hold for 10 minutes CUE: Meter indicates 10 KW Time 10 Minutes has elapsed Slowly Adjust Manual Heater Power until 20 KW is indicated on Heater Power Meter and Hold for 5 minutes CUE: Meter indicates 20 KW Time Compression 5 Minutes has elapsed Adjust Manual Heater Power as required to maintain Required Heater Power per Attachment 4 CUE: Meter indicates 49.3 KW JPM Complete STANDARD Rotate Switch to Start and spring return to neutral Rotate potentiometer clockwise observe heater power meter Rotate potentiometer clockwise observe heater power meter Rotate potentiometer clockwise observe heater power meter Rotate potentiometer clockwise observe heater power meter S/U File: 0280011601-1 .doc Difficulty: 3 Time: 15 Task Number: 0280010501 3 SOP-C8-7 Start a Hydrogen Recombiner Page 6 of 8 Any area of weakness observed? YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 0280011601-1 .doc Difficulty: 3 Time: 15 Task Number: 0280010501 3 SOP-C8-7 Start a Hydrogen Recombiner Page 7 of 8 This JPM is simulated. The Hydrogen Recombiners are not simulated. File: 0280011601-1.doc Difficulty: 3 Time: 15 Task Number: 0280010501 3 SOP-CB-7 Page 8 of 8 INITIAL CONDITIONS: A Large Break LOCA occurred 2 days All actions of ES-1.4 Transfer to Hot Leg Recirculation have been The Operating Crew Transitioned back to ES-1.3, Transfer to Cold Containment Hydrogen has slowly risen to Current VC Pressure -2 Pre-LOCA VC Pressure -0 Pre-LOCA VC Temperature -31,32, and 35 Fan Cooler Units are in Offsite power is INITIATING CUES: You are the BOP and the CRS has directed you to place the 31 Hydrogen Recombiner in service. Task Number I ,
Remove a Power Range Nuclear Instrument From Service Page 1 of 10 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator:
SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager , Nuclear Training. File: 0150021601-1 .doc Difficulty: 2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 2 of 10 JPM Title: Remove a Power Range Nuclear Instrument From Service JPM Number: S-6(f) KA Number and Importance: 015000A201 Ability to (a) predict the impacts of the following malfunctions or operations on the NIS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: -Power supply loss or erratic operation. RO-3.5 SRO-3.9 Suggested Environment: Simulator Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 25 Min Actual Time:
References:
3-S0P-NI-001 Excore Nuclear Instrumentation System Operation File: 0150021601-1 .doc Difficulty
2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 3 of 10 INITIAL CONDITIONS The plant is operating at 100% Power Range Channel N41 is operating The Shift Manager has declared N41 inoperableINITIATING CUES: You are the BOP and the CRS has directed you to remove channel N41 from sevice TASK STANDARD:
Channel N41 removed from service File: 0150021601-1 .doc Difficulty: 2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 4 of 10
Denotes Critical Step S/U STANDARD DESCRIPTIONS I CUES & NOTES STEP Inform operator to BEGIN after completion of review of the Initiating and log time 1. Commence evaluation Obtain Correct Procedure Select Attachment
2. 1 Circle selected channel Circles N41 3. If removing channel from service due to failure obtain guidance from I&C and

4. CUE: Channel is NOT being removed service due to partial Place Dropped Rod Mode Selector Switch Switch rotated to )5. BYPASS Nuclear Instrumentation Drawer N41A If Control Power is available check Dropped Rod Bypass lamp illuminated NIS Rod Drop Bypass PR 41 lamp 011 Checks lamps 5. Panel FBF is illuminated illuminatedNIS Trip Bypass alarm on Panel is Nuclear Instrumentation Drawer N41A Place applicable Rod Stop Bypass switch in Rotate Switch to N41.-6. BYPASS PR N41 Position Nuclear Instrumentation Drawer N50 Place applicable Power Range Channel Percent Power Computer Input Out of Limit 7. CUE: The STA will remove channel from Observe Warning Caution and Reviews Warning 8. Caution and Notes CUE: The CRS is reviewing Tech Specs. File: 0150021601-1
.doc Difficulty
2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Page 5 of STEP DESCRIPTIONS I CUES &NOTES STANDARD S/U .9. Block the dropped rod protection bypass relays for the selected channel by placing the blocking strip across the back of the relay Reactor Protection Channel 1 Rack E*2/E*3 NOTE Blocking strips are installed CUE: Blocking Strips have been Independently Verified Screw bolt in to engage relay .10. Defeat selected channel T signal by placing the delta T Defeat Switch in Defeat Channel 1 Rack 8*8 Rotate Switch to Defeat Ch 1 11 . Verify T Recorder selected to unselected channel Rotate recorder switch to channel 2, 3,or4 12. Observe caution Review Caution 13. Check the Overtemperature T bistables for the unselected channels are extinguished on Panel SOF NA the Selected Channel and Checks the remaining channels extinguished

14. Observe Note Reviews Note .15. Place the Overtemperature T bistable for Loop 1 Over Temp Trip in the tripped position RackA-4 Places trip switch in the up position 16. Check Overtemperature T bistable for Loop 1 Over Temp Trip is lit Panel SOF Grid A-11 Observes light illuminated

17. Check Overtemp Channel Trip or Rod Stop alarm lit on Panel SAF Observes annunciator lit 18. Verify Rod Control Mode Selector Switch is in Manual Observes Switch is in Manual .19. Place Power Mismatch Bypass Switch in PYBASS PR N41 Nuclear Instrumentation Drawer N50 Rotates Switch to N41 position File: 0150021601-1
.doc Difficulty
2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Page 6 of STANDARD S/U DESCRIPTIONS I CUES & NOTES STEP When a minimum of two minutes has elapsed, Rotates Rod Control Return Rod Control to Automatic Mode Selector Switch 20. CUE: Time Compression 2 minutes has to Automatic Place Detector Current Comparator Rotates switch Bypass PRN41 Nuclear Instrumentation Drawer N50 Section Switch in PR N41 Place Detector Current Comparator Rotates switch to Section Switch in PR N41 Bypass PRN41 Nuclear Instrumentation Drawer N50 22.
Place Comparator Channel Defeat Switch Rotates switch to '.23. N41 position N41 position Nuclear Instrumentation Drawer N37/N46 Check Comparator Defeat light is lit 24. Observes light lit Nuclear Instrumentation Drawer N50 Check no other overpower high range hi trip bistables are tripped on Bistable Observes no other 25. Panel light lit Panel SOF Grid B/C/D-9 Observes Overpower Check if overpower low range high flux trips 26. Low range high flux are NOT Blocked are blocked Observe NOTES 27. Reviews Notes Trip all NIS bistables associated with selected channel by removing both tJl28. Removes fuses and control power Nuclear Instrumentation Drawer Check alarms on Panel NIS Power Range Loss of Detector 29. Voltage Observes alarms lit NIS Poser Range Single Channel Range Determine Overpower Low Range High Flux Given Power greater 30. Trips are blocked than 25% Check Overpower High Range Hi Flux Trip bistable for N41 is lit 31 . Observes light lit Panel SOF Grid A-9 Determine Overpower Low Range High Flux Given Power greater 32. Trips are blocked than 25% File: 0150021601-1,doc Difficulty: 2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 7 of 10 STEP DESCRIPTIONS I CUES &NOTES STANDARD S/U 33. Verify NR-45 Recorder selected to an unselected channel Rotate switch to Channel 2, 3, or 4 if necessary J PM Complete File: 0150021601-1 .doc Difficulty
2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 8 of 10 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information
File: 0150021601-1
.doc Difficulty
2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 9 of 10 Reset Simulator to any 100% Power IC. File: 0150021601-1.doc Difficulty:
2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Page 10 of 10 INITIAL CONDITIONS The plant is operating at 100% Power Range Channel N41 is operating The Shift Manager has declared N41 INITIATING CUES: You are the BOP and the CRS has directed you to remove channel N41 from sevice Task
Reset R-18 Alarm Setpoint using the RM-23A Module Page 1 of 8 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager , Nuclear Training. File: 0730161601-1.doc Difficulty: 3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 ---Reset R-18 Alarm Setpoint using the RM-23A Page 2 of JPM Title: Reset R-18 Alarm Setpoint using the RM-23A Module JPM Number: S-7(g) KA Number and Importance: 073000A402 Ability to manually operate and/or monitor in the control room: -Radiation monitoring system control panel. RO -3.7 SRO -3.7 Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: Actual 3-S0P-RM-008 Radiation Monitor Control Cabinet (Bantam 11/RM-23A Cabinet File: 0730161601-1 .doc Difficulty
3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 3 of 8 INITIAL CONDITIONS Preparations are underway to release 31 Monitor The current alarm setpoint for R-18 is 4.0 X The calculated alarm setpoint for the release is 1.25 X 10-3 The Bantam 11 Control Cabinet is OOS for The CRS has reviewed 3-SOP-RM-01 0 and the setpoint change is The Radiation Monitor Supervisory Key is at location 58 in the Key RackINITIATING CUES: You are the BOP and the CRS has directed you to reset the Alarm setpoint for 18 to 1.25 X 10-3 IJCi/ml using the RM-23A in accordance with 3-S0P-RM-008 Step 4.3.5.3. TASK STANDARD:
R-18 Alarm setpoint is reset using the RM-23A controller. File: 0730161601-1.doc Difficulty: 3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 4 of 8 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Commence evaluation
1. 2. Determine NOT changing R-1 or R-33 Setpoint Given in initial conditions
.3. Depress Channel Depresses R18 LlQ button on RM-23A Insert key and turn Norm Supervisor switch to Supervisor Insert Key and rotate switch to Supervisor
5. Verify SUPV Mode LED is ON Observes SUPV Mode LED ON 6. If changing High Alarm set point ENTER 009 Enter a a 9 using keypad 7. Determine NOT changing Alert set point at this time 8. Depress ITEM and verify current setpoint is displays Depresses ITEM button and observes digital
.9. Enter new set point using the following format [1] [2] [5] [-] [0] [3] Enters data in stated format .10. Verify desired value is displayed then depress ENTER key Observes digital display correct then presses ENTER key 11. If value displayed is not correct, depress CLEAR button and repeat procedure step 4.3.5.4 If value displayed is not correct press CLEAR button and re-perform J PM starting at JPM step 3 File: 0730161601-1.doc Difficulty: 3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 5 of 8 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 11. Turn Normal Supervisory Key Switch to NORMAL and remove key Rotate key to NORM and remove 12 Depress desired channel button to return display to normal Depress R18 UQ button 13 IF RM-23A alarm set point was changed Verify Supv Mode LED is OFF Observes LED is OFF JPM is Complete File: 0730161601-1 .doc Difficulty
3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 6 of 8 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 0730161601-1 .doc Difficulty
3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 7 of 8 This JPM can be run from any IC. File: 0730161601-1.doc Difficulty:
3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Page 8 of 8 INITIAL CONDITIONS Preparations are underway to release 31 Monitor The current alarm setpoint for R-18 is 4.0 X 10-4 The calculated alarm setpoint for the release is 1.25 X 10-3 The Bantam 11 Control Cabinet is OOS for The CRS has reviewed 3-SOP-RM-01 0 and the setpoint change is The Radiation Monitor Supervisory Key is at location 58 in the Key INITIATING CUES: You are the BOP and the CRS has directed you to reset the Alarm setpoint for 18 to 1.25 X 10-3 !-ICi/ml using the RM-23A in accordance with 3-S0P-RM-008 Step 4.3.5.3. Task
Transfer Buses 1 -4 to the Station Aux Transformer Page 1 of 9 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee ID #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training. File: 0800031601-1.doc Difficulty: 2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 ---Transfer Buses 1 -4 to the Station Aux Page 2 of JPM Title: Transfer Buses 1 -4 to the Station Aux Transformer JPM Number: S-8(h) KA Number and Importance: 062000A401 Ability to manually operate and/or monitor in the control room: -All breakers (including available switchyard) RO -3.3 SRO -3.1 Suggested Environment: Actual Testing Alternate Path: Time Critical: Estimated Time: 15 Min Actual 3-S0P-EL-005 Operation of On-Site Power Sources File: 0800031601-1 .doc Difficulty: 2 Time: 15 Task Number: 0800020201 3-SOP-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 3 of 9 INITIAL CONDITIONS: A plant shutdown is in progress in accordance with 3-POP-3.1. Generator Load is approximately 35 MWe INITIATING CUES: You are the BOP and the CRS has directed you to Transfer Buses 1 -4 to the Station Aux Transformer in accordance with 3 SOP-EL-005 section 4.4. TASK STANDARD: Buses 1 -4 are energized from the Station Aux Transformer and Unit Aux Transformer breakers are open. File: 0800031601-1 .doc Difficulty: 2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 4 of 9 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below STANDARD S/U 1. Commence evaluation
2. Observe NOTES before step 4.4.1 Reviews Notes 3. Ensure less than 100 volts difference between Station and Unit Auxiliary Transformers Observe Meters; Adjusts MTG Voltage, Unit Aux or Station Aux Transformer Tap Changers if necessary If desired to transfer 6.9 KV Bus 1 to the Station Aux Transformer Determine transfer is desired 4. 5. 6. ** Perform Voltage Check per step 4.4.1 Place 6900 Bus 1 Synchroscope in Bus 1 Bus 5 position If Synchroscope is at 12 o'clock then Close the Bus No. 1-5 Tie Breaker Open 6900 Bus 1 Normal Feed Breaker Observe Station Aux and Unit Aux transformer voltage meters Places handle in switch location and rotate switch to bus 1 bus 5 position Rotate Switch to Close then release to auto Rotate Switch to Open the release to auto 8. Place 6900 Bus No. 1 Synchroscope in Off Rotate switch to Off 9. Ensure less than 2000 amps on 6900 KV bus 5 Observe meter determines
< 2000 amps File: 0800031601-1.doc Difficulty: 2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 5 of 9 STEP DESCRIPTIONS I CUES &NOTES STANDARD S/U If desired to transfer 6.9 KV Bus 2 to the Station Aux Transformer Determine transfer is desired 10. Ensure both 2A-3A Tie breaker is Open Observes breaker Open 11 . Perform Voltage Check per step 4.4.1 Observe Station Aux and UnitAux transformer voltage meters . 12. Place 6900 Bus 2 Synchroscope in Bus 2 Bus 5 position Places handle in switch location and rotate switch to bus 1 bus 5 position 13. If Synchroscope is at 12 o'clock then Close the Bus No. 2-5 Tie Breaker Rotate Switch to Close then release to auto . 14. Open 6900 Bus 2 Normal Feed Breaker Rotate Switch to Open the release to auto 15. Place 6900 Bus No.2 Synchroscope in Off Rotate switch to Off 16. Ensure less than 2000 amps on 6900 KV bus 5 Observe meter determines < 2000 amps If desired to transfer 6.9 KV Bus 3 to the Station Aux Transformer Determine transfer is desired 17. Ensure both 2A-3A Tie breaker is Open Observes breaker Open 18. Perform Voltage Check per step 4.4.1 Observe Station Aux and Unit Aux transformer voltage meters . 19. Place 6900 Bus 3 Synchroscope in Bus 3 Bus 6 position Places handle in switch location and rotate switch to bus 1 bus 5 position . 20. If Synchroscope is at 12 o'clock then Close the Bus No. 3-6 Tie Breaker Rotate Sw i tch to Close then release to auto File: 0800031601-1 .doc Difficulty
2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 6 of 9 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU . 21. Open 6900 Bus 3 Normal Feed Breaker Rotate Switch to Open the release to auto 22 . Place 6900 Bus NO.3 Synchroscope in Off Rotate switch to Off 23. Ensure less than 2000 amps on 6900 KV bus 6 Observe meter determines
< 2000 amps If desired to transfer 6.9 KV Bus 4 to the Station Aux Transformer Determine transfer is desired 24. Perform Voltage Check per step 4.4.1 Observe Station Aux and Unit Aux transformer voltage meters .25. Place 6900 Bus 4 Synchroscope in Bus 4 Bus 6 position Places handle in switch location and rotate switch to bus 1 bus 5 position 26. If Synchroscope is at 12 o'clock then Close the Bus No. 4-6 Tie Breaker Rotate Switch to Close then release to auto . i 27. Open 6900 Bus 4 Normal Feed Breaker Rotate Switch to Open the release to auto 28. Place 6900 Bus NO. 4 Synchroscope in Off Rotate switch to Off 29. Ensure less than 2000 amps on 6900 KV bus 6 Observe meter determines < 2000 amps 30. When transfer complete, ensure Unit Aux and Station Aux Tap Changers are in automatic Ensure both tap changer switches are pulled out JPM is complete File: 0800031601-1.doc Difficulty
2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 7 of 9 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information
File: 0800031601-1
.doc Difficulty
2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 8 of 9 Simulator Setup Reset Simulator to Ie -9 Reduce Load to < 40 MWe Take a snapshot if JPM is to be used more than once. File: 0800031601
-1.doc Difficulty
2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Page 9 of 9 INITIAL CONDITIONS:
A plant shutdown is in progress in accordance with 3-POP-3.1. Generator Load is approximately 35 MWe INITIATING CUES: You are the BOP and the CRS has directed you to Transfer Buses 1 -4 to the Station Aux Transformer in accordance with 3 SOP-EL-005 section 4.4. FileTask
Locally Start 32 Aux Boiler Feedpump Page 1 of 9 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager, Nuclear Training . File: 0610011604-1 .doc Difficulty
3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Page 2 of JPM Title: Locally Start 32 Aux Boiler Feedpump JPM Number: In Plant 1 (j) KA Number and Importance:
061000A207 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: -Air or MOV failure. RO -3.4; SRO -3.5 Suggested Environment: In Plant Actual Testing Environment: Alternate Path: YES Time Critical: NO Estimated Time: 30 Min Actual Time:
References:
3-S0P-ESP-001 Local Equipment Operation and Contingency Actions File: 0610011604-1.doc Difficulty: 3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump Page 3 of 9 INITIAL CONDITIONS:
1. The Control Room has been evacuated due to a fire. 2. No ABFPs started. 3. 480V power is not available

4. Current SG Pressures are all approximately 850 psig INITIATING CUES: You are the RO in the ABFP Building and the CRS has directed you to locally start 32 ABFP per 3-S0P-ESP-001, section 4.1.8 up to and including section 4.1.8.11 TASK STANDARD:
32 ABFP running with approximately 1000 psig discharge pressure File: 0610011604-1.doc Difficulty: 3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump Page 4 of 9
Denotes Critical Step STEP DESCRIPTIONS
/ CUES & NOTES STANDARD S/U NOTE: Remind operator to NOT change any switch or valve positions
1. Obtain correct procedure 3-S0P-ESP-001, section 4.1.8 2. Step 4.1.8.4 Determine if MS-PCV-1310A, 32 ABFP Steam Supply Isolation valve, is OPEN CUE: Valve is OPEN Observes valve stem limit switch position 3. Step 4.1 .8.5.a Isolate Air supply and bleed off at fitting at 131 OA Close Air Supply Valve and break a fitting between the isolation valve and 1310A actuator 4. Determine if MS-PCV-1310B, 32 ABFP steam Supply Isolation valve, is OPEN CUE: Valve is OPEN Observes valve stem limit switch position 5. Step 4.1.8.6.a Isolate Air supply and bleed off at fitting at 131 OA Close Air Supply Valve and break a fitting between the isolation valve and 1310B actuator 6. Step 4.1.8.7 If directed to use handwheels to control FCVs then rotate applicable FCV handwheels in the closed direction NOTE: The candidate will demonstrate how to control FCVs on one valve CUE: You are directed to control the FCVs using the handwheels.
Demonstrate how this is done on FCV-405A See Below File: 0610011604-1 .doc Difficulty
3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump Page 5 of 9 STEP .7. .S. 9. 10. .11. DESCRIPTIONS
/ CUES & NOTES Step 4.1.8.7.a Rotate handwheel in the closed direction until handwheel engages diaphragm or valve fully closed CUE: Valve indicates closed Step 4.1.8.7.b.1 Close IA 1675 (IA-PCV-1551 IA Isolation Valve) CUE: Valve indicates closed Step 4.1.8.7.b.2 Bleed off air using petcock of IA-PCV-1551 regulator CUE: Petcock open air heard venting Step 4.1 .8.7.b.3 Control FCV position using handwheel Step 4.1.8.8.a ADJUST HCV-1118 32 ABFP Turbine Speed Control manual handwheel for idle speed CUE: Handwheel in close position STANDARD Rotate handwheel in the close direction Rotates valve in close direction Rotate petcock counter clockwise CLOSE 1118 using manual handwheel S/U 12. .13. .14. Step 4.1.8.8.b CLOSE IA-865 32 ABFP MS-HCV-1118 Instrument Air Isolation valve CUE: Valve closed Step 4.1.8.8.c BLEED off air from 32 ABFP MS-HCV-1118 by removing cap and opening MS-456 CUE: Cap removed and valve open Step 4.1.8.8.d OPEN HCV-1118 , 32 ABFP Turbine Speed Control valve approximately 1/8" CUE: Valve open 1/8" NOTE: 1/8" is the first scribe mark on the indicator CLOSE IA-865 Remove cap and OPEN MS-456 Manual handwheel adjusted until valve stem -1/8" OPEN .15. Step 4.1 .8.9 Place 32 ABFP Trip/Auto/On local control switch to ON CUE: Turbine heard increasing speed of pump Rotate 32 ABFP Trip/Auto/On local control switch to ON File: 0610011604-1.doc Difficulty: 3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Page 6 of STEP DESCRIPTIONS / CUES & NOTES STANDARD StU 16. Review notes prior to step 4.1.8.10 Notes reviewed Step 4.1.8.10 Verify correct Steam Inlet pressure for 32 ABFP 17. .18. .19. .20. CUE: Steam Inlet pressure indicates 250 psig NOTE: There are two locations for steam inlet pressure indication. One on the wall next to the PCV-1139 Auto/Manual Loading Station and the second is on the gauge panel for 32 AFW Pump. Step 4.1.8.1 0.a.1 Adjust PCV-1139 AIM station manual loading pressure to match the instrument loading pressure (do not exceed 13 psig) CUE: Instrument Loading Pressure indicates 5 psig (Left Hand Meter) Step 4.1.8.10.a.2 Tum the AutolManual switch on the PCV-1139 AIM station to MANUAL Step 4.1.8.1 0.a.3 Slowly adjust PC-1139 AM Station Manual loading pressure to approximately 12 psig Observes 32 ABFP discharge pressure gauge NOT indicating 600 psig Rotate handle until pressure indicates approximately 5 psig Switch rotated to Manual Rotate knob until indicator 12 psig .21 . CUE: Indicator reads 12 psig Step 4.1.8.10.a.4 Adjust PC-1139 AIM station Manual Loading pressure to maintain steam inlet pressure to 32 Aux Boiler Feed Pump turbine at approximately 600 psig Observe inle t pressure approximately 600 psig NOTE to evaluator Step 4.1.8.10.b (Manual operation of PCV-1139) is Not Applicable .22. 18 Step 4.1.8.11 Adjust turbine speed using HCV-1118 until discharge pressure is 1000 psig CUE: Discharge Fressure indicates 1000 psig Inform SM 32 ABFP discharge pressure is 1000 psig Observes discharge pressure approximately 1000 SM Informed CUE: SM acknowledges File: 0610011604-1.doc Difficulty: 3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump Page 7 of 9 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU J PM Complete File: 0610011604 -1.doc Difficulty
3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump Page 8 of 9 Any area of weakness observed?
YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information
File: 0610011604-1.doc Difficulty:
3 Time: 30 Task Number: 0610010404 3-S0P-ESP-1 In Page 9 of 9 INITIAL CONDITIONS:
1. The Control Room has been evacuated due to a fire. 2. No ABFPs started. 3. 480V power is not available

4. Current SG Pressures are all approximately 850 psig INITIATING CUES: You are the RO in the ABFP Building and the CRS has directed you to locally start 32 ABFP per 3-S0P-ESP-001, section 4.1.8 up to and including section 4.1.8.11 FileTask
Start 32 CCW Pump from MCC312A Page 1 of 7 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Date: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation . This material may not be reproduced without the authorization of the Manager , Nuclear Training. File: 0840281604-1 .doc Difficulty: 2 Time: 10 Task Number: 0840280504 . 3-S0P-EL-12 In Start 32 CCW Pump from MCC312A Page 2 of 7 JPM Title: Start 32 CCW Pump from MCC312A JPM Number: In Plant -2(j) KA Number and Importance: 062000K201 Knowledge of bus power supplies to the following: -Major system loads. RO -3.3; SRO -3.4 Suggested Environment: In Plant Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 10 Min Actual Time:
References:
3-AOP-SSD-1 Control Room Inaccessibility Safe Shutdown File: 0840281604-1 .doc Difficulty: 2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Start 32 CCW Pump from MCC312A Page 3 of 7 INITIAL CONDITIONS: The plant is in MODE 3 Control of 32 CCW pump from the Control Room is prevented due to Control Room evacuation due to a fire Normal 480 volt power to the CCW pumps is not available 32 CCW pump will be the only load on MCC-312A Power is available to MCCs-312 and 312A The Nuclear NPO is standing by to assist you INITIATING CUES: You are the BOP and the Shift Manager has directed you to transfer the power supply for 32 CCW pump to MCC-312A and start the pump per SOP-EL-12, Section 4.2 TASK STANDARD: 32 CCW Pump running from its alternate feed (MCC-312A). File: 0840281604-1 .doc Difficulty: 2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Start 32 CCW Pump from MCC312A Page 4 of 7
Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below STANDARD S/U 1. Commence evaluation
2. 3 4. 5. .6 .7 Remove load from Bus 312 per Attachment 1 CUE: MCC-A, C or E-1 feeder breaker open Visually verify 32 CCW pump is not running CUE: Nuclear NPO reports 32 CCW pump is not running Verify 32 CCW Pumps transfer switch is de-energized CUE: Nuclear NPO reports all 8 lights are extinguished Review Caution and Note Unlock and place 32 CCW pump alternate feed transfer switch in Alternate feed position QUESTION:
Ask candidate to describe the location of the Alternate Feed Transfer Switch and how to operate it. CUE: Nuclear NPO reports transfer switch rotated clockwise 360 0 to Alternate Feed position Unlock and place disconnect switch on 312A for 32 CCW pump to on CUE: Disconnect switch is on MCC-A feeder OR MCC-C feeder OR MCC-E-1 feeder open Direct Nuclear NPO to verify pump is not running Direct Nuclear NPO to verify all eight indicating lights are off Caution and Note reviewed Direct Nuclear NPO to rotate disconnect switch 360 0 to alternate feed position Unlock and place disconnect switch to on File: 0840281604-1.doc Difficulty: 2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Start 32 CCW Pump from MCC312A Page 5 of 7 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U .8 Start 32 CCW pump CUE: Key switch in start position Push in and turn key switch to start position 9 Verify 32 CCW pump is running CUE: Red running light is illuminated Observe red running light illuminates JPM Complete File: 0840281604-1.doc Difficulty: 2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Start 32 CCW Pump from MCC312A Page 6 of 7 Any area of weakness observed? YEsDNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: 0840281604-1 .doc Difficulty
2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Page 7 of 7 INITIAL CONDITIONS:
The plant is in MODE 3 Control of 32 CCW pump from the Control Room is prevented due to Control Room evacuation due to a fire Normal 480 volt power to the CCW pumps is not available 32 CCW pump will be the only load on MCC-312A Power is available to MCCs-312 and 312A The Nuclear NPO is standing by to assist you INITIATING CUES: You are the BOP and the Shift Manager has directed you to transfer the power supply for 32 CCW pump to MCC-312A and start the pump per SOP-EL-12, Section 4.2 FileTask .. Perform Local Containment Isolation Valve Lineup IVSW Page 1 of 7 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: SAT UNSAT This JPM was administered for qualification? YES NO The Training Department developed this material for the Entergy training programs. Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation. This material may not be reproduced without the authorization of the Manager , Nuclear Training. File: Difficulty
3 Time: 20 Task Number: 3-S0P-CB-11 In Perform Local Containment Isolation Valve Lineup IVSW Page 2 of 7 JPM Title: Perform Local Containment Isolation Valve Lineup IVSW JPM Number: In Plant -3(j) KA Number and Importance:
078000K4.01 Knowledge of lAS design feature(s) and/or interlock(s) which provide for the following: -Manual/automatic transfers of control RO -2.7; SRO -2.9 Suggested Environment: In Plant Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: Actual Time:
References:
3-S0P-CB-11 Non-Automatic Containment Isolation 3-COL-CB-004 Isolation Valve Seal Water System 3-COL-LV-001 Locked Valve Check Off List File: Difficulty
3 Time: 20 Task Number: 3-S0P-C8-11 In Perform Local Containment Isolation Valve Lineup IVSW Page 3 of 7 INITIAL CONDITIONS:
The plant experienced a Large Break The operating crew is in 3-ES-1.3, Transfer to Cold Leg Internal Recirculation is All RCPs are INITIATING CUES: You are the Nuc Side NPO and the CRS has directed you to perform 11 Attachment 1 steps 1-5 Containment Isolation Valves Local Lineup. TASK STANDARD: 3-S0P-CB-11 Attachment 1 Steps 1-5 complete. File: Difficulty: 3 Time: 20 Task Number: 3-S0P-C8-11 In Perform Local Containment Isolation Valve Lineup Page 4 of Denotes Critical Step S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below STANDARD STEP DESCRIPTIONS I CUES & NOTES 1. Commence evaluation Observes Note Observe Note before Step 1 2. Open IV-1492 Manual N2 IVSW Locates and Opens PAB 41' behind Heat Trace Panel.3. Give candidate COL-C8-004 Isolation Seal Water System if requested to Open IV-1493 Manual Seal Water Locates and Opens Valve PAB 41' behind Heat Trace Panel Open IV-1443 Manual N2 Header 1090 Outlet Locates and Opens 5. Valve N2 Bottle Bank 55' PAB Close SI-859A Accumulator Injection Test Line CUE: If candidate attempts to access valves, Verified Closed Using 6. inform him as HP that the radiation levels are COL too high during recirculation. Provide candidate Locked Valve Check List when Close SI-859C Accumulator Drain/Safety Verified Closed Using 7. Injection Test Line Isolation COL Close SA-24-1 Station Air to Containment Verified Closed Using 8. Containment Isolation Valve COL File: Difficulty: 3 Time: 20 Task Number: 3-S0P-C8-11 In Perform Local Containment Isolation Valve Lineup IVSW Page 5 of 7 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 9. Close SA-24-2 Station Air to Containment Containment Isolation Valve Verified Closed Using COL 10. Ensure Breakers are Closed MCC-36A
AC-MOV-743 RHR Miniflow Isolation

AC-MOV-744 RHR Pump Discharge Isolation

CH-MOV-441 31 RCP Seal Injection Isolation

CH-MOV-442 32 RCP Seal Injection Isolation

CH-MOV-443 33 RCP Seal Injection Locate and Observe Breakers Closed If necessary Simulate Closing Breakers Isolation

CH-MOV-444 34 RCP Seal Injection Isolation

SI-MOV-885A Containment Sump RHR Suction . 11. Ensure Breakers are Closed MCC-36B

AC-MOV-1870 RHR Miniflow Isolation

CH-MOV-250A 31 RCP Seal Injection Isolation

CH-MOV-250B 32 RCP Seal Injection Isolation

CH-MOV-250C 33 RCP Seal Injection Isolation

CH-MOV-250D 34 RCP Seal Injection Isolation Locate and Observe Breakers Closed If necessary Simulate Closing Breakers

SI-MOV-882, RHR Pump RWST Suction Isolation

SI-MOV-885B Containment Sump RHR Suction JPM Complete File: Difficulty
3 Time: 20 Task Number: 3-S0P-C8-11 In Perform Local Containment Isolation Valve Lineup IVSW Page 6 of 7 Any area of weakness observed?
YES D NoD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information: File: Difficulty: 3 Time: 20 Task Number: 3-S0P-C8-11 In Page 7 of 7 INITIAL CONDITIONS: The plant experienced a Large Break The operating crew is in 3-ES-1 .3, Transfer to Cold Leg Internal Recirculation is All RCPs are stoppedINITIATING CUES: You are the Nuc Side NPO and the CRS has directed you to perform 11 Attachment 1 steps 1-5 Containment Isolation Valves Local Lineup. Task
Appendix D Scenario Outline Form ES-D-1 Facility: IPEC Unit 3 Scenario No.: 1 Op-Test No.: 1 Examiners: Operators: Initial Conditions
Plant is at 46% . 31 EDG is OOS for an oil system modification.
Turnover: Return power to 100%. 31 EDG is OOS and not expected back on this shift. Event No. Malf. No. Event Type* Event Description 1 N/A R(ATC) N(BOP) N(CRS) Perform power ascension. 2 PRS006 B I(ALL) TS(CRS) Controlling PZR level instrument fails low causing letdown to isolate. Channel is defeated and letdown is restored. 3 CVC003 C(ALL) TS(CRS) Letdown leak inside containment. Leak will be isolated. 4 EPS005 D C(ALL) 480V Bus 6A fault. 5 ATS004 AlB PRSOO3 D M(ALL) Sequential loss of Main Feedwater Pumps leading to plant trip. PORV fails open, cannot be isolated. 6 SIS004A IB C(CRS) 31 and 32 Safety Injection Pumps will not auto-start. (Neither board operator credited since either one may start pump.) 7 EPS001 C(ALL) Station Blackout when Containment Phase A is reset. * (N)ormal , (R)eactivity, (I)nstrument, (C)omponent , (M)ajor 2010 IP3 NRC Exam Scenario 1 Page 10f 13 Session Outline: The session begins with power at 46% and 31 EDG out of service for an oil system modification. The team has been instructed to return the plant to 100% at 10% an hour. They will begin raising power per POP-2.1, "Operation above 45% Power". When sufficient load ascension has been observed, the controlling PZR Level channel will fail low causing Letdown to isolate. The team will respond and restore Letdown per AOP-INST-1, "Instrument or Controller Failures". When Letdown has been restored, a leak will occur on the Letdown line inside containment. This can be isolated per AOP-LEAK-1, "Sudden Increase in Reactor Coolant System Leakage". Following leak isolation, a fault of 480V Bus 6A will occur. The team will respond per AOP-480V-1, "Loss of Normal Power to any Safeguards 480V Bus". When the team has had time to address Charging, Service Water and RCP seal cooling, the Main Boiler Feed Pumps will sequentially trip. In response, the Team will trip the reactor as per the guidance of AOP-FW-1, "Loss of Feedwater" (although formal entry into the AOP is not required). On the trip, PORV PCV-456 will fail open. Since Bus 6A is faulted, the MOV Block valve for this PORV cannot be closed. 31 and 32 SI pumps will not start, but can be started manually. RCPs will be tripped due to loss of subcooling. A LOOP will occur when Containment Isolation Phase A is reset. The team will have to respond per EOP LOOP-1, "Loss of Offsite Power after SI Reset". When the EOP LOOP-1 has been completed or transition to E-1 is announced, the scenario will be terminated. Procedure flowpath: POP-2.1, AOP-INST-1, AOP-Leak-1, AOP-480V-1, E-O, LOOP-1, E-1 Critical Tasks: CT 1: Start at least 1 High Head Safety Injection Pump. CT 2: Trip RCPs when RCP trip criteria are met. CT 3: Start Essential Service Water Pump to cool EDGs following LOOP. 2010 IP3 NRC Exam Scenario 1 Page 20f 13 Setup/Event Simulator Setup and Instructor Directions INSTRUCTOR Expected response/instructor cues ACTIONS IC Reset Reset Simulator to 46% power IC SES Setup Batch File Run setup schedule (U3 2010 Scenario 1) and verify malfunctions and over-rides have been entered. Loads L T -460 fails low on trigger 2 Loads letdown leak inside VC on trigger 3 Loads 6A fault on trigger 4 Loads sequential MBFP trips on trigger 5 Loads stuck open PORV when reactor trips Loads station blackout on Phase A reset Loads 31 EDG OOS Loads auto-start failures on 31/32 SI pumps Floor Setup Perform setup checklist. Update the Protected Equipment PC. Risk is Yellow HANG PROTECTED EQUIPMENT tags for: 32 and 33 EDG PTO 31 EDG Event 1 Power Ascension Make notifications as requested by team. Event 2 Click the Trigger 2 button at lead evaluator direction. L T -460 fails low w/o ramp or delay MAL-PRS006B Role Play If I&C requested to investigate: Inform team that a troubleshooting package is being developed. Event 3 Click the Trigger 3 button at lead evaluator direction. Letdown leak in VC w/o ramp or delay MAL-CVC003 Role Play When called to support Excess Letdown Open/adjust 33 charging pump recirc valve Event 4 Click the Trigger 4 button at lead evaluator direction Fault on Bus 6A w/o ramp or delay MAL-EPS005D 2010 IP3 NRC Exam Scenario 1 Page 30f 13 Setup/Event Simulator Setup and Instructor Directions INSTRUCTOR Expected response/instructor cues ACTIONS Role Play If asked to investigate Bus 6A Bus has smell of ozone and probably tripped on actual fault. More troubleshooting will be required. Event 5 Click the Trigger 5 button at lead evaluator direction MBFPs trip sequentially 31 trips on trigger MAL -A TS004A 32 trips with 60 second delay ATS004B Role Play If asked for field actions Support team as requested. 2010 IP3 NRC Exam Scenario 1 Page 40f 13 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No. : 1 Event No.: 1 Page 1 of 1 Event
Description:
Power Ascension Time Position Applicant's Actions or Behavior Note: Team will have been about power ascension in a briefing room prior to taking the watch. A reactivity plan will have been developed before the team comes to the simulator. ATC Energize all PZR backup heaters ATC If dilution is performed per reactivity plan:
Set primary water integrator for desired total dilution.

Place Makeup Mode Control Selector Switch in Dilute

Place the Makeup Control Switch in Start and back to Auto

Monitor Dilution If rod withdrawal is performed:

Place Rod Control Mode Selector Switch in Manual

Withdraw Control Rods BOP Peer check dilution or rod withdrawal BOP Using the MTG Governor, raise load per load schedule CRS Supervise reactivity addition and load increase Lead Evaluator When sufficient load ascension has been observed notify booth to insert Event 2. 2010 IP3 NRC Exam Scenario 1 Page Sot 13 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No. : 1 Event No.: 2 Page 1 of 1 Event Description
Controlling PZR Level instrument fails low. Time Position Applicant's Actions or Behavior CREW Diagnose level failure based on:
PZR Low Level Alarm

LCV-459 Indicates Closed ATC Announce failure of PT -460 low Place charging pump controller in manual CRS Instruct team to perform immed i ate operator actions of AOP-INST-1, Instrument or Controller Failures. ATC Checks for indications of other instrument failure CRS Enters AOP-INST-1 and re-checks instrument status with ATC Verifies charging pump in manual BOP Verifies alarms for failure CRS Goes to section of procedure for failed PZR level instrument BOP In back panel B-6 defeat failed level channel by taking U460A LEVEL DEFEAT in DFT CHII BOP Close letdown orifice valve CH-AOV-200B BOP Place PCV-135and TCV-130 in manual and 50% BOP Open LCV-459 BOP Open 200B and adjust HCV-142 and PCV-135 and TCV-130 ATC Adjust charging pump speed to maintain seal injection ATC Reset backup heaters by placing switches in off and back to on CRS Refer to T.S. T.S. Table 3.3.1-1 Function 8 will not be met 6 hour AOT to trip bistables per T.S. 3.3.1 Condition H Note: When T.S. has been referenced, the next event can be entered. The next step in the procedure is to trip bistables.
If this is observed bistable Loop 2 High Level Trip in rack A-10 will be tripped. Lead Evaluator Instruct booth to enter Event 3 2010 IP3 NRC Exam Scenario 1 Page 60t 13 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No. : 3 Page 1 of 1 Event Description
Letdown leak inside containment.
I I lillie Position Applicant's Actions or Behavior ATC/BOP Diagnose letdown leak by indications of no indicated letdown flow and VCT level decrease. May see increase in VC humidity and sumps levels. VC Sump Pump Running alarm will annunciate. CRS Enters AOP-LEAK-1 Sudden Increase in Reactor Coolant System Leakage May enter 3-AOP-CVCS-1 which will also isolate letdown. CRS Will check for leaks in PORVs , Safeties, SGs CRS Go to section for letdown leak BOP Close 200B, 459 and 460 valves may be closed as soon as procedure is entered. ATC Reduce charging pump speed BOP Close HCV-142 CREW Should determine that leak has been isolated CRS Direct BOP to place Excess Letdown in Service BOP Using 3-S0P-CVCS-002 Place Excess Letdown in service:
Open CCW Valves to/from Excess Letdown HX 0 AC-AOV-793 , 796, 791, 798

Have 33 Charging Pump recirc valve opened by NPO 0 CH-409

Position CH-AOV-215 to divert Excess Letdown to RCDT

Crack open CH-HCV-123 about 10%

Open Excess Letdown isolation valves CH-AOV-213A1B

Open HCV-123 to warmup Excess Letdown

Align Excess Letdown to VCT by taking AOV-215 to Normal ATC Adjust charging pump speed to restore PZR level and maintain seal injection CRS Should address T.S. for RCS leakage (3.4.13 Condition A) and possibly PZR high level (3.4.9 Condition A). May have to ask CRS as follow up question.
Lead Evaluator When Excess Letdown flow has been established have booth insert Event 4 2010 IP3 NRC Exam Scenario 1 Page 70f 13 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Page 1 of 1 Event Description
480V Bus 6A fault. Time Position Applicant's Actions or Behavior CREW Diagnose Loss of Bus 6A CRS Enters 3-AOP-480V-1 , Loss of Normal Power to a Safeguards 480V Bus ATC Start a charging pump BOP Should call Nuke NPO to open recirc valve for running charging pump BOP Start SW Pumps after checking pressure CRS Check T.S. in either 8 hour AOT for inoperable 480V bus per 3.8.9 Condition A or LCO 3.0.3. due to 2 inoperable offsite circuits and EDG to bus (3.8.1 Condition H). Note: Event may proceed, but there will be no resolution on returning power to the bus. Lead Evaluator When sufficient actions have been observed have booth insert Event 5 2010 IP3 NRC Exam Scenario 1 Page 80t 13 Appendix Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No.: 1 Event No.: Page 1 of 1 Event
Description:
Sequential loss of Main Feedwater Pumps leading to plant trip. Position Applicant's Actions or Behavior Time Diagnose loss of first MBFP based on alarm and pump indication CRS BOP/ATC Direct team to perform immediate operator actions of AOP-FW-1, Loss of Feedwater BOP/ATC Diagnose loss of second Trips the Directs team to perform the immediate operator actions of E-O, Reactor Trip or Safety Injection ATC Verifies reactor trip by checking: Flux decreasing Rod Bottom Lights lit IRPls < 20 steps
Reactor trip and bypass breakers Verifies turbine trip based on stop valve Verifies Power to 480V busses:

5A, 2A and 3A will be energized by offsite power ATC Checks if SI is required: A PORV has failed open and cannot be isolated due to 6A losing power

ATC should recognize need for SI and manually initiate SI CRS Announce entry into E-O and re-perform first 4 steps. Note: Actions will be continued on Event 6 D-2 2010 IP3 NRC Exam Scenario Page gof 13 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Page 1 of 1 Event
Description:
31 and 32 Safety Injection Pumps will not auto-start. Time Position Applicant's Actions or Behavior CRS/ATC May observe that are no running HHSI pumps and start 31 and 32 SI Pumps at this time. ATC Place 32 AFW pump in service to 33 and 34 SGs since 33 AFW does not have power. BOP or ATC Crttical Taelc1: Start 31 EX' 32 PumpS (bDtff tI!IOUld be ataitad priOr .$teP.2 Of Ro-1 .Qr 8 of e-o. BOP CRS/ATC ATC Initiate procedure RO-1, BOP Actions during EOPs:
Check SI equipment Status (may start SI pumps per this step)

Place switches for Fan Cooler Unit Dampers in SI position

Place SW Valves 1104/1105 in open

Place CCR AC switch in incident postion

Reset SI (may be performed in E-1)

Reset Phase A (will initiate event 7) (may be performed in E-1) Check:

MBFP

MFRVs

SG Blowdown Valves

SI Flow (will start SI pumps if not already done)

Containment Spray not required

RCP seal cooling

Start a charging pump

RCS Temperature
.; Crlticaf Task 2:. Note: At about this time, it is expected that the BOP will have reset Phase A valves and caused initiation of area wide blackout. This will lead to power only being available to Bus 5A from 33 EDG. Continued actions will be on Event 7 D-2 2010 IP3 NRC Exam Scenario 1 Page 100f 13 Appendix D Required Operator Actions Form ES-D-2 Op-Test 1\10.: 1 Scenario No.: 1 Event No.: 7 Page 1 of 1 Event
Description:
Station Blackout when Containment Phase A is reset Time Position CREW CRS BOP BOP ATC/BOP ATC/BOP ATC/BOP ATC CRS/ATC Lead Evaluator Applicant's Actions or Behavior Diagnose Loss of Offsite Power Enters LOOP-1 Loss of Offsite Power after SI Reset :'i:;" Critical Task 3: . .....Starts 34 SWP before 33 EDG trJPa due fD .......Places all CCW Pumps in trip pullout Starts 31 SI Pump (failure to do this constitutes failure of Critical Task) Starts 31 and 33 Fan Cooler Units Establishes AFW flow to 31 and 32 SG from 32 AFW pump Start 31 Charging Pump Back in E-O determine need to transition to E-1 for stuck open PORV Terminate scenario when transition to E-1 is announced 2010 IP3 NRC Exam Scenario 1 Page 110f 13 Appendix 0 Required Operator Actions Form ES-O-2 Emergency Classification ALERT: Per EAL 3.1.2 Primary system leakage exceeding capacity (75 gpm) of a single charging pump. 2010 IP3 NRC Exam Scenario 1 Page 120f 13 Turnover % RCS Rod PZR Press PZR Level RCS Total RCS Unidentified Condenser Air RCS Gas Risk Plant Equipment Status: 31 EDG is OOS for oil system modification. Instructions: Return unit to 100% at 10% per hour. Today/Now Power Ops 46% Equilibrium 1222 ppm CB D 173 steps Channel 1 Channel 2 0.1 gpm 0.01 gpm 6 SCFM 9.59E-3 I-lCi/cc Yellow 2010 IP3 NRC Exam Scenario 1 Page 130f 13 Appendix D Scenario Outline Form ES-D-1 Facility: IPEC Unit 3 Scenario No.: 2 Op-Test No.: 1 Examiners: Operators: Initial Conditions: Plant is at 5%. 31 Charging Pump is OOS for maintenance. Turnover: Come up to 10% power, then warm up the MTG and place it in service. 31 Charging Pump is OOS and not expected back on this shift. Event No. Malf. No. Event Type* Event Description 1 N/A R(ATC) N(CRS) N(BOP) Perform power ascension . 2 040A I(ALL) TS(CRS) 32 SG Pressure Channel Failure causing ADV to open. 3 CCWOO 1NB C(CRS) C(BOP) TS(CRS) 31 CCW Pump trips and 32 CCW fails to auto-start. 4 CCWOO 5A TS(CRS) CCW leak at 31 CCW Pump. Can be isolated 5 MSS009 A C(CRS) C(ATC) Main Steam header break with no MSIVs auto-closing and 1 MSIV failing open. 6 RPS002 NB M(ALL) Failure of the Reactor to trip both Auto and Manual. Team will emergency borate and manually insert control rods. 7 CNM001 12 C(BOP) Containment Sump Pump Isolation Valves fail to close requiring manual action. * (N)ormal, (R)eactivity , (I)nstrument , (C)omponent , (M)ajor 2010 IP3 NRC Exam Scenario 2 Page 10f 16 Session Outline: The evaluation beg i ns with the plant at 5% power ready to raise power and place the MTG in service. The following equipment is out of service: 31 Charging pump for PM. The team has been instructed to raise power to 10% and begin warming up the MTG to bring the unit on line. When sufficient power ascension has occurred , a failure of the 32 SG Pressure C channel 429C) will occur. Th i s will cause the Atmospheric Dump Valve for that SG to go full open. The ATC will place the valve in manual and closed. The team will enter AOP-INST-1 and trip bistables to satisfy Tech Specs. When PT-429C bistables are tripped , 31 CCW pump will trip and 32 w i ll fa i l to auto-start. Manual start of 32 CCW pump will work. After flow has been re-established a leak in CCW will occur at 31 CCW Pump. The team will take actions in accordance with AOP-CCW-1, Loss of Component Cooling. Prior to completion of the Subsequent Actions of AOP-CCW-1, a steam break will occur in the Turbine Build i ng. The team will attempt to manually trip the plant , close MSIVs, and perform actions of E-O , Reactor Trip or Safety Injection. The reactor will not trip from the Control Room and the team will respond per FR-S.1 , Response to Nuclear Power Generation I ATWS and will SID the reactor by manually inserting control rods and initiating emergency boration . The reactor trip breakers will be locally opened when emergency boration is intitiated. The team will complete FR-S.1 and transition to E-O , Reactor Trip or Safety Injection. Following SI actuation, the containment isolation valves for the containment sump fail to auto-close requiring manual action. The MSIVs will fail to auto close. All but 34 MSIV will be able to be closed in manual from the control room . The team will respond to the faulted SG per E-2, Faulted Steam Generator Isolation. If 34 SG is isolated in E-O , the scenario may be terminated when the transition to E-2 is announced. Otherwise terminate the scenario when E-2 is completed. Procedure flow path: POP-1.3 , AOP-INST-1 , AOP-CCW-1, AOP-UC-1, E-O, FR-S.1, E-O, E-2 Critical Task: CT 1: Insert negative reactivity when reactor fails to trip. CT 2: Isolated faulted SG. 2010 IP3 NRC Exam Scenario 2 Page 20f 16 Setup/Event Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Reset Simulator to 5% power IC (IC-50) SES Setup Schedule File Load setup Schedule file (U3 2010 Scenario 2) Transfer Actions to the Director Verify malfunctions I overrides entered Holds off 31 Charging pump Inserts failure of 1723/1728 to close (simulated) and events to remove failures when switches placed in closed. Loads Rx trip breakers failure to auto-open Loads Rx trip breakers failure to manually open (from CCR) Loads 32 SG Press Channel C Failure on Event 1 Loads CCW pump failure on Event 2 Loads CCW leak on Event 3 Loads Main Steam header break on Event 4 Loads failure of all MSIVs to auto close Loads failure of 34 MSIV to close in auto or manual Loads autostart failure of 32 CCW Pump Floor Setup Perform setup checklist Distribute turnover sheets Place cIs in TPO and hang Danger tag for: 31 Charging pump Place Protected Equipment tags for: 32 & 33 Charging pumps Update the protected equipment PC display Event 1 Power Ascension Event 2 Actuate Event 2 At lead evaluator direction 32 SG Pressure Channel C will fail high wlo ramp or delay MAL SGN002F to 1400 Role Play If NPO sent to investigate Nothing unusual at transmitter. Role Play If I&C ask to investigate. A troubleshooting package is being developed. Event 3 Actuate Event 3 At lead evaluator direction 31 CCW Pump trips and 32 fails to autostart. MAL-CCW001 B to failure to autostart at setup MAL-CCW001A to trip 2010 IP3 NRC Exam Scenario 2 Page 30f 16 Setup/Event Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play If N PO sent to investigate Indications are that 31 CCW Pump breaker tripped on overcurrent. Motor is hot and smells like winding damage may have occurred. Event 4 Actuate Event 4 At lead evaluator direction CCW Leak at 31 HX (will be reported as from 31 CCW seal) MAL-CCW005A to 500 with 120s ramp Role Play If NPO sent to investigate After NPO dispatched to locate leak, wait 2 minutes then report a lot of water is flowing out of 31 CCW pump seals. If the team directs the NPO to isolate the leak then, isolate by deleting CCWOO5A. Note: The CCW Surge tanks may empty if the leak is not isolated. The team will then trip the operating CCW pumps and attempt to trip the reactor. Event 2 (steam line break) should be activated prior to the reactor trip. Role Play If NPO dispatched to makeup to CCW: LOA RMW012, 1 LOA RMW013, 1 OPEN CCW makeup valves: PW-831A PW-831 B Role Play If NPO dispatched to split headers: LOA CCWOO7 LOA CCWOO8 LOA CCW035 LOA CCW036 LOA CCW015 LOA CCW016 Operate valves as requested: NOTE: 832A I 764A not modeled 766A 766B 766C 7660 759C 7590 EventS Activate Event 5 At lead evaluator direction Inserts Steam Break in Turbine Building on East Header at 100,000 Ib/hr ramped over 300 seconds. MAL-MSS009A to 100000 with 300s ramp 2010 IP3 NRC Exam Scenario 2 Page 40f 16 Setup/Event Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES NOTE: MAL MSSOO9A As directed by lead evaluator If the Team delays, increase the size of the steam break until the Team Trips the Rx. Role Play After the Team diagnoses the steam break Call as the NPO to the CCR and report there is a lot of steam in the Turbine Building and appears to be from the 33' elevation. Role Play If asked to locally close 34 MSIVs in the ABFP building NPO is unable to close 34 MSIVs. It appears to stuck open. Event 6 ATWS Entered in Setup Rx trip breakers fail to open from the CCR. They will open when tripped open locally by the NPO Role Play When NPO sent to locally open Rx Trip Breakers Delete reactor trip breaker malfunctions Wait until Emergency Boration is commenced before locally opening reactor trip breakers MAL-RPSOO2A RTBs fail to open (auto) MAL-RPSOO2B RTBs fail to open (manual) Role Play When NPO dispatched to isolate seal injection 241A LOA-CVCOO7 241B LOA-CVCOO8 241C LOA-CVCOO9 2410 LOA-CVC010 Event 7 Entered in Setup Failure of 31 FCU to autostart. 2010 IP3 NRC Exam Scenario 2 Page Sof 16 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: -.L Event No.: _1_ Page _1_of -.1 Event
Description:
Perform power ascension. Time Position Applicant's Actions or Behavior Note: Team will have been about power ascension in a briefing room prior to taking the watch. A reactivity plan will have been developed before the team comes to the simulator. BOP Controls SG level in manual using Low Flow Bypass Valves ATC Energize all PZR backup heaters ATC If dilution is performed per reactivity plan:
Set primary water integrator for desired total dilution.

Place Makeup Mode Control Selector Switch in Dilute

Place the Makeup Control Switch in Start and back to Auto

Monitor Dilution If rod withdrawal is performed:

Place Rod Control Mode Selector Switch in Manual

Withdraw Control Rods BOP Peer check dilution or rod withdrawal CRS Supervise reactivity additions Lead Evaluator When sufficient load ascension has been observed notify booth to insert Event 2. 2010 IP3 NRC Exam Scenario 2 Page Gof 1G Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: L Page _1_of .1 Event Description
32 SG Pressure Channel Failure causing ADV to open . Time Position Applicant's Actions or Behavior ATC/BOP Diagnose PT-429C failure:
32 ADV Open

32 SG Press C Channel Meter high ATC Places 32 ADV controller in manual and closes valve CRS Directs team to perform immediate operator actions of AOP-INST-1 , Instrument or Controller Failure ATC Checks for instrument failures on flight panel instruments , determines only PT-429C has failed. CRS Enters AOP-INST-1 and re-checks for failed instruments. Verifies that 32 ADV is closed in manual. CRS Goes to AOP section for SG Press failure CRS Refers to T.S. 6 hour AOT to trip bistables. BOP Trips the following bistables in rack B-2 : Loop 2C, Low Press Loop 2C, P2 < P3 A Loop 3C, P3 < P2 -A Lead Evaluator When bistables are tripped instruct booth to insert Event 3. 2010 IP3 NRC Exam Scenario 2 Page 70f 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: -.L Event No.: Page _1_of -.1 Event
Description:
31 CCW Pump trips and 32 CCW fails to auto-start. Time Position Applicant's Actions or Behavior BOP Diagnoses 31 CCW Pump Trip BOP Starts 32 CCW Pump (may be directed by CRS) CRS May enter AOP-CCW-1 for loss of CCW , but this is not necessary CRS Evaluates T.S. for failed CCW Pump 30 dai' AOT Lead Evaluator When Pump has been started and CRS evaluates T.S. instruct booth to insert Event 4. 2010 IP3 NRC Exam Scenario 2 Page Sof 16 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: -L Event No.: Page_1_of Event
Description:
Leak at 31 CCW Pump Time Position Applicant's Actions or Behavior BOP Diagnoses a loss of CCW surge tank level (this will be masked by swapping pumps for previous eventL CRS Enters AOP-CCW-1, Loss of CCW BOP Calls NPO to makeuQ.to surge tanks and investigate loss of CCW CRS May initiate splitting of CCW headers CRS Will direct isolation of leak when report of location is received BOP Should place 31 CCW Pump in trip pull out and will have leak isolated CRS Assess that leak has been isolated and review T.S. 72 hour AOT due to loop inoperability Lead Evaluator When leak has been isolated and CRS has had time to assess situation , instruct booth to insert Event 5 2010 IP3 NRC Exam Scenario 2 Page 90f 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.:.L Event No.: ....§.... Page _1_of J. Event Description
Main Steam header break with no MSIVs auto-closing and 1 MSIV failing open . Position Applicant's Actions or Behavior Time CREW Diagnose steam break downstream of MSIVs:
Noise

Steam flow increase all channels

T avg lowering

Turbine power lowering

Reactor power May enter AOP-UC-1 or may just give order to:

Trip the reactor

Then close Will attempt to trip reactor At this point actions will be tracked on D-2 for Events 6 and 2010 IP3 NRC Exam Scenario 2 Page 100f 16 Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: -.L Event No.: Page _1_of 2 Event
Description:
Failure of the Reactor to trip both Auto and Manual. Position Time CRS ATC BOP BOP BOP BOP/ATC Applicant's Actions or Behavior Instruct team to perform immediate operator actions of FR-S1 Will insert control rods Will trip the turbine Direct NPO to locally trip the reactor Will establish greater than 686 gpm AFW flow Critical Task 1: EstablIsh EtntirgEmCY. Boration as follows: (prior to step f . S1): Check charging pump running Open MOV-333 .:: Cla$e. HCV-1M and 105 Sfait bolt BATPa mfast .....
, Note: When emergency boration has been initiated, the NPO will trip the reactor local/y. It will be acceptable (and preferred) at any pOint to close the MSIVs, but this action may not be done until FR-S1 is exited. Also, AFW flow may be reduced at this point. ATC/BOP Verify VC ventilation isolation CRS Check SI status. SI will have actuated due to steam leak. BOP Performs steps 35 42 of E-O (SI verification)
ATC Checks reactor is subcritical ATC Secures Emergency Boration (charging pump may be secured due to SI) Closes MOV-333 Place BATPs in slow speed Place HCV-104/105 to 25% ATC Checks RCP seal cooling. CCW will be available for seal cooling. 2010 IP3 NRC Exam Scenario 2 Page 110f 16 Appendix D Required Operator Actions Form ES-D-2 ATC Aligns charging pump suction to RWST and starts a charging pump CRS Exits FR-S1 Note: Actions will be continued on Event 7 D-2. 2010 IP3 NRC Exam Scenario 2 Page 120f 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: 2 Event No. : Page_1_of 2 Event Description
Containment Isolation Valves 1723/1728 for Containment Sump do not auto-close. Position A licant's Actions or Behavior Time While performing SI verification steps will note that Containment Isolation Valves 1723/1728 did not close which allows a path from the Containment Sump to the Aux Building. The manual switches (2 on SNF) will close the valves. CRS/ATC BOP Return to If not alread done, close MSIVs -34 will not Perform E-O actions:
Verify reactor trip

Verify turbine trip

Verify power to 480V busses

Ver i fy SI actuated CRS/ATC Verify AFW Flow:

At this point, AFW flow will be reduced if not already done

This also ma be where team addresses faulted SG Note: It is critical that the fol/owing task be performed prior to exiting E-2, however it is acceptable and preferred that this action be performed sooner. BOP/ATC

eloise other three MSIVa

secure AFW now to 34 SG

ISOlate the upstream traps for 34 SG 2010 IP3 NRC Exam Scenario 2 Page 130f 16 Appendix 0 Required Operator Actions Form ES-D-2 BOP Performs RO-1 procedure for SI verification and reset (these actions may have been done while still in FR-S1):

Verif i es SI equipment

Checks Containment Isolations. Will note that Isolation Valves for the Containment Sump do not indicate closed (Valves 1723/1728). Will take switches (2 on SNF) to closed.

Resets SI

Resets Phase A CRS/ATC Continue with E-O:

Verifies feed water isolation

Verifies blowdown isolation

Verifies SI flow

Verifies Containment Spray not required

Verifies RCP seal cooling

Checks RCS Temperature

Checks for RCP trip criteria

Checks PORVs and Safeties

Checks if SGs are faulted CRS Announces transition to E-2, Faulted SG Isolation Lead Evaluator If 34 SG has been isolated, terminate scenario. If isolation has not yet been accomplished, allow isolation in E-2 (the only action) and terminate when transition to E-1 is announced.
2010 IP3 NRC Exam Scenario 2 Page 140f 16 Emergency Classification SAE: Per EAL 1.1.2 Red Path in F-O.1 Subcriticality and all manual attempts at tripping the reactor from the Control Room have failed to reduce power range to <5%. 2010 IP3 NRC Exam Scenario 2 Page 150f 16 Turnover DatelTime: Today/Now Condition: Power Ops % Power: 5% Xenon: Equilibrium RCS Boron: 1040 ppm Rod Position CB 0 117 PZR Press Control: Channel 1 PZR Level Control: Channel 2 RCS Total Leakage: 0.1 gpm RCS Unidentified Leakage: 0.01 gpm Condenser Air leakage 6 SCFM RCS Gas activity 9.59E-3 Risk Assessment: Green Plant Equipment Status: 31 Charging Pump is out of service for a major PM. Instructions: Raise power to 10% in preparation for starting up MTG and bringing the unit online. POP-1.3, Plant Startup from Zero to 45% Power, is complete up to Step 4.31 . Prerequisites for turbine startup are being performed by other operators. 2010 IP3 NRC Exam Scenario 2 Page 160f 16 Appendix D Scenario Outline Form ES-D-1 Facility: IPEC Unit 3 Scenario No.: 3 Op-Test No.: ---.1 Examiners: Operators: Initial Conditions: Plant is at 100%. 31 AFW Pump is OOS due to high vibrations. PORV 455C is inoperable due to blowing fuses. Turnover: Maintain 100% power conditions. 31 AFW Pump is OOS due to high vibrations. PORV 455C is inoperable due to blowing fuses. Event Malf. No. Event Event No. Type* Description 1 I(ALL) VCT level instrument fails low. CVC049 2 C(ALL) 33 Charging Pump Trip. CVC005C TS(CRS) 3 C(CRS) 900 gpd SGTL on 33 SG. SGN005C C(BOP) TS(CRS) 4 R(ATC) Tech Spec required shutdown. N(CRS) N(BOP) 5 M(ALL) SGTL becomes SGTR. PORV and Instrument Air to VC Valve SGN005C failures will lead to loss of pressure control. PRS003D AIR002C 6 C(CRS) 33 AFW Pump fails to auto-start. CFW001C C(ATC) 7 C(BOP) 31 Safety Injection Pump fails to auto-start. SIS004A . (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2010 IP3 NRC Exam Scenario 3 Page 10f 16 SESSION OUTLINE: The evaluation begins with the plant at 100% power steady state operation. The following equipment is out of service: # 31 ABFP was declared inoperable 3 hours ago due to high vibrations during its PT (TS 3.7.5 -72 hr AOT) PORV 455C was declared inoperable 1 hour ago due to blowing its control power fuses. TIS is in progress. Per TS 3.4.11, the block valve has been closed with power removed and a 7 day AOT entered. After taking the watch, the VCT Level instrument fails low. The team will respond per AOP-CVCS-1 , "Chemical and Volume Control Malfunction". When the VCT level failure has been addressed , the running Charging Pump will trip. The team will re-enter and take actions per AOP-CVCS-1, " Chemical and Volume Control Malfunction". After performing actions for the Charging pump trip, a 900 gpd SG tube leak on 33 SG will occur. The team should take actions per AOP-SG-1, "Steam Generator Tube Leak". This will include begin a plant shutdown. When the team has sufficiently progressed through the shutdown, the SGTL will become a SGTR. The team w i ll trip the Reactor and initiate SI. 33 AFW pump will fail to start requiring manual action to be taken in E-O. 31 SI pump will have to be manually started. The team will transition to and take actions per E-3, "Steam Generator Tube Rupture". Normal and auxiliary spray will not be available due to a failure of PCV-1228, IA to VC to open. This, along with the PORV failure to open, will require the team to transition to ECA-3.3, 'SGTR Response without Pressurizer Pressure Control" until SI pumps are secured. Procedure flow path: AOP-CVCS-1 J AOP-SG-1, E-O, E-3, ECA-3.3 Critical Tasks: CT 1: Establish 365 gpm AFW flow. CT 2: Isolate 33 SG (ruptured SG). CT 3: Establish and maintain cooldown in E-3. 2010 IP3 NRC Exam Scenario Page 20f 16 Simulator Setup and Instructor Directions Setup/Event EXPECTED RESPONSEIINSTRUCTOR CUES Ie Reset INSTRUCTOR ACTIONS Reset Simulator for proper IC Ie 11 SES Setup Deenergizes 31 ABFP Schedule File Deenergize PCV-455C & Block Valve 535 entered VerifY malfunctions / overrides Loads 33 ABFP trip malfunction Loads 33 Charging pump trip Loads SGTL 900 gpd Loads SGTR 400gpm Loads PCV-456 failure Loads auto-start failure of31 S[ pump Loads failure ofPCV-1228 Floor Setup Ensure 33 Charging pump is in service Place cis in TPO and hang Danger tag for: Perfonn setup checklist Distribute turnover sheets 31 ABFP Place PORV 455C in Closed Ensure Rx Vessel Head valve fuses are available in Place block valve 535 to TPO drawer Remove PCV -455C fuses in rear of Flight Panel Place Protected Equipment tags for: 32 & 33 ABFPs Update the protected equipment PC display Event #1 Click the Event 1 button VCT Level Instrument Fails Low i /nsert maljimction XMT-I LT-112fails At lead evaluator [ CVC049 low direction Role Play If I&C or NPO called to I&C will infonn team that a troubleshooting investigate package will be developed NPO will find no issues with the running charging pump Event #2 Click the Event 2 button 33 Charging pump trip I Insert malfunction MAL-l CHARGING At lead evaluator CVC005C on event I PUMP 33 TRIP direction Role Play IfNPO sent to investigate NPO reports no obvious problems 2010 IP3 NRC Exam Scenario 3 Page 30f 16 --Event #3 Click the Event 3 button SOTL on 33 S/O 900 gpd no ramp STEAM! /nsert malfunction MAL-At lead evaluator SGN005C to 0.005 on GENERATOR 33 direction TUBE LEAK j event 3 Event #5 SOTR on 33 S/O 400 gpm ramped in 10 min.Click the Event 5 button STEAM I Insert malfunction MAL-At lead evaluator SGN005C to 20.00 on GENERATOR 33 direction TUBE LEAK I event 5 Role Play Perform various LOA's per NPO local task list Role Play At CCR request If asked to investigate 33 No obvious signs of pump problem but ABFP trip breaker shows over current trip 2010 IP3 NRC Exam Scenario 3 Page 40f 16 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: Page _1_of J. Event
Description:
VCT level instrument fails low. Time Position Applicant's Actions or Behavior CREW Diagnoses failure of VCT Level instrument: Auto-makeup VCT Low Level Alarm Charging Pump Suction re-aligns to RWST (LCV-112B opens and LCV-112C closes) CRS Enters AOP-CVCS-1, CVCS Malfunction BOP Opens LCV-112C BOP When LCV-112C indicates open, closes LCV-112B these actions re-align charging pump suction back to VCT ATC Places Makeup Control Switch to Stop ATC Place Makeup Mode Selector Switch to Manual CRS Has procedure step to reduce load as necessary in case temperature changed due to makeup. This should not be necessary. CREW Ensure VCT Pressure is 2-10 psig above pre-event value and have NPO monitor running charging pump. Lead Evaluator At this point there are no more actions until the instrument is repaired. Instruct booth to insert Event 2. 2010 IP3 NRC Exam Scenario Page Sot 16 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: ..J-.-Event No.: -L Page _1_of -1 Event Description
33 Charging Pump Trip. Time Position Applicant's Actions or Behavior CREW Diagnose 33 Charging Pump Trip:
RCP Thermal Barrier Low DP Alarm

480V Motor Trip Alarm

Amber light on 33 Charging Pump Switch CRS Enters AOP-CVCS-1 BOP Close LCV-459 and 460 ATC Starts 31 or 32 Charging Pump ATC Adjusts charging pump speed in manual to maintain 6-12 gpm seal injection flow BOP Closes AOV-200B BOP Place PCV-135 in manual and 50% BOP Place TCV-130 in manual and 50% BOP Opens LCV-459 and 460 BOP Opens AOV-200B ATC Increases charging pump speed BOP Adjusts PCV-135 and TCV-130 as necessary and may return valves to auto at this time. Lead Evaluator The charging pump will probably not be returned to auto at this time, so there are no more actions. The CRS should evaluate the TRM for the failed charging pump , but this may have to be a followup question. TRO 3.1.C is affected. Instruct the booth to insert Event 3. 2010 IP3 NRC Exam Scenario 3 Page 60f 16 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: Event No.: Page _1_of -.1 Event Description
900 gpd SGTL on 33 SG. Time Position Applicant's Actions or Behavior CREW Diagnoses SGTL:
Increased trend on R-15 Steam Jet Air Ejector

Eventual Alert on R-15

SliQht increase in 33 SG steam line monitor CRS Enters AOP-SG-1, Steam Generator Tube Leak ATC Verifies that PZR Level is not affected by leakage CREW Requests SG samples and field surveys to quantify leakage and identify leaking SG. Note: Time compression will be used for chemistry samples. . BOP May perform Secondary Plant Isolation per Attachment 3 of 3-AOP-SG-1 in parallel with SID:

Bypass and Isolate Condensate Polisher o Open CD-AOV-521 and 519 o Clsoe CD-AOV-518 and 520

Close LCV-1129

Adjust 33 SG ADV setting to 74% 1040psig

Close 33 SG Blowdown Isolation Valves

Close MS-42 Steam supply to 32 AFW Pump from 33 SG

Direct isolation of upstream traps for 33 SG CRS Will determine that SID is required to be: * < 50% in 1 hour

Mode 3 within and additional 2 hours Note: The plant is in a T.S. required shutdown per LCO 3.4.13 Condition A, but this may have to discussed as a followup with CRS. 2010 IP3 NRC Exam Scenario 3 Page 70f 16 Appendix 0 Required Operator Actions Form ES-D-2 Actions will continue on Event 4 2010 IP3 NRC Exam Scenario 3 Page 80f Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: Page _1_of -.1 Event Description
Tech Spec Shutdown ATC CRS CREW ATC BOP BOP ATC Lead Evaluator Applicant's Actions or Behavior Develops reactivity plan using reactivity summary sheet Uses POP-2.1 attachment for load reduction Note: Team may use ONOP-TG-3, Rapid Shutdown If requested , notifications w i ll be made for CRS by pe r sonnel outside the control room. Hold reactivity briefing.
Performs Boration for load reduction: Sets boric acid integrator for required volume Energizes all PZR backup heaters Takes Makeup Mode Selector to BORATE Starts boration by taking Makeup Control Switch to START and back to NORM Borates 20 gallons at 10 gpm and then adjusts to flowrate determined in shutdown reactivity plan. Peer checks boration Begins load reduction using the MTG Governor Peer Checks MTG Governor manipulations When sufficient actions for shutdown are observed instruct booth to insert Event 5 2010 IP3 NRC Exam Scenario Page 90f 16 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: Event No.: Page _1_of 2. Event
Description:
SGTL becomes SGTR. PORV and Instrument Air to VC Valve failures will lead to loss of pressure control. Time Position Applicant's Actions or Behavior CREW Diagnoses that SGTL has become SGTR:
Lowering PZR Level

Lowering PZR Pressure and possible Low Pressure Alarm

R-15 in Alarm ATC May start a second charging pump BOP May reduce letdown to 45 Jlpm CRS Instruct Crew to:

Trip Reactor

Initiate SI ATC Trips reactor , announces reactor tripped BOP Manually actuates SI CRS Instructs team to perform immediate operator actions of E-O ATC Verifies reactor trip:

Trip/bypass breakers open

Flux decreasing

Rod bottom lights lit

I RPls < 20 steps ATC Verifies turbine trip:

May note that stop valves were previously closed

May use first stage pressure to confirm turbine trip BOP Verifies power to 480V busses:

All powered from offsite power 2010 IP3 NRC Exam Scenario 3 Page 100f 16 Appendix 0 Required Operator Actions Form ES-O-2 ATC Verify 51:

51 will be actuated

51 buttons will be pressed CR5 Enters E-O and re-performs first four steps Note: Actions will be continued on Event 6fl D-2 2010 IP3 NRC Exam Scenario 3 Page 110f 16 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No. : Page_1_of
Event
Description:
33 AFW Pump and 31 SI Pump fail to auto-start Position Applicant's Actions or Behavior Time ATC/BOP CrItIcal Task 1: EstabUlttat least 385 gpm AFWftow Yllllbe es1ab1lshed): Start 33 AfW Pump whi£h.wiU feed 33' SG8
Increaae" on 32 AFW Pump

aiId:32 SGa ftdm 32/i#W
.', . Will perform RO-1 , BOP Operator Actions during EOPs: BOP Verify SI Pumps Running
31 SI Pump will be manually started. Verify other SI equipment Align FCU damper switches to SI position Align VC SW Valve (1104/1105) switches to on

Place CCR HVAC switch to SI position Reset SI Rest Phase A Attempt to open PCV-1228 to establish instrument air to the VC, but valve will not open . Resets MCCs

Initiates local action to align SW CRS/ATC Performs E-O actions: Verifies FW isolation Verifies SI flow

Verifies Containment Spray not required Verifies RCP seal cooling and starts a charging pump Verifies RCS Temperature

Checks if RCP trip criteria are met. 2010 IP3 NRC Exam Scenario Page 120f 16 Appendix Required Operator Actions Form ES-D-2 CRS/ATC CRS/ATC CRS/ATC CRS/ATC CRS/ATC Perform E-O diagnostic steps and determine that transition to E-3, Steam Generator Tube Ru ture is re uired. Check if RCP tri criteria are met .Cr1tk:ar Task 2: I....33 SG-nota these actIon8 tNiy not all be perf'ormed at the ana WHen 33 SG level reach_.: Secure feeding 33 SG by AFW FRY for 33 SG seta3 SG ADV to Isolate Iteam Craps upstream of 33 Close 33 Verify Btowdown Valves _closed far 33 SG cl1bl Task 3: Usa cQndal1l8l' aIaaIrI duriIps to lnitlata cooldoWr'l (max 0 IbmIhr) SlopCooldownwhenCmareat
.. continue in B-3 while wafting to reach CRS/ATC Ensure at least one PORV block valve 0 en CREW CREW CREW Attempt to establish IA to VC if not already done per RO-1. PCV -1228 will noto en CRS/ATC lace in auto CRS/ATC Check RCP seal coolin CRS/ATC o en LCV-112B and close LCV-112C CRS/ATC Check subcoolin >60F CRS/ATC Determine that normal s ra is not available for de ressurization 2010 IP3 NRC Exam Scenario Page 130f 16 Appendix 0 Required Operator Actions Form ES-O-2 CRS/ATC Attempt to depressurize using PORV 456 CRS Transition to ECA-3.3 CRS/ATC Check 33 SG Level < 75% (should be < 75% at this point):
Procedure will address attempting to establish spray , aux spray or PORV CRS/ATC Check PZR Level is >14% CRS/ATC Check subcooling
>40F CRS/ATC Check >365 gpm AFW flow available for heat sink CRS/ATC Check RVLlS >72% ATC/BOP Secures SI and places in auto Lead Evaluator Terminate Scenario 2010 IP3 NRC Exam Scenario 3 Page 140f 16 Emergency Classification ALERT: Per EAL 3.1.2 Primary system leakage exceeding capacity (75 gpm) of a single charging pump. 2010 IP3 NRC Exam Scenario 3 Page 150f 16 Turnover DatelTime: Condition: Power % Power: Xenon: RCS Boron: 1040 PZR Press Control: Channel PZR Level Control: Channel RCS Total Leakage: 0'.1 RCS Unidentified Leakage: 0.01 Condenser Air leakage 6 RCS Gas activity 1.78E-2 Risk Assessment: Plant Equipment Status: # 31 ABFP was declared inoperable 3 hours ago due to high vibrations during its PT (TS 3.7.5 -72 hr AOT). Maintenance has de-coupled the pump and motor , and it is expected to returned for re-test next shift. PORV 455C was declared inoperable 1 hour ago due to blowing its control power fuses. TIS is in progress. Per TS 3.4.11 , the block valve has been closed with power removed and a 7 day AOT entered. Instructions: Maintain 100% power. 2010 IP3 NRC Exam Scenario Page 160f 16}}

v t e Letter Sequence Acceptance Review
TAC:U01789, (Open)
Initiation Acceptance Administration Questions Answers Results Approval... Other: ML103090017, ML103090020, ML103090036, ML103410223
MONTHYEAR2010-07-20 [Table View]

ML103090054

Text

1.0 RECORD

7.0 CALCULATE

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