ML103090054
| ML103090054 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/17/2010 |
| From: | David Silk NRC Region 1 |
| To: | Entergy Nuclear Operations |
| Hansell S | |
| Shared Package | |
| ML100980645 | List: |
| References | |
| TAC U01789 | |
| Download: ML103090054 (243) | |
Text
{{#Wiki_filter:Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 1 of 15 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: 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 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: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 20 Min Actual Time: _ __
References:
2-POP-2.1 Operations at Greater than 45% Power File: 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 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 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> 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 minutes Task Number: 2000770101 2-POP-2 .1 Administrative
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 Candidate will be
- 2. Obtain current copy of 3-POP-2 .1 given the procedure Attachment 1 step 1
.3. Enters 324 (+/- 1) MW Enter Total MW change Attachment 1 step 1 Enters approx 108 Enter Rate of Shutdown MW/hr (+/- 1)
Attachment 1 step 1
- 5. Enters Current Time Enter Start Time Attachment 1 step 1 Enters Start Time + 3 6.
Enter End Time hours. Attachment 1 step 2
.7. Enter 400 (+/- 3) pcm Determine Power Defect from Graph RV-1 Attachment 1 step 3
- 8. Enter 18 (+/- 0.5) pcm Determine Xenon Worth from Graph 3D Attachment 1 step 4
- 9. Enter 382 (+/- 3.5) pcm Calculate total of steps 2 & 3 Enter 190 steps (No Attachment 1 step 5
- 10. tolerance. From Enter Target Rod Position table)
Enter 76.96 pcm (No Attachment 1 step 5
.11. tolerance. From Enter Integral Rod Worth at 190 steps table)
Attachment 1 step 5
'12. Enter 230 Steps Enter Current Rod Position Attachment 1 step 5
- 13. Enter 0 pcm Enter Integral Rod Worth at 230 Steps File: 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 5 of 15 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Attachment 1 step 5 Enter 76.96 (note this 14. Calculate Reactivity due to rods is a negative number) 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 needed.
Step 6 +-2.03 pcm/gal JPM Complete. File: 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 6 of 15 OPERATION AT No: 3-POP-2.1 Rev: 53
- - GREATERTJtAN<l5"7'oPOWER Page 35 of 40 ATTACHMENT 5 POWER REDUCTION REACTIVITY WORKSHEET (Page 1 of 2)
- The preferred reactivity calculation for planned power reductions is the Beacon Summary provided by Reactor Engineering
- This worksheet serves 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 Cu nel'\1 Tt~ End Time C<<oen t I, ~ of 3 h4if"~ 2.0 DETERMINE Power Defect from 3-GRAPH-RV-1 OR the dally reactivity sheet (+) 4ro~ 3) pcm 3.0 DETERMINE Xenon worth as follows; 3.1 I.E Xenon equilibrium is established AND 3-GRAPH-RV-3D has current cycle data, THEN USE 3-GRAPH-RV-30. 3.2 I.E Xenon equilibrium is NOT established, OR 3-GRAPH-RV-3D does NOT have current cycle data, THEN REQUEST Xenon worth from Reactor Engineering (-) If>{! O.S ) pcm 4.0 CALCULATE the total of SJeps 2 and 3. ~ 3<fl 1',\ ~'8,\
""'00 +~6~ -}...!J1~,,--_ _ _ =(+) 3t.l.(~'3.s) pcm Step 2 Step 3 4ol'j It\" ~~5 . Oj II ANSWER KEY II File: 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 OPERATION AT No: 3-POP-2.l Rev: 53
- -UREA I ER I RARZl5'1o POWER Page 36 of 40 ATTACHMENT 5 POWER REDUCTION REACTIVITY WORKSHEET (Page 2 of 2) 5.0 DETERMINE Reactivity due to control rods using 3-GRAPH-RV-13
-AND 3-GRAPH-RV-7B.
Control Rod Position Integral Rod Worth Target Rod Position r~o Steps 1~.'U, pcm Current Rod Position J~ Steps - D pcm {-) 7f~qL pcm 6.0 CALCULATE the Reactivity needed from Boric Acid by summing Steps 4 and 5.
~?f.\ ~I.'SI/
~f~ + (-)1/, .1(,. =(+) '1>$".II'fe,.~m
'!I~-\ ~o,. 6'-!
S~p4 S~p5 7.0 CALCULATE the total amount of Boric Acid needed. Ilff. f (II/A)
~.~
' 6 0'/ pem / _---=J.;....o_.;...
~ _ _----'pcm/gal = I ~.l (,~) gal
-.oII"O'i
~ . 5"--
~ ISlA (, 0 )
Step 6 (from 3-GAAPH-AV-14. Reactivity Control Parameters. QB. Reactor Engineering) IIANSWERKEY II
..J File: 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 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)
~i=:-~~~~~~-~;:~[t(~~~~1 0.0
-200.0
-400.0 1600 ppm ----.- - i
-600.0 \~ppm ~~--=-~j
~,,~~
.~-I--I'-1--r 1200 ppm
---==i
--*-----i
-800.0 - - - -- ---l E "'~~-<-'~I-+' ' I_ 1000ppm==-~:::I
!-1000.0
--.. --=--.-------------~
~~¢~~~ .'. --~=~-:.. : ---=-~~
t-O W I ..J .-..ItQ -'200.0 a: W *1347 .6 pcm o~ *14000 . .1400.5 pcm Q. *1458.7 pcrn
*1523.5pcm
. 1595.9pcm
*1732.5 pcm
-1800.0 .. - -.-- -----.
- 1604.3pcm
__ ______ _ ..__ ... _.0 PIlm
. 16t!1.2 pcm
-2000.0 -..... - - - -- -. -. - --
r~ - .-- - --."..-.. . . -", -.. .-.. -.__.u--.. ... -----.
-2200.0 f~: ::~-~~' -' --: :--~-- ..~.~~~~~~= ::~"- ..
2400.0 r:*: -: :~ :. . . . . . . " .__ .. . '
*2299.8pcm
*2349.7 pcrn
*2401.9 pcm
-2600.0 1-"-- -'-' _____.___.____
o 10 20 30 40 SO 60 70 60 90 100 (! l ' . Writlen By~ _~~ '____ POWER LEVEL (%) BOL BORON =\800 ppm 10 1000 ppm Reviewed By~ MOL BORON = 800 ppm to 400 ppm ApproveO B . . EOl BORON = 200 ppm to 0 ppm Effective Date: .1 - 16 . .,)..~ [IANSWERKEY II File: 2000771601-1.doc Difficulty: 3 Time: 20 minutes Task Number: 2000770101 2-POP-2.1 Administrative
-ill Dl = Cfl CD
.. f L ' ~ .'
n ZN cO 38 0" --.I 0) ( ") C Re~ ... CD--.I . . CJ) 0) 3- GRAPH-RV-1 20 NO 0-"" TOTAL POWER DE ECT n> 0' (for use with 3-S0P*R . C-003) 0) 0:-" --.I 0 CYCLE 16 (Page 2 ~f 2) --.10 OC)
"'0 0
o BOL Res BORON CONCENTRATI:>N
"'0-. (ppm)
EOL :en> g: POWER("fo) 1000 1200 1400 1600 1800 400 _1iQ!l sao 0 100 200 ~ 0 0.0 0.0. 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0. ~ 10
*106.6
*207.3
*100.2
- 195.5
'95.0
- 185.7
*90.7
*177.7
*87.1
-170.9
'108.6
-214.2 -20 .2
*101.8
-200.9
-159.9
-Jl0.7
'157.0
*305.3
*154 . ~
-3002 n>
Q, 15 -302.9 *286.4 *272.7 -2612 -251 .S -317.1 - .6 -297,4 -453.6 -445.8 *438,4 C 20 *394.0 .J73.~ *356.2 -~1 . 7 -329.3 -417.6 .2 -391.8 ~9 . 6 *579.5 -569.9 -U 25 30
-481.4
*565.6
-457.2
*538.1
-436.8
-514.8
"'9.5
-494.9
-4~ .6
-477.6
-5162
~13 .0
..9t*5
-59 .1
-464.1
-574.6
*719.7
-1144.7
*707.4
-8302
*695.7
--a16.5 Q)~
CO _. r:-'o 35 *647.2 -616.6 -590.5 *568.1 48.6 -708.4 -68$.2 -ti63.6 -965.5 *948.9 *833.0 ('t) 0 "U~ 0(')'
"Uc ~~
Z
~o 45 50 5S 60
-726.5
-304.0
*880.1
-955.0
-10.289
-693.0
-767.7
-MO. 9
-912.9
-963.9
-664.3
-736.3
*807.0
*876.3
*94<4.5
-639.5
-709.1
*777.3 442
-909.9
-617.7
-685.1
-751.0
-815.6
*878.9
-802.5
-895.5
-987.7
*1079.2
*1170.0.
-775.9
-8sS.4
-gs.i.o
- 1~1 . 7
*1128.7
-75 1.1
-837.4
-922.6
- looM
-1090.1
*1082.8
-1197.3
'1309.6
-1420.3
-1529.9
-1()64.0
- 11762
-1286.3
-1394.6
*1501.7
-1~6 . 1
-11562
-1264 .0.
-1370.0.
. 1474.7 tO~
o~
-n>
....... 0)
VJ r.n 65 70
'110.2.2 -10.54.0. *10.11 .8
- 1174 .7 ~'!J *10.782
-974.5
-1036.1
-941.1
-1002.1
'1260.4
-1350.3
*1215.0
.1306.7
-11n.7
, '254 .5
*1638.8
*1747.3
*1807.9
-1713.7
*1578.5
-1681 .6 0'1(,,)
~
75 '1246.7
- 1 .0. *1143.7 -1100.8 *10822 *1439.8 .1385.9 -1335.7 -1855.8 -1819.3 *1784.4 80 *1316.1 - 1259.9 *1208 .5 -1162.6 -1121.3 -162Q.a *1470.6
- 1~16.3 -1964.4 -1924.9 -18872 85 ' 1388.9 -1327.2 -1272.4 -1223.5 -1179.4 -1617.7 -1554.9 -1496.2 -2073.2 -20'30.7 '1990.0.
- 1458.9 ' 1393.6 *1335.5 *2182.4 -2 136.7 -2093.0.
~
tn 90 95 100
-1 528.0. ~ -1397.6
- 1~95.9 523.5
- 1458.7
*1283.5
-1342.5
-1400.5
-1236.6
*1292.7
- 1~7 . 8
-1708.1
*1793.9
- 1881.2
-\6311.6
-1721.7
'1804.3
-1575.6
'1654.4
-1T32.5
-2292.0.
*2401.9
-2243.0
*~9 .7
-2196.a
*2299.8 "'0
~ 0)
~
~ BY:C _ . -£ . =
"C n>
tn Wnn.n Re.iewed By: _ _ _ _ _ __ ~
~
AppmYed By '.. . ..:... _ _ _ _ _ _ __ Eftecllve 0816:.. _ : r,(:-~...3.. __..._____ _ "'0
-i 0 b3' "'0 ~~ .
I _. N N
- lo ~
iii'
~ _.
3 iii :J Q".S 0:: (1) CD Cfl
Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 10 of 15 3*GRAPH*RV*3D Rev. 18 Xenon Reactivity Inserted for Various Shutdown Rates from 100% Power, Equilibrium Xenon, Cycle 15 EOL (25.445 MWDIMTU)
~
. -.-.j
~
I'
-. - - - - ._- -~ .. - .- - - Written by: ~ -."--'
f--- -- . - f - - - - - - - -.- 1-. Reviewed by: -=~
- - - - - - .. - - . - - ; - - -..-. _Approvedby: *~1r---J, EHective Date: 0 1 9~!
I- Reacto at Hot Full Power --r- ~ . '
- --Ir---+--- - - I - - . 1--'-- ' t-.----. ~____l
--+----.. .-.-'-_. - - - . t--.--- ..-
-+---+--...-... --- -I--.- ..... .- .- - f---...... ..- -
2 4 6 8 10 12 14 16 18 20 22 Hours After Start of Shutdown File: 2000771601-1.doc Difficulty: 3 Time: 20 minutes Task Number: 2000770101 2-POP-2.1 Administrative
-Ill CONTR~U:D Ill::': C/l CD f 7' . . (") ZN C 38 rr --I 0 3-GRAPH-RV-7 Rev.11 - S>> C') a AT POWER CONTROL BANK WORTH AS FUNCTION OF BANK POSITION C CD--I Q) CYCLE 16 (For Use wi h POP-2.1) S>> NO EQUIUBRIUM XENON C NDiTIONS (I) 0-' 0' 0:-' S>> --I a. --10 DC) o BANKPosmON Step. Wftbdr'8Wfl BOL 150 MWDIMTU BOUMOl 6000 MWDIMTU dl MOL 1 000 MWO/MTU MOUEOL 18000 MWO/MTU 25017 MWOfMTU EOl ""C o om.....,U.1 Integnl 0111....1101 In....' 'Dllhranllal Integ..1 om-t>ta, \nbIgraI 0IftwM1Ial Inlegnol ~ B4NKC BANKO Rod Worth Rod Wot1h Rod Worth (I) Rod Wot1h Rod WotIh Rod Wor1I1 RodWonh Rod Wortn Rod Wco1h Rod WortII
~
(pom/.top) (pcm) {pcmtl18p, (JII;l!I) (p<OnIslep) (pcm) (pemlstop) (pcmI.lop) (pcm) (pom'
~
230 230 0.00 0 .00 0.00
..~
\O1.43 0.00 0 .00 0.00 0.00 0.28 0 .00 :;0 no 227 0.62 3. It 0.28 0.32 1.58 0 .51 2.54 105 ~66 (I) 230 22. 1.24 6 .22 0.57 2.85 0.63 3.15 1.02 5 .06 181 9 .33 C.
230 220 2.07 10.37 0 .95 4.75 1.05 5.26 1.69 8.,6 2 .83 15.54 "'OC [f) 230 2 18 2.36 15.97 1.20 7.91 1.38 8.92 215 14.14 3A3 24.22 Q) C') 230 215 2.80 r:->o 24.36 158 12.S. 1.83 14.40 2.a. 22.66 4.~ 37.2.1 to "
~
CD -
"U::ii 230 212 3.24 32.76 1.95 17.37 2.29 19.89 3.53 31.\6 5.24 5024 o On' 230 210 3.53 38.36 2.20 20.52 2 .60 23.55 3.99 36.66 5.85 58.91 =:::s "Uc N-? tJ1 230 230 206 203 3 .56 3.58 52.62 63.31 2.47 2 .66 3066 38.25 3 .01 3.31 35.98 45.31 4.52 4.92 55.48 69.45 6 . 3.~
6.72 114.80 10422 0:;0
-(I)
~
230 200 3.80 74.00 w 2.66 45.8' 3 .62 54 :6<1 5.33 83.'2 7 .10 123.63 ........ S>> 230 197 3 .60 B4.71! 3.01 56.18 3 .79 66.38 5.46 100.06 710 1~ . 95 (]'IC') 230 194 3 .59
~
9556 3.16 64.51 3 .97 78.11 S59 116.71 711 166.27
~
230 190 3 .59 Hl9.!14 3.36 42 1 93.75 sn 138.90 7.12 19-4.71) Z30 188 3.57 117.Q2
~
3.42 . 7 4.26 102.42 &.75 150.34 7.02 208.45 tJ1 Z30 18~ 3.54 127.63 3 .51 94A9 ~.33 115.39 5.72 187.49 8.88 2211.06
~
230 182 3.51 138.24 3.511 105.00 4.40 1211.37 5.69 184.85 6. 73 249.71 2.10 160 3. 49 145.31 3.66 112.02 '.44 137.D3 5.tr7 196.09 6.604 .26-1.47 ""C 2:)() 176 3.48 ISO.13 3 .73 127.04 ' .48 ISS.oo 5.56 218.32 6.47 2119.19 S>> 2.30 230 173 170 3 .4< 3.42 169.49 179.l14 3.110 138.30 4.51 166.48 5.51 234 .l1li 6 .31; 3011.48 :::s 3 .66 149.67 4.54 181.96 5.'5 251.88 6.22 327.78 230 167 3.41 100.00 3.92 161 .43 4.56 195.66 5.35 287 .66 6 . 13 346.00 "C (I) 230 154 340 200.27 3.117 173.29 4 .57 209.35 5.32 283.71) 6 .06 36423 ~ 230 160 3.39 213.88 * .05 189.11 * .59 227.62 5.23 305.07 5.93 388.53
""C
~ o""C WritlenB.
-I Reviewed bo ~r ~-
Q.CD ApprOll8d I:'!c~:~ _ .. _
- 3
_. .N. Efleclive N I BOL~ 4096pcm EOL~ 4485 pcm
- l 0 ~
~3_. ~
Qj ::J
.... c ~. CD (I) C/l
-Ill 3-GRAPH.RV-13 Rev.7 III = ~~ o BANK POSITION TO MAINTAIN[HFP TARGET FLUX DIFFERENCE n ZN C 0 Cye E16 0) 38 230 Written By rr- .k~ -.AI' . n 0'" -...J (1) -...J
...... 220 Reviewed By:- ~ ./.' :
c ., m Approved By:_._ __ . / ./ ' ' iii' NO 0 ...... 210 ___._ EHective Date: >" ~cc..-':' _1- ,( ~ _~' ... ..,.' CD 0' 0) 0:-"
-...J 0- 200 -...JO on l\l ~,.-.::~ ."
o 190 o
...... ~ ;:"".- ~
180
--<- - ".. . ..,CD 170 - .MOL ,......---. :::0 J..~ ~ .... CD o ~ -~~ Q.
~ 160 01)
- g. 150 ~Ol~ ,
""OC Q) n
, ('l)
(0 -_. NO Vi o
-o=ii On'
-;; 140
~~
"Uc N~
.2
~ 130 o
,/ 0:::0
...... 11.
-CD
-' BANK 0 POSTION (Steps Withdrawn) ......0) w o 120 (JIn
-" /
;; 110 t----------+~--------~--------_+----------~--P~r%
Ql l! SOL ~ EOl 100 t--------"t---------t-;=::::::::::--t--------t--- 30 40 156 164 160 166 45 101
~
90 I "'r--...
~ ~~------.a_-60 50 172 172 157 -
0) 80
/
EOl Z
- 70 80 181 190 201 179 186 195 169 181 193 "C
~
70
, C/l 90 211 205 204 ..,
CD 60 , ' ~ 100 230 230 230 ."
-I 50 o
- b Q.(1)
- 3_. "N 3'
40
- I tr1 I
."I N
- '0 o 40 SO ~ 60 70 80 90 100 -a.
~3 .., _. ~ Relative Power (%)
Qi :J _c
<" CD (b (J) m
~
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 I
- Cycle Burnup (MWD/MTUI Specllled Boron Concenlrallon (ppm) '"
Relative Powerj%l"
=
150 974 100 2000 MWQIMI!.I 6000 1194 100
~
12000 100! 100 E.Qi. 25017 100 100 Moderato,.lemperalure Coefflclenl (perrilFl. -'2.9 *10:9 -is.1 -29.8 Isothermal Temperature Coefficient (pcm/F) = -'4.6 -12.7 -17.2 -33.' Moder.tor Temperature Defeet (pcm) .. -221 .9 -173.9 -252.8 -557.6 Doppler Power Coefficient (pcml"l. power) * -S.9 -8.6 -S.8 -8.9 Doppler Temperature Coefficient (pemlF) .. -1.3 -1.3 -1.4 -1 .4 Do"ppler Power Defect (pcm) " -l1n.2 -'177.3 -1221.0 -1173.8 Total Power Coefficient (pcml"l. power). -13.8 -12.6 *14.7 -21.3 Tota' Power Defect (pcmi .. *1606.0 -1440.3 -1663.S -2349.7 Axial ReactlvilY Redistribution Defect (pcm) .. -206.S -S9 .1 -190.0 -618.3 Control Banks Diff..rential Rod Worth - C bank and 0 bank (pcmlstep) .. 4.7 5.0 5.2 6.6 Control Bank 0 AVer89" Differential Rod Worth 100 to 223 steps (pcmlstep) 3.1 3.4 3.7 5.4 Control Bank D Power Worth (stepel%) " -4 -4 -4 -4 Hlgheet Worth Stuck Rod (pcm) " 948(N-ll) 762 (K-IO) Dropped Rod Worth (pcm) = 100.0 100.0 100.0 100.0 Differential Boron Worth (pcmlppm) " -6.316 -6.289 -6.687 -8.199 BoreUon (using 12_5 % Boric Acid) (gal/ppm) = 3.1 3.1 3.1 3 .0 Dilution (Pure Makeup Water) (gal/ppm) = 66 54 64 645 I Boron Dilution Worth (pcm/gal) = -0.096 -0. 116 -0.104 -0.013
/
= ~
Bontloa WOr:lb (pcmigaJ) -2_04 *2.16 -2.73 Dilution Differentia. Power Worth (No Rod Motion) (9all%) ~ 144 108 141 1675 Boration Differential Power Worth (No Rod Motion) (gaJIV.) ,. 6.8 6.2 6 .8 7.8 Other Parameters Pressurizer Level Hot - 75 9all% Cold - 125 gal/OJ. Pressurizer Pressure I"F ,n ~ 1% 6 Level 1% 6 pzr Level ~ 1011 6 Press 1°F 6 Tavg ~ 1OO~ 6 Press when solid IANSWER KEY \ Sleam Dump Steam Flow - .1.75% Steam FlowfOF Temp. Error Above S'F Dead Band Using Ina above information, other conlrol parameters CaIl easily be derived if Ihe desired units are known . Linaar interpolation 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. By:: .
~
Wrinen Reviewed Approved By: By:q+;E.
~ .
Ellective Dale: ::r - 16 - ,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 minutes Task Number: 2000770101 2-POP-2.1 Administrative
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 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> 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:
c Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 1 of 8 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: 0001251601-1 .doc Difficulty: 2 Time: 15 minutes Task Number: 0001250501 3-FR-1.3 Administrative
Perform 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: RO A 2 KA Number and Importance: 2.1.25 Conduct of Operations Ability to interpret reference materials such as graphs, curves, tables etc. RO - 3.9 Suggested Environment: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 15 Min Actual Time: ---
References:
3-FR-1.3 Response to Voids in Reactor Vessel File: 0001251601-1 .doc Difficulty: 2 Time: 15 minutes Task Number: 0001250501 3-FR-1.3 Administrative
Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 3 of 8 INITIAL CONDITIONS:
- 1. An event occurred 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR 1.3.
- 2. 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 pressure 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 minutes Task Number: 0001250501 3-FR-L3 Administrative
Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 4 of 8 Denotes Critical Step STEP S/U DESCRIPTIONS I CUES & NOTES STANDARD Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below
- 1. Commence evaluation Candidate will be
- 2. Obtain Current Rev of Procedure given procedure Calculates 2.41E6 to
.3 Determine Containment Volume at STP (A) 2.43E6
.4 Determine Maximum Hydrogen volume that can be vented (8)
Calculate 4.82E4 to 4.86E4 Determine Hydrogen flow rate as a function of
.5 RCS pressure (C) 2900 to 2950 Calculate maximum venting time Calculate 16.3 to
. 6 16.7 minutes JPM Complete File: 0001251601-1.doc Difficulty: 2 Time: 15 minutes Task Number: 0001250501 3-FR-1.3 Administrative
Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 5 of 8 Number: litle : Rev -; 5 i on Plumber : 3*FR-I.3 R£S~NSE TO VOIDS I N REACTOR VESSEL lJ Attach~ent 4 (Attachm~nt pag~ 1 of 1) INSTRUCTIONS FOR DETERMINING VENTING TIME I I. DETERMINE Containment Volu~ at STP - A A - ( 2.61 xl 0 6 Ft 3 ) x _ _ _~p_ _ _ _ x _ _.:::.4.o<.J92"-o-,,R~_ 14.7 psia T where : P (psig) - Containment pressure (psig) + 14 . 7 T( OR) - Conta i nment temperature(OF) + 460 A - ( 2.61xl06 Ft 3 ) x 11.;).. x 4!/Z°R 14 . 7 psia (,~O
).*41 A- ~ ."f~ 'B. cfo Ft3
,.,,~
. - 2. DETERMINE Milximulli Hydrogen volulIIe that can be vented - B B - (3$ -- Containment Hydrogen Concentration) x A 100S
'f.YJ. 4 B - _.-J'1,iu..Y....t:;'g;.u()' --_
CL11 _ _ Ft 3
~.ft,
- 3. DETERM1NE Hydrogen flow rate as a funct10n of ReS pressure - e
- a. CHECK RCS pressure .
- b. DETERMINE Hydrogen f l ow rate using Attachment 5. HYDROGEN FLOW RATE VERSUS RCS PRESSURE, Page 29.
C a J1ot> - ~SD SCFM ANSWER KEY
- 4. CALCULATE maximum venting t1~:
Max i mum venting t i me ~ C Maximum vent i ng time - l /' * ~* lit.? minutes
-END OF ATTACHMENT*
I Page 28 of 29 File: 0001251601-1 .doc Difficulty: 2 Time: 15 minutes Task Number: 0001250501 3-FR-1.3 Administrative
Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 6 of 8 Nu mber : Title : Revision Mumbfr: 3 - FR-I_3 RESPONSE 10 VOIDS IN R£AC10R v[SSH o M;tachm~!!l !! (Attachment page 1 of 1) HYDROGEN FLOW RATE VERSUS ReS PRESSURE FLOIolRATE (SCFM) 8000 ANSWER KEY V V 5000
/ ., c:'
4000 ./ V
/
3000
/
2000 ./
/
/
1000 I"
~
/
0 0 250 500 7S0 1000 12S 0 ]SOO 17S0 2000 2250 2500 RC S PRe SS UR[ (P SIG )
.. - END OF ATTACHME!rr 1
Page 29 of 29 File: 0001251601-1 .doc Difficulty: 2 Time: 15 minutes Task Number: 0001250501 3-FR-1.3 Administrative
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 minutes Task Number: 0001250501 3-FR-1.3 Administrative
Page 8 of 8 INITIAL CONDITIONS:
- 1. An event occurred 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR 1.3.
- 2. 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 pressure 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. File: Task Number:
I o
, \ 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 minutes Task Number: 2000700102 IP-SMM-DC-904 Administrative
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 minutes Task Number: 2000700102 IP-SMM-DC-904 Administrative
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 minutes Task Number: 2000700102 IP-SMM-DC-904 Administrative
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
- 1. Commence evaluation Obtain current copy of IP-SMM-904 2.
CUE: Candidate given procedure Document Review on Attachment 10.2 Identifies dates
- 3. Calibration due dates recorded recorded Identifies dates within
- 4. Instruments within calibration calibration
- 5. Changes documented by TPC Identifies NA Identifies step 4.2.7
- 6. All required procedural steps completed NOT signed off All steps NOT completed noted & explained in Identifies step 4.2.7 7.
Comments Section not signed off Identifies correction on page 12 is
- 8. All corrections lined out, dated and initialed correctly lined out, dated and initialed All Calculations Correct Identifies calculations
- 9. NOTE: On page 14 step 4.2.15 data is correct incorrectly transcribed. The calculation is correct; however it is OOS Identifies step 4 .2.15 pump discharge
.10. All data properly transcribed pressure not properly transcribed from page 12 to page 14 Required CRs, WOs, PFs, or CTSs etc
- 11. Identifies NA initiated File: 2000701602-1 .doc Difficulty: 2 Time: 15 minutes Task Number: 2000700102 I P-SMM-DC-904 Administrative
, Perform a Peer Review of a Surveillance Test Page 5 of 8 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Identifies conclusions correct for the
- 12. Operability conclusions correct corrected data on
_page 12. Identifies conclusions correct for the
- 13. Overall acceptance conclusions correct corrected data on page 12.
JPM Complete File: 2000701602-1.doc Difficulty: 2 Time: 15 minutes Task Number: 2000700102 I P-SMM-DC-904 Administrative
I Perform a Peer Review of a Surveillance Test Page 6 of 8
-E".." , 11 terp,y IPEC SITE MANAGEMENT MANUAL QUALITY RELATED ADMINISTRATIVE PROCEDURE INFORMATIONAL USE IP*SMM DC-904 Page 20 Revision of 3
20 ATTACHMENT 10.2 PEER REVIEW SHEET PEER REVIEW SHEET PROCEDURE NUMBER: 3 -\'IF Qltl.:> 0 DATE PERFORMED: ~ -I 0- I 0
./
v' V*
./
,/
./
r/ V I,/"" COMMENTS: I-{- 5"", tf.') .7 not .j)~~cC '# ts-+cp ac-hOn~ (lUW\ple-k) 7f(Yd,,/ trd"jCflbed -for" s~r.Lf.;t,,, C~(c<<13~~ perfo' rl\Id oo(rec-fl~j hplV(l)t( tlv rt!'~ult l~ tJo~ ANSWER KEY PEER REVIEWER: £~ [)~ ~dtdtut: S\gnalur~ ;;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 minutes Task Number: 2000700102 IP-SMM-DC-904 Administrative
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. File: Task Number:
I o
Perform a SG tube Leakrate Determination using 3-AOP-SG-1 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: 0350041602-1 Difficulty: 2 Time: 15 minutes Task Number: 0350040502 3-AOP-SG-1 Adminstrative
Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 2 of 8 JPM
Title:
Perform a SG Tube Leak Determination using 3-AOP 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: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 15 Min Actual Time: - - -
References:
3-AOP-SG-1 Steam Generator Tube Leak File: 0350041602-1 Difficulty: 2 Time: 15 minutes Task Number: 0350040502 3-AOP-SG-1 Adminstrative
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 minutes Task Number: 0350040502 3-AOP-SG-1 Adminstrative
Perform a SG tube Leakrate Determination using 3-AOP-SG-1 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 Candidate may use
- 2. Enter data Attachment 1 or separate paper Determines Avera~e
- 3. Calculate average R-63 R-63 is 1.49 X 10 j.Jci/cc Determines SG Tube
- 4. Calculate SG Tube Leakage for 1215 Leakage is 15.12 gpd Determines SG Tube
- 5. Calculate SG Tube Leakage for 1230 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 minutes Task Number: 0350040502 3-AOP-SG-1 Adminstrative
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 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> .
- If leak < 30 gpd, take data once every 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />.
R-63 Current* **DELTA Method Used To R-15 Time *Date (!lCi/ee) Leakrate LEAKRATE Determine (!lCi/ee) gpm (gpd) gpm (gpd)/hr Leakrate A B 1215 Today 8.37 X 10-6 1.09 X 10.2 1.9 X 10.2 15.12 gpd 1230 Today 8.5 X 10-6 1.09 X 10.2 1.9 X 10.2 15.36 gpd 0.96 gpd/hr Answer Key
- The DATE is required to be recorded in the first entry and when the date changes: otherwise, the DATE may be left blank.
** DELTA LEAKRATE 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 minutes Task Number: 0350040502 3-AOP-SG-1 Adminstrative
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 minutes Task Number: 0350040502 3-AOP-SG-1 Adminstrative
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. File: Task Number:
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 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />.
- If leak < 30 gpd, take data once every 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />.
R-63 Current **DELTA Method Used To R-15 Time *Date (~Ci/cc) Leakrate LEAKRATE Determine (~Ci/cc) gpm (gpd) gpm (gpd)/hr Leakrate A B 1215 Today 8.37 X 10-6 1.09X 10.2 1.9X10*2 1230 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 LEAKRATE 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: Task Number:
I 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 minutes Task Number: 2000050102 0-SOP-LEAKRATE-001 Administrative
Review a Gross Leakrate Determination Calculation Page 2 of 10 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 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. SRO - 4.7 Suggested Environment: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 20 Min Actual Time: - - -
References:
o SOP LEAKRATE-001 RCS Leakrate Surveillance, Evaluation and Leak Identification File: 2000051602.doc Difficulty: 3 Time: 20 minutes Task Number: 2000050102 O-SOP-LEAKRATE-OO 1 Administrative
Review a Gross Leakrate Determination Calculation Page 3 of 10 INITIAL CONDITIONS: The plant has been operating at 100% Power for 200 days. An increase in containment humidity has been observed The PC program for leakrate calculation is not available. An RO performed a Gross Leakrate Determination in accordance with O-SOP LEAKRATE-001. Non-RCPB Leakage from previous evaluation 0.15 gpm Previously identified leakage from previous evaluation 0.03 gpm 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 minutes Task Number: 2000050102 0-SOP-LEAKRATE-001 Administrative
Review a Gross Leakrate Determination Calculation Page 4 of 10 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 Candidate will be
- 2. Obtain current copy of procedure given the procedure
- 3. Evaluate Manual Calculations See Below Determine Total Attachment 1 Step 1a Time is 127 minutes Calculate Total Time NOT 137 minutes Attachment 1 Step 1b Determine 6.26
- 5. Calculate Change in Mass due to Change in gallons is correct Pressurizer Level Attachment 1 Step 1c Determine 104.48
- 6. Calculate Change in VCT Mass due to change gallons is correct in level Attachment 1 Step 1d Determine - 8.64 is
- 7. Calculate Change in RCS mass due to change incorrect it should be in Tavg + 8.64 gallons Determine 102.1 is Attachment 1 Step 2
- 8. incorrect; it should be Calculate Gross Leakage 119.38 gallons Determine 0.74 gpm Attachment 1 Step 2
- 9. is NOT correct; it Calculate Gross Leakage LR1 should be 0.94 Determine 0.56 gpm Attachment 1 Step 3
- 10. is NOT correct; it Calculate Unidentified Leakage should be 0.76 gpm Attachment 1 Step 5 11.
Candidate does Not Sign the form
- 12. JPM Complete File: 2000051602.doc Difficulty: 3 Time: 20 minutes Task Number: 2000050102 O-SOP-LEAKRATE-OO 1 Administrative
Review a Gross Leakrate Determination Calculation Page 5 of 10 No: O-SOP-LEAKRATE-001 Rav: 1 Res LEAKRATE SURVEILLANCE, EVALUATION AND LEAK IDENTIFICATION Page 490'63 ATIACHMENT2 CALCULATING GROSS RCS LEAKAGE (Page 1 of 2) 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.
1.0 RCS Manual Leakrate Calculation Worksheet: Circle one: Unit 2 ( ): Indicates mathematical sign must be observed.
.) CALCULATE lolal time [1J Final: Time i d. ~ d l[ Answer Key Initial: T1me Elapsed Time b) Change In R ~MIQ'-'Iooio/00i000t4ren 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. CI OF
- H S. '1
~~
Initial: TAVE OF ~ 8.L' Difference: (- ) o. i .q OF x (86.444 g =:: 8.Vi Ie] File: 2000051602.doc Difficulty: 3 Time: 20 minutes Task Number: 2000050102 O-SOP-LEAKRATE-OO 1 Administrative
Review a Gross Leakrate Determination Calculation Page 6 of 10 No: O-SOP-LEAKRATEoOO1 Rev: 1 i RCS LEAKRATE SURVEILLANCE, EVALUATION AND LEAK IDENTIFICATION Page SOot 63 ATIACHMENT2 CALCULATING GROSS RCS LEAKAGE (Page 2 of 2) Answer Key 2.0 in System Volume Leakage {LRd 6, 1') gpm b) RECORD previously identified Leakage (from previous Evaluation [LAsD: 0, CI ) gpm A poslUve number indicates a net removal of mass from the system. 1_---"'0'-,_o_. -~_ _ gpm - 0 ,0 ~ [LRa] lLRa] 4.0 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).
5.0 !E there is an unanticipated 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 Gross 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)
Commen~: Print name Signature Date File: 2000051602 .doc Difficulty: 3 Task Number: 2000050102 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 minutes Task Number: 2000050102 O-SOP-LEAKRATE-OO 1 Administrative
Page 8 of 10 INITIAL CONDITIONS: The plant has been operating at 100% Power for 200 days. An increase in containment humidity has been observed The PC program for leakrate calculation is not available. An RO performed a Gross Leakrate Determination in accordance with O-SOP LEAKRATE-001 . Non-RCPS Leakage from previous evaluation 0..15 gpm Previously identified leakage from previous evaluation 0.03 gpm INITIATING CUES: You are the CRS and the SM has directed you to review the Gross Leakrate Determination. File: Task Number:
Page 9 of 10 No: O-SOP-LEAKRA TE-001 Rev: 1 RCS LEAKRATE SURVEILLANCE,
. r~ EVALUATION AND LEAK IDENTIFICATION Page 49 of 63 ATIACHMENT2 CALCULATING GROSS RCS LEAKAGE (Page 1 of 2)
Date: TDl)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 observed. a) CALCULATE tolal time fTJ Final: Time I). : <+ l( Initial: Time W: Il Elapsed Time ~\~ ~,-,7,--__ mlnutn [T] 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 /Q~* . cf '!? 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 OF X (86.444 gall"F) = (-) ,; .t {/ gal [F]
Ie] File: Task Number:
Page 10 of 10 No: O-SOP-LEAKRA TE-Q01 Rev: 1 RCS LEAKRATE SURVEILLANCE, EVALUATION AND LEAK IDENTIFICATION Page 50 of 63 ATIACHMENT2 CALCULATING GROSS RCS LEAKAGE (Page 2 of 2)
2.0 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 Evaluation [LR2I): 6 .1 '5- gpm b) RECORD previously Identified 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
~~[~LR-d---
gpm- 0 .\ <;
---~(~LR~d~---
gpm- 0. 0,) [~ gpm.. D,'; L* gpm [LR Unidelllltlell] 4.0 RECORD [LR1] 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).
5.0 IE there is an unanticipated 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 Seelion 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 11:_-,O,,-'
, ,-~)_'1_
, -._ _ _ _ _ _ _ _ gpm Unidentified Leakage [LR unldontlfled!: O.'l{., gpm Performed by: '2.> ,'),:- 1'-" Of(f~'::l q", ra"t1J4~~ (' ptA-dli1t I./),dftr (RO)
Reviewed by:--:::-:-~ _ _ _ _ _ _ _-=:-_~_ _ _ _ _ _ _ _~_ _ (CRSlSM) Print name Signature Date J Commen~: __________________________________________ File: Task Number:
Review Reactor Vessel Venting Time Calculation per FR-1.3 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: 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 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: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 15 Min Actual Time: ---
References:
3-FR-I.3 Response to Voids in Reactor Vessel 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 3 of 8 INITIAL CONDITIONS:
- 1. An event occurred 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR 1.3.
- 2. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel.
- 3. 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 pressure 1000 psig 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 minutes Task Number: 0001250502 3-FR-1.3 Administrative
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 Candidate will be
- 2. Obtain Current Rev of Procedure given procedure Calculates 2.42E6 3 Determine Containment Volume at STP (A) Determines TSC did not add 460 0 Determine Maximum Hydrogen volume that can be vented (8)
.4 Note this is incorrect because previous Calculate 4.84E4 to 4.86 E4 calculation was incorrect.
Determine Hydrogen flow rate as a function of 5 2850 to 2950 RCS pressure (C) Calculate maximum venting time Calculate 16.4 to 6 Note this is incorrect because previous 17.0 minutes calculation was incorrect. JPM Complete 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 5 of 8 Nullltltr: Tit Ie: ~.1 s 1011 Nulllber; 3-FR - J.3 RESPONSE TO VOIDS IN REACTOR VESSEL {) Attachment 4 (Attachment page 1 of 1) INSTRUCTIO"S FOR PETERMINING VENTING TIME 1_ DETERMINE Contl1n.ent Yolu.e it STP - A A - I 2 . 61 xl 06 Ft 3 ) x _ _ _..:.P___- - - , - - .....*~R'--_ X _ _. :z.4&J92 14.7 psia T where: P Ipslg) - Containment pressure Ipsig) + 14.7 TI*R) - Containment temperatureC*F) + 460 A - ( 2 _6lxl 06 n3 ) x \1. :l x 14 . 7 psia
@ t,lD A -~ JAl¥Ii)(,.Ft3
- 2. DETERMINE Haxl.u. Hydrogenvolulle thlt cln be vented - B B - (3; Containment Hydrogen Concentration) x A
.... ~ 100; B- ~4.R4fflO~Ft3
- 3. DETERMINE Hydrogen flow rate as I functlon of ReS pressure - C a . CHECK ReS pressure.
- b. D[TERM 1NE Hydrogen flow rate using Attachment 5, HYDROGEN FLOW RATE VERSUS ReS PRESSURE. Page 29 .
e - __d.::....'1..:...::;.. D .::...._ U ___ SCFM
- 4. CALCULATE .axi.u. vent1ng t1.e:
Maximum venting time - B C Maximum venting time - @ l nG. minutes Answer Key ,
- END OF ATTACHMENT f
Page 28 of 29 I 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 minutes Task Number: 0001250502 3-FR-1.3 Administrative
Page 7 of 8 INITIAL CONDITIONS:
- 1. An event occurred 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR 1.3.
- 3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel.
- 3. 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 pressure 1000 psig INITIATING CUES: You are the CRS and the SM has directed you to review the Reactor Vessel Venting Time calculation . File: Task Number:
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
- 1. DETERMINE Containment Volu~ at STP - A A .. ( 2. 6] xl 06 Ft 3 ) x ____p'--_ _ _ _ x _ _.....9Z 4........o.....R'--_
14.7 psia T where: P (psig) - Containment pressure (psig) + 14.7 T(OR) - Containment temperature(OF) + 460 A - (2.6lx10 6 Ft 3 ) x _ _~\:,-l-::,:l_--:-__ 14.7 psia Ft 3
- 2. DETERMINE Haxfmu~ Hydrogen volume that can be vented - B B ~ (3: -- Containment Hydrogen Concentration) x A 100S B - _'"-t'--'~,-7.:....r,-,I~Q_
-' ;')___ Ft 3
- 3. DETERMINE Hydrogen flow rate as a function of ReS pressure - C
- a. CHECK RCS pressure.
- b. DET£RMlNE Hydrogen flow rate using Attachment 5, HYDROGEN FLOW ~ATE VERSUS ReS PRESSURE, Page 29.
C ~ JC;' CO SCFM
- 4. CALCULATE maximu. venting ti~:
Maximum venting time - B C Maximum venting time & minutes r II*.
*END OF ATTACHMENT*
File: Task Number:
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 minutes Task Number: 2000450102 OAP-34 Administrative
Review a Safety Function Determination Page 2 of 13 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 minutes Task Number: 2000450102 OAP-34 Administrative
Review a Safety Function Determination
. Page 3 of 13 INITIAL CONDITIONS:
Unit 3 is operating at 100% Power 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> 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 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />. This was the only Active LCO at that time. 5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> 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 minutes Task Number: 2000450102 OAP-34 Administrative
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 Identify Tech Spec required Supported Determine 3.5.2 and 2.
Systems entered in D 3.8.9 are correct Determine 3.7.5, Identify Systems supported by the system 3.7.8, 3.7.9, 3.7.11, 3. listed in D above entered in E 3.7.13, 3.8.1, 3.8.4, 3.8.7 are correct Determines 3.4.4, Identify all systems supported by the systems 3.5.2.,3.7.8,3.7.12, 4. listed in Block E above 3.8.1, 3.8.9 are correct Identify any systems redundant to those Determine 3.5.2 is
- 5. systems identified in D, E, and F above that correct are tracked by active LCOs entered in G Identify systems supported by systems listed Determine None is 6.
in G above entered in H correct Identify the systems supported and affected by Determine None is 7. the systems listed in H Entered in I correct Identify redundant systems listed between Determine 3.5.2 is 8. blocks D, E, & F, and G, H, and I correct Review the minimum equipment required to Determine Block K is 8. mitigate an accident operable NOT correct Determine Loss of
- 9. Review Loss of Safety Function Safety Function NOT correct File: 2000451602-1.doc Difficulty: 4 Time: 30 minutes Task Number: 2000450102 OAP-34 Administrative
Review a Safety Function Determination Page 5 of 13 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Do Not Sign Safety Function Determination
. 10. Does Not sign Form Form JPM is Complete File: 2000451602-1 ,doc Difficulty: 4 Time: 30 minutes Task Number: 2000450102 OAP-34 Administrative
Review a Safety Function Determination Page 6 of 13
\ No: OAP-034 Rev: 2 SAFETY FUNCTION DETERM'NAT'ON
\ L PROCESS J Page 12 of 37 ATIACHMENT1 Safety Function Determination (Page 1 of 2) SAFETV FUNCTION OETERMINATION A. Inoperable system: R.t.nlne. CR Number:
* ~1.. 'E:~eN: \ f-(i \)'t t~~'
,.j i G~/~
I Safety Functlon(.) (S,C,H,P.Z,I), ref. Itep 6.3. C ~ 7- '"I TS Sectlon(l) /3,A. \
- 8. Technical Sp4Iclflcation Related: -V V** 0 No C. Support sy.tem: (l;l' Ye. 0 No D. LI.t all syatem. supported by the Inoperable system Identified above:
3.S .2 W84t
~<)'-~b1 31~fg -
E. List all systems supported by the sy.tems listed In block 0 above: ___~7 , 5' 3.7 13 -.... 3* 7 .g -- 3 , '? I I 3,/ * '1 -_.. ~ .~.~
"j.t.1 1 3 . ~ ,1 F. LI.t all sy.tem. supported by the system. listed In block E above:
~.~.:l 3.'? \
3 , 5 2 .._. -~~~-- - --- -- , 317. C;
~ "
- IZ-G. 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- ._ - -
~-- . ---- -- -- ...- ... -. . ..-.. ~- - .. ..- -- ..._ ... -- - - .....-- .. - - -.-- ~ --- ---_.... . - --. _._-_. J L- -- -.
File: 2000451602-1.doc Difficulty: 4 Time: 30 minutes Task Number: 2000450102 OAP-34 Administrative
Review a Safety Function Determination Page 7 of 13 r---.--- - . Rev:.~ I I SAFETY FUNCTION DETERMINATION i No: OAP-034 L- PROCESS i Page 13 of 37 _____1 ATTACHMENT 1 Safety Function Determination (Page 2 of 2) 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:
~L
~CIJL J. Identify redundant system. fisted between blocks D. E. & F ~ G_ H.4i I above:
3*5 "2
~
K. II the minimum equipment required to mitigate an accident op.r.~~ ~. 0 No If the minimum equipment required to mllf?~~ I. not 0 able the lOI' of Safety Function exists. /. _ L_ Don. Lo.e of Safety Function exist? ~ 0 Yel ~N.l - ltiCofrt'Ct
"
- Lo** of Safety Function exletl, then rform th tlons of the Leo in wl1lch the Lo** of Safety Functton exllts.
M_ RevlewlApproval: Prepared by: ,5h)U II? -.1\1\ ~4' - _Q. ,i~"' ;/t *v $)1;~J .f: 'bc, kId (STA) Name Ignarure Dale Reviewed by: SM/CRS/FSS , i SAO (Current)
-- - Name Signat ure Date Time : 30 minutes Difficulty: 4 File: 2000451602-1.doc Administrative OAP-34 Task Number: 2000450102
Review a Safety Function Determination Page 8 of 13 SAFETY FUNCTION DETERMINATI~~-~ OAP-03~_ __ _ R _ e_v: 2 i PROCESS I Page 9 of 37 6 .2 Minimum Equ ipment 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 Generators
.- . .~- - .. ' . - -¥ ~ ..---
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 Service 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 ical Specification Shutdown Sections. The minimum equipment required is determined based on Technical Specifications, plant status, and plant configuration .
6.3 Safety Function A function described or specified in the Technical Specification Bases Section "Applicable Safety Analysis", FSAR - Chapter 14, Design Basis Documents, or Acc ident 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 inment integrity. and RCS inventory. File: 2000451602-1.doc Difficulty: 4 Time: 30 minutes Task Number: 2000450102 OAP-34 Administrative
Review a Safety Function Determination Page 9 of 13 SAFETY FUNCTION DETERMINATION . bo: OAP-034 _ __ R~ PROCESS __.__ipage 7 0'_3_7 _ _ __ ~ 4.2 .5 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. 4.2.6 IDENTIFY all systems supported by systems entered in G. 4.2.6.1 RECORD identified systems in "H" of Attachment 1. 4 .2.7 IDENTIFY all systems supported by systems entered in H. 4 .2.7.1 RECORD these systems in "I" of Attachment 1, 4 .2.8 ENTER any redundant systems identified during the evaluation in oJ" of Attachment 1. 4 .2.9 lE redundant systems have been identified, THEN DETERMINE if the minimum equipment required to mitigate an accident is operable. 4 .2.10 4 .2.9.1 INDICATE the determination in 'K' of Attachment 1. 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). -
File: 2000451602-1.doc Difficulty: 4 Time: 30 minutes Task Number: 2000450102 OAP-34 Administrative
Review a Safety Function Determination Page 10 of 13 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 minutes Task Number: 2000450102 OAP-34 Administrative
Page 11 of 13 INITIAL CONDITIONS: Unit 3 is operating at 100% Power 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> 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 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />. This is the only Active LCO at time zero. 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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 . File: Task Number:
Page 12 of 13 SAFETY FUNCTION DETERMINATION [ No: OAP-03~ Rev: 2
,i L.
PROCESS I Page 12 of 37 ATIACHMENT1 Safety Function Determination (Page 1 of 2) SAFETY FUNCTION DETERMINATION A. Inoperable system: Reference CR Number:
- 31 ~j\\ e I"~ f. 'A t. ..\ \) i t ;. 'i' \ (q ~j'~
Safety Functlon(&) (S,C,H,P.Z,I), ref. step 6.3. C t--t -z. . :r TS Sectlon(l) /3,8" l B. Technical Specification Related: ~ Ve. 0 No C. Support system: ~ Yes 0 No O. List al\ system. supported by the Inoperable Iystem IdentIfied above:
--~--- --
3 ,5 ,2 ' -- - -'
~ I~ d ____ .- _._-_.*
E. List all systems supported by the systems listed In block D above: ___..~ *5 3. 7 , 13 -_.
-_.__. 3* 7 .g *... - 3 ,%
- I 3./*'1 ~ \~ . ~
? 7 . 11 3 Ii 1'1 F. List all systems supported by the systems listed In block E above :
__ . ~ l\.f I"i 3.? \ .. 3 5 .2-1 "3 *i~_ __.__ - .- - - . .- - - - ...
- 3. 7. 'i -
~.I , I 2,..
G. 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:
--.-~.'I) 2 _ "_ _ _ _ _._ 0>. . _ "_ _
- -.. -- -- - - -.. _ .- .- ..
- _ __ .... . __ _ . ~ ** _ _ _ A
_ _
- _ _ _ _ _ ' _ _ A _ _
File: Task Number:
Page 13 of 13 Rev: ~ i I SAFETY FUNCTION DETERMINATION \ No: OAP-034 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 . . --- I. List the systems supported AND affected by the systems listed In block H above: tJC~f.. J. Identify redundant systems fisted between blocks D. E. & F AND G. H.& , above: 3 ,S ~ K. Is the minimum equipment required to mitigate an accident operable? !B'Yes 0 No If the minimum ~uiJ)ment requlrsd to mitigate an accident Is not operable then a LOll 01 Safety Function exists. ./ L. 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. M. Review/Approval: Prepared by: .5k 4 \e.c.v,I\'!'.....Q. ,.:.\.J II \/~ ,V' '5~,¥ ~J 1?i....
. U q .~ ~li (STA) Name Signature Date ReViewed by:
SM/CRS;FSS ! SRO (Current) - - - --Name- *- - --- ---------s;gnature---- -Oate- " File: Task Number:
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 minutes Task Number: 2000180102 3-S0P-WDS-13 Administrative
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 minutes Task Number: 2000180102 3-S0P-WDS-13 Administrative
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 3 Concentration of Noble Gases 1.3 X 10- !-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 minutes Task Number: 2000180102 3-S0P-WDS-13 Administrative
Review a Manual Gaseous Rad Waste Release Permit Page 4 ofa
- 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 Ensures given data
- 2. Review Entered given data properly entered Deterrnine Total Activity Not Correct
. 3. Calculate Total Activity Correct Value 1.31 X 5
10 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 Determines Calculated Leakrate _ l8. Determine calculated leakrate NOT correct Correct Value 15.9 IJCi/sec Does Not sign the
- 9. Calculations are not correct form JPM Complete File: 2000181602-1 Difficulty: 3 Time: 15 minutes Task Number: 2000180102 3-S0P-WDS-13 Administrative
Review a Manual Gaseous Rad Waste Release Permit Page 5 of 8 No: 3-S0P-WDS-013 Rev: 26 GASEOUS WASTE RELEASES Page 36 of 55 ATTACHMENT 1, GASEOUS WASTE RELEASE PERMIT FORM (Page 1 of 1) Tank! Current System (1) '31 i.h1>r DateiTime (2) IDVI'N }lto o Permit No. (3)_-='_'_ __ Date Time Concentration 01
.. Volume (4) 5.11) 1t3 Inilial Pressure (5) '00 psig Noble Gas (C)(6)_-'I-',....!>"-"'\(....,"'-_~
IQ _ _-I~ClIec Grab sample:(7c;;-;t~ 'Q Date Tb'M 'l Time I (.,DT OR R-12 Monllor
. l. ~ l no'S Activity (A)(a) ~ :r UCi Noble Gas Iodine 131 Aclivity (8a) tJA- !lCi/ee l~ ,t\ VC Purge Only Calculated Release Rate (R}(9 \_-'--"7'"_.rCi/sec Available Release Aate (0)(10) ~Cilsec Discharge Monitor (11 )_ _->;) '"--
1'--_ _ __ Actual Alarm Selpoinl (12) 3. 1>B).(o 5 !lCi/sec Calculated alarm setpoin! (13)_....:~ c..:;.:....
" _ _--'UCiisec Alert setpoint(14) , . () 'liD j UCi/sec R* 12 Auto Closure/Alarm Setpoints: Calculated (15)_ _e f.)~ {}.0--_--JUCilcc Actual (16) UA uCi/cc IE discharge monitor is OOS, THE~ COMPLETE the following:
- Monitor (17)_ _tJ",,-
. .:..b.e--_Placed out service@ _ _..:.:::..:L: t.J "'_ _
Date Time
- Vent Sample:(18) Sample II f.,) A. Date_ _.!..C br_ _ Time N,--,- IJ A Results (19) NA uCi/cc (Noble Gas)
- Vent flow rate (20) ~ " elm Continuous Release Rate (CR)(21 )_---'l>;::..-!t-"-__
-. -I~Ci/sec Release Calculations verified by (22) _ _ _ _-'t""-I J b!:!.-________________
r Release Path Valve Alignment Verified (23) _ __ ~ _ _ _~_ __ __ _ _ _ _ _ _ _ __ CRS/SM Discharge Au1horized (24 J--=c::-=.,--,----- Release Stan (25)_---:::--_ CAS/SM 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.lOL-_ _ % 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 minutes Task Number: 2000180102 3-S0P-WDS-13 Administrative
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 File: Task Number:
.. Page 8 of 8 No: 3-S0P-WDS-013 Rev: 26 GASEOUS WASTE RELEASES Page 36 of 55 ATTACHMENT 1, GASEOUS WASTE RELEASE PERMIT FORM (Page1of1) Tankl Current System (1) 3/ L61)f DatelTime (2) 'TDOI'<Y hoo Permit No. (3)_...:...10-:'_ __ Date Time Concentration 01 I .. Volume (4) 5 ;).1) 1t3 Initial Pressure (5) 100 pslg Noble Gas (C)(6) t . '3 )(,W' ? uCilcc Grab Sample:(?) Sample # 35[,/0 Date TbDA Y Time I t,p, 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) I~ . '3 uCiisec Available Release Rate (OHIO) ipl'(1D~ uCilsec Discharge Monitor {I 1),_ _..J;;}.t.-J-L-_ _ __ Actual Alarm Setpoint (12) 3. l>B ); (o ~ J.l.CilS8C
. ,,?;J Calculated alarm setpoint (13)_..!~=!c_ ______JJ.lCilsec Alert selpoint (14) I fYi l ,; ~Cilsec R-12 Auto Closure/Alarm Setpoints: Calculated (15)_ _.ctJ'--"-()..:....-_--'UCilcc Actual (IS) 4) A ~Ci/cc
!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 H_-'~ r.=..:~
~_ _ Date_ _!.::tJ:.....:..:.~_ _ 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)_ _ _ _....!J"""'l!"- ________________
Relea.S8 Path Valve Alignment Verifled (23),_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ __ CRSISM Oischarge Authorized (24) _ _=~:-:- ____ Release Start {25)_--:=__ _ _ __ CRS/SM Dale Time Final Pressure (26) _ _ _ _ _ _psig Release Stop ( 2 7 ) _ _ _ _ _--=_ _ Dale Time Calculations Resul1s: S (28}_..._ _._ _ Emax (29) 5 DO ~ RCV-014 Setting (31)_--1 0'--__ 4 ... % open
) Comments:(32)_ _ _ __ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ __
File: Task Number:
c 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: Classroom Actual Testing Environment: Alternate Path: NO Time Critical: YES Estimated Time: Actual Time: - - -
References:
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 meters/second Wind Direction: 120 degrees @ 10 meters Stability Class: C 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. EAL (4.1.4)
** GENERAL Note: Declaration must be made within 15 minutes of start of JPM Time Declaration Made:
Complete and Approve "New York State Radiological Emergency Data Form, Part 1" Note: MUST BE COMPLETED WITHIN 15 Complete IP-EP-115
.3. MINUTES OF DECLARATION Form 1 Time IP-EP-115 Form 1 completed:
Refer to procedure IP-EP-21 0, Attachment
- 4. Attach 9.1 9.1 (SM / POM / ED Checklist)
Initiate County, State and NRC notification per IP-EP-115, Form EP-4, 5 or 6 as applicable Request for CCR 5. comunicator CUE: Acknowledge as communicator when requested to commence notifications. File: Difficulty: Time: minutes Task Number: Procedure Ref category
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: TI:2~AY.
- 1. j Reactor Status: ~ ~
This is an: EXERCIS Unit 2 f:Jperalloni!D ACTUAL EMERGENCY at: UNIT 2 ~ BOTH UNITS I (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
- 2. Th~ Emergency A. Unusual Event B. Alert C . Site Area Emergency 1>
Emerge~ ClaSllification is: Co: G eneral E. Emergency Tennlnated This Emergency Classification declared on: 'TllDMI at 11~~ DF J2ffl~t.A!1() J (Date) (T1me 24 hr clock) 3~ EAL#: "-1.1.4 Con.fi"I1lI'O ~sc" p.," I ~D18t1Dr1 OI"r\aLH> "Di<lI~t()~ft!Vld lot}. wl-hlle~5 -th2'n "n,nlrf\\AM ('"I"I{a, ,.,~ d £'OD"~ ~"a-(ds. qguftrltftf 1!J2'hr(;!, C.iab\t' .r..l-.~') I\"l{ It\6tc ~;,n-s l>+ $w I a ldo lo";)~ l'f.).ble 4, tJ
- 4. R'i!lease of Radioi!ctlve Materials due to the Clas~ified !;;V!!nt:
f>..
~oRelea3>+ B. Release BELOW Federal limits To Atmosphere To Water C. Release ABOVE Federal limits To Atmosphere To Water D. Unmonitored release requiring evaluation
- 6. Wind !21;!!lllg' 3.5 Meters/Sec a\ elevation 10 meters 6.
1~ t2 WlnQ Direction' (Frgml Degrees at elevation 10 meters Answer Key
- 7. StS!bilit~ Cla~s: A B @ D E F G 8.
The followtng Protective Actions are recommended 10 be implemented a5 soon as practicable: A. NO NEED for PROTECTIVE ACTIONS outside the site boundary
~VACUATE and IMPLEMENT the KI PUIN for the following Sectors C. SHELTER-IN-PUlCE and IMPLEMENT the Kf PUIN for the follOwing Sectors
*- ~( All remaining Arens MONITOR the EMERGENCY ALERT SYST~
~miles around 5-miles downwinV . 5 miles around 10'miles downwind Entire EPZ
¥- In Ihe followtng Sectors:Q) 6) 4 5 6 7 8 9 10 11 12 13 14 15 @
NOTE: OFFSITE AUTHOBITIES ~HQULD CQN§IQER :2HELTf,;R*IN*PLl!QE + IAKJ;; KIIE EVAQUATION 1:2 NOT FE8~II!Li;
- 9. Reported by - Communicator: Telephone #
(Communicator's Name)
~
10-¥: Emergency Director Approval: DatefTime: TbD,..\f M~ ::ny~ (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 meters/second Wind Direction: 120 degrees @ 10 meters Stability Class : C 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. File 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 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
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 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
Emergency Borate Page 3 of 9 INITIAL CONDITIONS:
- 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.
- 4. Current Boron concentration is 1148 ppm INITIATING CUES:
You are the ATC and the CRS has directed to emergency borate per ONOP 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 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
Emergency Borate Page 4 of 9 Denotes Critical Step STEP DESCRIPTIONS / CUES & NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1 Obtain correct procedure ONOP-CVCS-3 Observe Charging 2 Check Charging Pump running Pump RUNNING Verify MCC-36A 3 Check MCC-36A and 368 available and 368 energized OPEN Emergency Bot'ation Valve Places CHoMOV 333 to OPE 4 CUE Inform operatorthat MOV-333 win NOT ObserVes Valve
. OPEN ..
.. borate using Normal BoratiOn 8w~ath does not ODen .
Rotates SwitcheS
-5 . Place Boric Acid Transfer Pumps in Fast Speed Fast position Rotate.*. Borie~~~
_~ r~"'l r.<
-6 ReStart ~neACfd Trariafar PUmps r~:*c.: :"~'_ ~j:~~!,,!: '.i.-.~
.~
I
- ' ~ . 7 ' Place FCV-110A, Boric ACid Flow Control Raise Blender, controller in Manual to Manual~ ~~~
i***. EnsW8 FCV-1110A, Boric Acid FloW Control l Move fir bar to taft
-8 Blender, controller is fUlly open Open Place FCV-111A Makeup H20 to BoriC Acid :RaIse T bar 8wittb
. 9 Blender. controllet in Manual to Manual POsItion -
-? :::".
~ (.
. 10 Ensure FCV..111A,
- Boric Acid Flow Control MoveT'bar Blender, controller is closed Open t
. 11 Place Makeup Mode Selector switCh in ~I RotateSwitch. IJ-Manual Position Rotate SWitCh to Turn Makeup Control Switch to Start and Return . *12 Start then back to to NOflTlal .Ngrmal File: 0040421601-5.doc Difficulty: 2 Time: 10 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
Emergency Borate Page 5 of 9 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU 13 Check Ff-11OA flOw Indicated Observe FIQw Is indicated Cfoie Boric Acid storage Tank Recirculation I' Valves HCV-104 &HCV-105 R0bd8~ 14 (Panel SFF) to ~ Locatad on Panel SFF '. net_ ,.. Place~" :
,.u. ..... to u Transfer operating (:hai"ging pump speed to a : ~_
15 ~tQ manWif and Increase speed to MAXIMUM i~ .:.;.-~ .
- ~'.. . .:.
incre_ .. 0,,_ to *;1 Maximum Verify Pressurizer Check Pressurizer pressure LESS THAN 2335 16 pressure < 2335 psig psig Verify reactor 17 Check status of reactor subcritical 18 Check RCS temperature >500°F Verify RCS >500°F Check RCS temperature >540°F Observe RCS 19 approximately CUE: Cue Candidate Tem~erature is 535°F 535°F If any rod is greater than or equal to 20 steps Observes 2 rod 20 emergency borate per attachment 4 fully withdrawn Determine boration time NOTE: Minimum Boration Time 142 seconds for temperature. Candidate may continue with procedure and add 142 seconds with the time for Determines
- 21. stuck rods (34 min). for a total of 36 minutes and minimum of 142 22 seconds. seconds CUE: (Time Compression) Inform candidate that the calculated time has passed.
Determine 2 Rods 22 Determine status of Control Rods
> 20 Steps File: 0040421601-5 .doc Difficulty: 2 Time: 10 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
Emergency Borate Page 6 of 9 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU Determine amount of boron concentration increase required Calculate 212 ppm 23 boron concentration NOTE: 212 ppm for each additional rod greater increase required than one Determine boration time required NOTE: 34 min for each additional rod greater than one Determine 34 additional minutes NOTE: Minimum Boration Time 142 seconds for required
.24 temperature and the time for stuck rods (34 min). OR for a total of 36 minutes and 22 seconds. Determine total time 36 min 22 If candidate stops and is waiting for time to Seconds elapse, CUE: (Time Compression) Inform candidate that additional 34 minutes has passed Examiner can terminate JPM at this time Direct Watch Chemist to sample RCS boron Direct Watch concentration Chemist to sample 25 RCS for boron CUE: Acknowledge as Watch Chemist concentration Determine Determine if boration completed expected boration time completed OR 26 CUE: (Time Compression) Inform candidate required boron that additional 34 minutes has passed concentration achieved Rotate speed 27 Place boric acid transfer pumps to SLOW switch to slow position Rotate Makeup 28 Turn Makeup Control Switch to Stop Control Switch to Stop Rotate valve Open Boric Acid Storage Tank Recirculation 29 potentiometer to Valves to approximately 25%
25% JPM Complete File: 0040421601-5.doc Difficu Ity: 2 Time: 10 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
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 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
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 minutes Task Number: 0040420501 ONOP-CVCS-3 Simulator
Page 9 of 9 INITIAL CONDITIONS:
- 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 ONOP 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 minutes Task Number: 0130150501 ES-1 .3 Simulator
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 minutes Task Number: 0130150501 ES-1.3 Simulator
Transfer to Cold Leg Recirculation Page 3 of 10 INITIAL CONDITIONS:
- 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 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 minutes Task Number: 0130150501 ES-1 .3 Simulator
Transfer to Cold Leg Recirculation Page 4 of 10 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 Obtain correct procedure ES-1.3, Step 1 Caution and Note 2 Review Caution and Note prior to Step 1 reviewed Determine if transfer to Cold Leg Recirc is Verify both RWST required Low-Low Level 3 alarms LIT and VC CUE: Containment Level is trending up on Sump trending up Recorders LR-1253 and LR-1254 4 RESET SI Verfy SI reset Verify SI Actuated 5 Check SI RESET light extinguished VC Spray reset per 6 RESET Containment Spray initiating cue Place Recirc Sw #1 7 Align SI Recirc Switches #1 and #3 and #3 to ON 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-MOV Dispatch NPO to 8 894B,894D energize valves on MCC 36A and 36B 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 Dispatch NPO to 9 PAB, 73 ft. CUE: Acknowledge as NPO Verify Recirc Switch 10 Check status of Recirc Switch #1 #1 function complete light LIT File: 0130151601-1 .doc Difficulty: 4 Time: 20 minutes Task Number: 0130150501 ES-1.3 Simulator
Transfer to Cold Leg Recirculation Page 5 of 10 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Check status of Recirc Switch #3 NOTE: Function Complete light is not Verify Recirc Switch expected when candidate reaches this step.
#3 function complete This is due to time to energize valves 882 11 light LIT 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 RCS pressure Check RCS pressure less than intact SG 12 less than intact SG pressure pressure Place 31 I 33 ABFP 13 Stop both Motor Driven Auxiliary Feed pumps in PULLOUT Initiate performance of Attachment 1 CUE: Additional Team operator will perform parallel actions of Attachment 1 Direct performance 14 BOOTH OPERATOR: Verify 459,460,200 of Attachment 1 A,B, C closed, stop running Charging pump(s), place all Pressurizer heaters in OFF. Notify operator that Attachment 1 complete Dispatch NPO to Check status of SWN-FCV-1111 and 1112 verify SWN-FCV 15 CUE: FCV-1111 and 1112 are CLOSED 1111 and 1112 CLOSED Place Recirc Sw #2 16 Align SI Recirc Switch #2 to ON Verify Recirc Switch 17 Check status of Recirc Switch #2 #2 function complete light LIT Establish communications with PAB 73 ft. Request NPO to 18 CUE: Acknowledge as NPO standby CCW Hx's Check RHR Hx CCW Shutoff Valves OPEN. Verify 822 A and 19 CUE: Acknowledge as NPO 822B OPEN Observes 32 Recirc 20 Manually START 32 Recirc pump pump NOT running File: 0130151601-1 .doc Difficulty: 4 Time: 20 minutes Task Number: 0130150501 ES-1.3 Simulator
Transfer to Cold Leg Recirculation Page 6 of 10
& NOTES STANDARD S/U Observes 31 Recirc pump NOT running Verify Recirculation Trains not affected by sump blockage
- Low Head Injection Line Low Flow alarm Verify indications of 31 sump blockage do
- SI Pump Suction Low Pressure alarm NOT exist
- Indications of erratic / reduced flow
- Abnormal sum level indication Throttle to maintain Determine Minimum Core Recirculation 360 gpm on lowest Flowrate available indicator File: 0130151601-1.doc Difficulty: 4 Time: 20 minutes Task Number: 0130150501 ES-1.3 Simulator
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 minutes Task Number: 0130150501 ES-1 .3 Simulator
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 minutes Task Number: 0130150501 ES-1.3 Simulator
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 minutes Task Number: 0130150501 ES-1 .3 Simulator
Page 10 of 10 INITIAL CONDITIONS:
- 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. File: Task Number:
Respond to Pressurizer Controlling Pressure Channel Failure High Page 1 of 9 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Oa~: 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 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
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 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
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 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
Respond to Pressurizer Controlling Pressure Channel Failure High Page 4 of 9
- 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
- 1. Determine PRZR pressure not Identify Failure/Stabilize Plant NORMAL
.2.
- 2. Place PRZR pressure control in MANUAL Check All Control Systems
- Rod Control - Not Affected
- PRZR Level Control- Not Affected
- 3.
- MBFP Speed Control - Not Affected Check indications for
- SG Level Control- Not Affected all control systems
- 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 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
Respond to Pressurizer Controlling Pressure Channel Failure High Page 5 0 f 9 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Place Pressurizer Pressure Defeat Switch in Rotates Switch to DEFEAT 1 & 4 (Rack B-6)
- 9. DEFEAT 1 & 4 CUE: A spare operator will monitor the flight position panel Place Delta T Defeat Switch T/411A in Defeat Rotates Switch to 10.
Loop 1 (Rack B-8) Loop 1 position Rotates Switch to Place Pressurizer Pressure Recorder to
- 11. channel 2 or 3 channel 2 or 3 position Place Master
- 12. Return Heaters and Sprays to Auto Pressure Controller to auto Refer to Technical Specifications.
13. CUE: The CRS is reviewing Tech Specs
- 14. Observes Note before step Reviews Note Using Attachment 6 Table 1 Check Check Redundant Bistables for failed channel
- 15. Bistable Status lights NOT tripped extinguished (Panel SOF)
- 16. Observe NOTE before step Reviews Note Place the bistables to trip for failed channel in Rack Red A-4
- Loop 1 Overtemp Trip Places bistable trip
- 17.
- Loop 1 Hi Press Trip switches in the UP
- Loop 1 Lo Press Trip position
- Loop 1 Unblock SI
- Loop 1 SI Evaluator can terminate the JPM at this time Check all bistable status lights for failed Observes all status
- 18. instrument listed in Attachment 6 Table 3 lights illuminated illuminated File: 0100081601-1 Difficulty: 3 Time: 20 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
Respond to Pressurizer Controlling Pressure Channel Failure High Page 6 0 f 9 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U JPM Complete File: 0100081601-1 Difficulty: 3 Time: 20 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
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 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
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 minutes Task Number: 0100080501 3-AOP-INST-1 Simulator
Page 9 of 9 INITIAL CONDITIONS: The plant is at 100% Power INITIATING CUES: You are the ATe. File: 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. 104A Initiate a Bleed and Feed of the RCS (Alternate Path) 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. 104A Initiate a Bleed and Feed of the ReS (Alternate Path) Page 3 of 6 INITIATIAL CONDITIONS
- 1. A loss of feedwater has occurred.
- 2. Steps 1-4 of E-O are complete .
- 3. A transition to ES-O.1 was made at Step 4.
- 4. A transition to FR-H.1 was made due to a RED path on the Heat Sink CSF.
- 5. 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. 104A Initiate a Bleed and Feed of the ReS (Alternate Path) Page 4 of 6 ~ Denotes Critical Step STEP DESCRIPTIONS t CUES & NOTES STANDARD StU
- 1. Obtain correct procedure FR-H.1, Step 9
- 2. Review Caution prior to Step 9 Caution reviewed Step 9 Depress manual SI
. 3.
Manually actuate SI pushbuttons - both Step 10a Manually CLOSE
. 4.
Check all MISVs CLOSED all MSIVs Step 10b
- 5. TRIP all RCPs Check all RCPs STOPPED Observes Thermal Step 11 Barrier CCW Check RCP Seal Cooling Header Low Flow alarm clear and
- 6.
- Thermal Barrier CCW Header Low Flow 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.
Check Charging Pump Status available to pumps Step 12b Observes no
- 8. charging pumps Check Charging Pumps Running running Step 12b RNO (1) Rotate LCV-112B Align Charging to RWST switch to OPEN
. 9.
Open LCV-112B and LCV112C Close LCV-112C switch to CLOSE Step 12b RNO(3) Place controller in manual and adjust
- 10. Prepare all available charging pumps for start 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. 104A Initiate a Bleed and Feed of the ReS (Alternate Path) Page 5 0 f6 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Step 12c(2) Observes valve 11. Check 142 Fully Open fully open Step 12c(3) Observes valve is 12. Open 204B open Rotate breaker Step 12c(4) control switches to
- 13. Start all available charging pumps and increase START and speed speed to maximum controller to maximum Step 13a Observe all SI 14.
Check status of SI purnps pumps running Step 13b(1) Observe alarm
- 15. Verify Safeguard Valve Off-Normal Position clear alarm CLEAR Step 13b(2 & 3) Verify 1835A I B
- 16. and 1852A I B Verify BIT discharge and inlet valves OPEN OPEN Verify 856J I H I C I
- 17. Step 13b(4)
EOPEN Verify High Head Stop valves OPEN Step 14a Verify power to RC 10 Check power available to PORV block valves MOV-535 and 536 Step 14b Check MOV-535 11 Check both Pressurizer PORV Block Valves and 536 OPEN OPEN Step 14c PCV-455C and 456
.12 OPEN both Pressurizer PORVs OPEN Step 15 Observe 456 13 Verify adequate RCS bleed path CLOSED File: (JPM104A.doc) Difficulty: 4 Time: 20 minutes Parent Task # 0000130501 FR-H.1 REV: 2
JPM No. 104A Initiate a Bleed and Feed of the Res (Alternate Path) Pa 6 of 6 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 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. 104A Initiate a Bleed and Feed of the ReS (Alternate Path) 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
- 1. A loss of feedwater has occurred.
- 2. Steps 1-4 of E-O are complete.
- 3. A transition to ES-O.1 was made at Step 4.
- 6. A transition to FR-H.1 was made due to a RED path on the Heat Sink CSF.
- 7. 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.
o o
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 minutes Task Number: 0280010501 3 SOP-C8-7 Simulator
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 minutes Task Number: 0280010501 3 SOP-CB-7 . Simulator
Start a Hydrogen Recombiner Page 3 of 8 INITIAL CONDITIONS: A Large Break LOCA occurred 2 days ago. All actions of ES-1.4 Transfer to Hot Leg Recirculation have been complete. The Operating Crew Transitioned back to ES-1 .3, Transfer to Cold Leg Recirculation. Containment Hydrogen has slowly risen to 1.5% Current VC Pressure - 2 psig Pre-LOCA VC Pressure - 0 psig Pre-LOCA VC Temperature - 98°F 31, 32, and 35 Fan Cooler Units are in operation Offsite power is available 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 minutes Task Number: 0280010501 3 SOP-C8-7 Simulator
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 Energize 31 H2 Recombiner by placing Directs NPO to close breaker in ON the breaker for 31 H2 2.
Recombiner on CUE: NPO reports breaker closed MCC-36C Verify Control Power Available light is lit on Hydrogen Recombiner Panel Observes Control 3. Power Light CUE: Control Power White Light is Lit Verify Manual Heater Power Adjust Rotate potentiometer 4. potentiometer is set to 000 fully counterclockwise Verify Heater Mode Selector Switch is in Observes Switch in 5. Manual Manual Note the following
- Current VC Pressure
- Pre-LOCA VC Pressure
- Pre-LOCA VC Temperature
- 6. Record parameters CUE: If Simulating this ...IPM
- Current VC Pressure - 2 psig
- Pre-LOCA VC Pressure - psig a
- Pre-LOCA VC Temperature - 98°F Determine Pressure Correction Factor (Cp) Determine Cp 1.165
.7.
using Attachment 2 +/-.005 Enters 1.165 +/- .005
- 8. Record Cp on Attachment 4 on Attachment 4 Determine Determine Required Heater Power on
- 9. approximately 49.3 +/-
Attachment 4 (Cp X 42.3 KW) 0.3 KW File: 0280011601-1 .doc Difficulty: 3 Time: 15 minutes Task Number: 0280010501 3 SOP-C8-7 Simulator
Start a Hydrogen Recombiner Page 5 of 8 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Place Recombiner Control Switch in Start and Rotate Switch to Start Release
.10. and spring return to neutral CUE: Green Light OFF Red Light ON Slowly Adjust Manual Heater Power until 5 KW is indicated on Heater Power Meter and Hold Rotate potentiometer for 10 minutes
.11. clockwise observe heater power meter 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 Rotate potentiometer Hold for 10 minutes
'12 clockwise observe heater power meter CUE: Meter indicates 10 KW Time Com~ession 10 Minutes has elapsed Slowly Adjust Manual Heater Power until 20 KW is indicated on Heater Power Meter and Rotate potentiometer Hold for 5 minutes
.13. clockwise observe heater power meter CUE: Meter indicates 20 KW Time Compression 5 Minutes has elapsed Adjust Manual Heater Power as required to maintain Required Heater Power per Rotate potentiometer
.14 Attachment 4 clockwise observe heater power meter CUE: Meter indicates 49.3 KW JPM Complete File: 0280011601-1 .doc Difficulty: 3 Time: 15 minutes Task Number: 0280010501 3 SOP-C8-7 Simulator
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 minutes Task Number: 0280010501 3 SOP-C8-7 Simulator
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 minutes Task Number: 0280010501 3 SOP-CB-7 Simulator
Page 8 of 8 INITIAL CONDITIONS: A Large Break LOCA occurred 2 days ago. All actions of ES-1.4 Transfer to Hot Leg Recirculation have been complete. The Operating Crew Transitioned back to ES-1.3, Transfer to Cold Leg Recirculation. Containment Hydrogen has slowly risen to 1.5% Current VC Pressure - 2 psig Pre-LOCA VC Pressure - 0 psig Pre-LOCA VC Temperature - 98°F 31,32, and 35 Fan Cooler Units are in operation Offsite power is available INITIATING CUES: You are the BOP and the CRS has directed you to place the 31 Hydrogen Recombiner in service. File: Task Number:
I o , 0
Remove a Power Range Nuclear Instrument From Service Page 1 of 10 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Oa~: 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 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
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 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
Remove a Power Range Nuclear Instrument From Service Page 3 of 10 INITIAL CONDITIONS The plant is operating at 100% power. Power Range Channel N41 is operating erratically. The Shift Manager has declared N41 inoperable. INITIATING 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 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
Remove a Power Range Nuclear Instrument From Service Page 4 of 10
- 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 Obtain Correct Procedure Select Attachment 2.
1
- 3. Circle selected channel Circles N41 If removing channel from service due to partial failure obtain guidance from I&C and Reactor Engineering.
4. CUE: Channel is NOT being removed from service due to partial failure Place Dropped Rod Mode Selector Switch in BYPASS 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 illuminated
- NIS Trip Bypass alarm on Panel SBF-1 is annunciated Nuclear Instrumentation Drawer N41A Place applicable Rod Stop Bypass switch in
.-6. BYPASS PR N41 Rotate Switch to N41 Position Nuclear Instrumentation Drawer N50 Place applicable Power Range Channel Percent Power Computer Input Out of Limit
- 7. Check CUE: The STA will remove channel from limit check Observe Warning Caution and Notes Reviews Warning 8.
Caution and Notes CUE: The CRS is reviewing Tech Specs. File: 0150021601-1 .doc Difficulty: 2 Time: 25 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
Remove a Power Range Nuclear Instrument From Service Page 5 of 10 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U 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 Screw bolt in to
.9.
engage relay NOTE Blocking strips are installed CUE: Blocking Strips have been Independently Verified Defeat selected channel ~ T signal by placing the delta T Defeat Switch in Defeat Channel 1 Rotate Switch to
.10.
Defeat Ch 1 Rack 8*8 Rotate recorder Verify ~ T Recorder selected to unselected 11 . switch to channel 2, channel 3,or4
- 12. Observe caution Review Caution NA the Selected Check the Overtemperature ~ T bistables for Channel and Checks
- 13. the unselected channels are extinguished on the remaining Panel SOF channels extinguished
- 14. Observe Note Reviews Note Place the Overtemperature ~ T bistable for Places trip switch in
.15. Loop 1 Over Temp Trip in the tripped position the up position RackA-4 Check Overtemperature ~ T bistable for Loop 1 Observes light
- 16. Over Temp Trip is lit illuminated Panel SOF Grid A-11 Check Overtemp ~T Channel Trip or Rod Stop Observes 17.
alarm lit on Panel SAF annunciator lit Verify Rod Control Mode Selector Switch is in Observes Switch is in 18. Manual Manual Place Power Mismatch Bypass Switch in Rotates Switch to
.19. PYBASS PR N41 N41 position Nuclear Instrumentation Drawer N50 File: 0150021601-1 .doc Difficulty: 2 Time: 25 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
Remove a Power Range Nuclear Instrument From Service Page 6 of 10 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U When a minimum of two minutes has elapsed, Rotates Rod Control Return Rod Control to Automatic
- 20. Mode Selector Switch CUE: Time Compression 2 minutes has to Automatic elapsed Place Detector Current Comparator Upper Rotates switch to
.21. Section Switch in PR N41 Bypass PRN41 Nuclear Instrumentation Drawer N50 position Place Detector Current Comparator Lower Rotates switch to
- 22. Section Switch in PR N41 Bypass PRN41 Nuclear Instrumentation Drawer N50 position Place Comparator Channel Defeat Switch to 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 flux trip bistables are tripped on Bistable Status 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 tri~ are blocked
- 27. Observe NOTES Reviews Notes Trip all NIS bistables associated with the selected channel by removing both instrument tJl28. Removes fuses and control power fuses Nuclear Instrumentation Drawer N41A1B Check alarms on Panel SBF-1
- NIS Power Range Loss of Detector
- 29. Voltage Observes alarms lit
- NIS Poser Range Single Channel High Range Trip Determine Overpower Low Range High Flux Given Power greater 30.
Trips are blocked than 25% Check Overpower High Range Hi Flux Trip 31 . bistable for N41 is lit 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 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
Remove a Power Range Nuclear Instrument From Service Page 7 of 10 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Rotate switch to Verify NR-45 Recorder selected to an
- 33. Channel 2, 3, or 4 if unselected channel necessary J PM Complete File: 0150021601-1 .doc Difficulty: 2 Time: 25 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
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 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
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 minutes Task Number: 0150020501 3-S0P-NI-001 Simulator
Page 10 of 10 INITIAL CONDITIONS The plant is operating at 100% power. Power Range Channel N41 is operating erratically. The Shift Manager has declared N41 inoperable. INITIATING CUES: You are the BOP and the CRS has directed you to remove channel N41 from sevice File: Task Number:
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 minutes Task Number: 0730160101 3-S0P-RM-008 Simulator
Reset R-18 Alarm Setpoint using the RM-23A Module Page 2 of 8 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: Simulator Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: Actual Time: - - -
References:
3-S0P-RM-008 Radiation Monitor Control Cabinet (Bantam 11/RM-23A Cabinet File: 0730161601-1 .doc Difficulty: 3 Time: 10 minutes Task Number: 0730160101 3-S0P-RM-008 Simulator
Reset R-18 Alarm Setpoint using the RM-23A Module Page 3 of 8 INITIAL CONDITIONS Preparations are underway to release 31 Monitor Tank The current alarm setpoint for R-18 is 4.0 X 10-4IJCilml 3 The calculated alarm setpoint for the release is 1.25 X 10- IJCi/ml The Bantam 11 Control Cabinet is OOS for maintenance. The CRS has reviewed 3- SOP-RM-01 0 and the setpoint change is acceptable. The Radiation Monitor Supervisory Key is at location 58 in the Key Rack. INITIATING CUES: You are the BOP and the CRS has directed you to reset the Alarm setpoint for R 3 18 to 1.25 X 10- 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 minutes Task Number: 0730160101 3-S0P-RM-008 Simulator
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
- 1. Commence evaluation Determine NOT changing R-1 or R-33 Given in initial 2.
Setpoint conditions Depresses R18 LlQ
.3. Depress Channel button on RM-23A Insert key and turn Norm Supervisor switch to Insert Key and rotate
.~.
Supervisor switch to Supervisor Observes SUPV
- 5. Verify SUPV Mode LED is ON Mode LED ON Enter a a 9 using
- 6. If changing High Alarm set point ENTER 009 keypad Determine NOT changing Alert set point at this 7.
time Depresses ITEM Depress ITEM and verify current setpoint is
- 8. button and observes displays digital dis~ay_
Enter new set point using the following format Enters data in stated
.9.
[1] [2] [5] [-] [0] [3] format Observes digital Verify desired value is displayed then depress
.10. display correct then ENTER key presses ENTER key If value displayed is not correct press If value displayed is not correct, depress CLEAR button and
- 11. CLEAR button and repeat procedure step re-perform J PM 4.3.5.4 starting at JPM step 3
File: 0730161601-1.doc Difficulty: 3 Time: 10 minutes Task Number: 0730160101 3-S0P-RM-008 Simulator
Reset R-18 Alarm Setpoint using the RM-23A Module Page 5 of 8 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Turn Normal Supervisory Key Switch to Rotate key to NORM 11. NORMAL and remove key and remove Depress desired channel button to return Depress R18 UQ 12 display to normal button IF RM-23A alarm set point was changed Verify Observes LED is 13 Supv Mode LED is OFF OFF JPM is Complete File: 0730161601-1 .doc Difficulty: 3 Time: 10 minutes Task Number: 0730160101 3-S0P-RM-008 Simulator
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 minutes Task Number: 0730160101 3-S0P-RM-008 Simulator
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 minutes Task Number: 0730160101 3-S0P-RM-008 Simulator
Page 8 of 8 INITIAL CONDITIONS Preparations are underway to release 31 Monitor Tank 4 The current alarm setpoint for R-18 is 4.0 X 10- !-ICi/ml 3 The calculated alarm setpoint for the release is 1.25 X 10- !-ICi/ml The Bantam 11 Control Cabinet is OOS for maintenance. The CRS has reviewed 3- SOP-RM-01 0 and the setpoint change is acceptable. The Radiation Monitor Supervisory Key is at location 58 in the Key Rack. INITIATING CUES: You are the BOP and the CRS has directed you to reset the Alarm setpoint for R 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. File: Task Number:
o 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 minutes Task Number: 0800020201 3-S0P-EL-005 Simulator
Transfer Buses 1 - 4 to the Station Aux Transformer Page 2 of 9 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: Simulator Actual Testing Environment: Alternate Path: NO Time Critical: NO Estimated Time: 15 Min Actual Time: - - -
References:
3-S0P-EL-005 Operation of On-Site Power Sources File: 0800031601-1 .doc Difficulty: 2 Time: 15 minutes Task Number: 0800020201 3-SOP-EL-005 Simulator
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 minutes Task Number: 0800020201 3-S0P-EL-005 Simulator
Transfer Buses 1 - 4 to the Station Aux Transformer Page 4 of 9 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. Observe NOTES before step 4.4.1 Reviews Notes Observe Meters; Adjusts MTG Voltage, Unit Aux or Ensure less than 100 volts difference between
- 3. Station Aux Station and Unit Auxiliary Transformers Transformer Tap Changers if necessary If desired to transfer 6.9 KV Bus 1 to the Determine transfer is Station Aux Transformer desired Observe Station Aux and Unit Aux
- 4. Perform Voltage Check per step 4.4 .1 transformer voltage meters Places handle in Place 6900 Bus 1 Synchroscope in Bus 1 Bus switch location and 5.
5 position rotate switch to bus 1 bus 5position Rotate Switch to If Synchroscope is at 12 o'clock then Close the
- 6. Close then release to Bus No. 1-5 Tie Breaker auto Rotate Switch to
** Open 6900 Bus 1 Normal Feed Breaker Open the release to auto
- 8. Place 6900 Bus No. 1 Synchroscope in Off Rotate switch to Off Observe meter Ensure less than 2000 amps on 6900 KV bus
- 9. determines < 2000 5
amps File: 0800031601-1.doc Difficulty: 2 Time: 15 minutes Task Number: 0800020201 3-S0P-EL-005 Simulator
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 Determine transfer is Station Aux Transformer desired Observes breaker
- 10. Ensure both 2A-3A Tie breaker is Open Open Observe Station Aux and UnitAux 11 . Perform Voltage Check per step 4.4 .1 transformer voltage meters Places handle in Place 6900 Bus 2 Synchroscope in Bus 2 Bus switch location and
. 12.
5 position rotate switch to bus 1 bus 5 position Rotate Switch to If Synchroscope is at 12 o'clock then Close the
- 13. Close then release to Bus No. 2-5 Tie Breaker auto Rotate Switch to
. 14. Open 6900 Bus 2 Normal Feed Breaker Open the release to auto
- 15. Place 6900 Bus No.2 Synchroscope in Off Rotate switch to Off Observe meter Ensure less than 2000 amps on 6900 KV bus
- 16. determines < 2000 5
amps If desired to transfer 6.9 KV Bus 3 to the Determine transfer is Station Aux Transformer desired Observes breaker
- 17. Ensure both 2A-3A Tie breaker is Open Open Observe Station Aux and Unit Aux
- 18. Perform Voltage Check per step 4.4.1 transformer voltage meters Places handle in Place 6900 Bus 3 Synchroscope in Bus 3 Bus switch location and
. 19.
6 position rotate switch to bus 1 bus 5 position Rotate Switch to If Synchroscope is at 12 o'clock then Close the
. 20. Close then release to Bus No. 3-6 Tie Breaker auto File: 0800031601-1 .doc Difficulty: 2 Time: 15 minutes Task Number: 0800020201 3-S0P-EL-005 Simulator
Transfer Buses 1 - 4 to the Station Aux Transformer Page 6 of 9 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU Rotate Switch to
. 21. Open 6900 Bus 3 Normal Feed Breaker Open the release to auto 22 . Place 6900 Bus NO.3 Synchroscope in Off Rotate switch to Off Observe meter Ensure less than 2000 amps on 6900 KV bus
- 23. determines < 2000 6
amps If desired to transfer 6.9 KV Bus 4 to the Determine transfer is Station Aux Transformer desired Observe Station Aux and Unit Aux 24 . Perform Voltage Check per step 4.4.1 transformer voltage meters Places handle in Place 6900 Bus 4 Synchroscope in Bus 4 Bus switch location and
.25.
6 position rotate switch to bus 1 bus 5 position Rotate Switch to If Synchroscope is at 12 o'clock then Close the
- 26. Close then release to Bus No. 4-6 Tie Breaker auto Rotate Switch to
. i27. Open 6900 Bus 4 Normal Feed Breaker Open the release to auto
- 28. Place 6900 Bus NO. 4 Synchroscope in Off Rotate switch to Off Observe meter Ensure less than 2000 amps on 6900 KV bus
- 29. determines < 2000 6
amps Ensure both tap When transfer complete, ensure Unit Aux and
- 30. changer switches are Station Aux Tap Changers are in automatic pulled out JPM is complete File: 0800031601-1.doc Difficulty: 2 Time: 15 minutes Task Number: 0800020201 3-S0P-EL-005 Simulator
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 minutes Task Number: 0800020201 3-S0P-EL-005 Simulator
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 minutes Task Number: 0800020201 3-S0P-EL-005 Simulator
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. File: Task Number:
o 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 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
Locally Start 32 Aux Boiler Feedpump Page 2 of 9 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 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
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 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
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 3-S0P-ESP-001,
- 1. Obtain correct procedure section 4.1.8 Step 4.1.8.4 Determine if MS-PCV-1310A, 32 ABFP Steam Observes valve
- 2. Supply Isolation valve, is OPEN stem limit switch position CUE: Valve is OPEN Close Air Supply Valve and break a Step 4.1 .8.5 .a
- 3. fitting between the Isolate Air supply and bleed off at fitting at 131 OA isolation valve and 1310A actuator Determine if MS-PCV-1310B, 32 ABFP steam Observes valve
- 4. Supply Isolation valve, is OPEN stem limit switch position CUE: Valve is OPEN Close Air Supply Valve and break a Step 4.1.8.6.a
- 5. fitting between the Isolate Air supply and bleed off at fitting at 131 OA isolation valve and 1310B actuator Step 4.1.8.7 If directed to use handwheels to control FCVs then rotate applicable FCV handwheels in the closed direction
- 6. NOTE: The candidate will demonstrate how to See Below control FCVs on one valve CUE: You are directed to control the FCVs using the handwheels. Demonstrate how this is done on FCV-405A File: 0610011604-1 .doc Difficulty: 3 Time: 30 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
Locally Start 32 Aux Boiler Feedpump Page 5 of 9 STEP DESCRIPTIONS / CUES & NOTES STANDARD S/U Step 4.1.8.7.a Rotate handwheel in the closed direction until Rotate handwheel
.7. handwheel engages diaphragm or valve fully in the close closed direction CUE: Valve indicates closed Step 4.1.8.7.b.1 Rotates valve in .S. Close IA 1675 (IA-PCV-1551 IA Isolation Valve) close direction CUE: Valve indicates closed Step 4.1.8.7.b.2 Bleed off air using petcock of IA-PCV-1551 Rotate petcock
- 9. regulator counter clockwise CUE: Petcock open air heard venting Step 4.1 .8.7.b.3 10.
Control FCV position using handwheel Step 4.1.8.8.a ADJUST HCV-1118 32 ABFP Turbine Speed CLOSE MS-HCV Control manual handwheel for idle speed
.11. 1118 using manual handwheel CUE: Handwheel in close position Step 4.1.8.8.b CLOSE IA-865 32 ABFP MS-HCV-1118
- 12. Instrument Air Isolation valve CLOSE IA-865 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 Remove cap and
.13.
OPEN 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" Manual handwheel
.14. adjusted until valve CUE: Valve open 1/8" stem -1/8" OPEN NOTE: 1/8" is the first scribe mark on the indicator Step 4.1 .8.9 Rotate 32 ABFP Place 32 ABFP Trip/Auto/On local control switch Trip/Auto/On local .15.
to ON control switch to CUE: Turbine heard increasing speed of pump ON File: 0610011604-1.doc Difficulty: 3 Time: 30 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
Locally Start 32 Aux Boiler Feedpump Page 6 of 9 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 Observes 32 ABFP CUE: Steam Inlet pressure indicates 250 psig discharge pressure 17.
gauge NOT NOTE: There are two locations for steam inlet indicating 600 psig 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 Rotate handle until pressure to match the instrument loading pressure pressure indicates
.18. (do not exceed 13 psig) approximately 5 psig CUE: Instrument Loading Pressure indicates 5 psig (Left Hand Meter)
Step 4.1.8.10.a.2 Switch rotated to
.19. Tum the AutolManual switch on the PCV-1139 Manual AIM station to MANUAL Step 4.1.8.1 0.a.3 Slowly adjust PC-1139 AM Station Manual loading Rotate knob until .20. pressure to approximately 12 psig indicator 12 psig CUE: Indicator reads 12 psig Step 4.1.8.10.a.4 Observe inlet Adjust PC-1139 AIM station Manual Loading pressure .21 . pressure to maintain steam inlet pressure to 32 approximately 600 Aux Boiler Feed Pump turbine at approximately psig 600 psig NOTE to evaluator Step 4.1.8.10.b (Manual operation of PCV-1139) is Not Applicable Step 4.1.8.11 Adjust turbine speed using HCV-1118 until Observes discharge .22. discharge pressure is 1000 psig pressure approximately 1000 CUE: Discharge Fressure indicates 1000 psig Inform SM 32 ABFP discharge pressure is 1000 psig 18 SM Informed CUE: SM acknowledges File: 0610011604-1.doc Difficulty: 3 Time: 30 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
Locally Start 32 Aux Boiler Feedpump Page 7 of 9 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU JPM Complete File: 0610011604-1.doc Difficulty: 3 Time: 30 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
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 minutes Task Number: 0610010404 3-S0P-ESP-1 In Plant
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 File: Task Number:
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 minutes Task Number: 0840280504 . 3-S0P-EL-12 In Plant
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 minutes Task Number: 0840280504 3-S0P-EL-12 In Plant
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 minutes Task Number: 0840280504 3-S0P-EL-12 In Plant
Start 32 CCW Pump from MCC312A Page 4 of 7
- 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 MCC-A feeder OR Remove load from Bus 312 per Attachment 1 MCC-C feeder 2.
OR CUE: MCC-A, C or E-1 feeder breaker open MCC-E-1 feeder open Visually verify 32 CCW pump is not running Direct Nuclear NPO 3 to verify pump is not CUE: Nuclear NPO reports 32 CCW running pump is not running Verify 32 CCW Pumps transfer switch is de-Direct Nuclear NPO energized to verify all eight 4. indicating lights are CUE: Nuclear NPO reports all 8 lights are off extinguished Caution and Note
- 5. Review Caution and Note reviewed Unlock and place 32 CCW pump alternate feed transfer switch in Alternate feed position Direct Nuclear NPO QUESTION: Ask candidate to describe the to rotate disconnect location of the Alternate Feed Transfer
.6 switch 360 0 to Switch and how to operate it.
alternate feed position CUE: Nuclear NPO reports transfer switch rotated clockwise 360 0 to Alternate Feed position Unlock and place disconnect switch on MCC
.7 312A for 32 CCW pump to on Unlock and place disconnect switch to on CUE: Disconnect switch is on File: 0840281604-1.doc Difficulty: 2 Time: 10 minutes Task Number: 0840280504 3-S0P-EL-12 In Plant
Start 32 CCW Pump from MCC312A Page 5 of 7 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Start 32 CCW pump Push in and turn key
.8 switch to start CUE: Key switch in start position position Verify 32 CCW pump is running Observe red running 9
light illuminates CUE: Red running light is illuminated JPM Complete File: 0840281604-1.doc Difficulty: 2 Time: 10 minutes Task Number: 0840280504 3-S0P-EL-12 In Plant
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 minutes Task Number: 0840280504 3-S0P-EL-12 In Plant
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 File: Task Number
Perform Local Containment Isolation Valve Lineup IVSW Page 1 of 7 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Name: Employee 10 #: Evaluator: Oa~: 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 minutes Task Number: 3-S0P-CB-11 In Plant
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 minutes Task Number: 3-S0P-C8-11 In Plant
Perform Local Containment Isolation Valve Lineup IVSW Page 3 of 7 INITIAL CONDITIONS: The plant experienced a Large Break LOCA. The operating crew is in 3-ES-1.3, Transfer to Cold Leg Recirculation Internal Recirculation is established. All RCPs are stopped. INITIATING CUES: You are the Nuc Side NPO and the CRS has directed you to perform 3-S0P-CB 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 minutes Task Number: 3-S0P-C8-11 In Plant
Perform Local Containment Isolation Valve Lineup IVSW Page 4 of 7 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. Observe Note before Step 1 Observes Note Open IV-1492 Manual N2 IVSW Header Isolation PAB 41' behind Heat Trace Panel Locates and Opens
.3.
Valve Give candidate COL-C8-004 Isolation Valve Seal Water System if requested to locate valves Open IV-1493 Manual Seal Water Header Isolation Locates and Opens
~.
Valve PAB 41' behind Heat Trace Panel Open IV-1443 Manual N2 Header IV-PCV 1090 Outlet Isolation Locates and Opens 5. Valve N2 Bottle Bank 55' PAB Close SI-859A Accumulator Drain/Safety Injection Test Line Isolation 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 Off List when requested 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 minutes Task Number: 3-S0P-C8-11 In Plant
Perform Local Containment Isolation Valve Lineup IVSW Page 5 of 7 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Close SA-24-2 Station Air to Containment Verified Closed Using 9. Containment Isolation Valve COL 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 Locate and Observe Isolation Breakers Closed
- 10.
- CH-MOV-442 32 RCP Seal Injection If necessary Isolation Simulate Closing
- CH-MOV-443 33 RCP Seal Injection Breakers Isolation
- CH-MOV-444 34 RCP Seal Injection Isolation
- SI-MOV-885A Containment Sump RHR Suction 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 Locate and Observe Isolation Breakers Closed
. 11.
- CH-MOV-250C 33 RCP Seal Injection If necessary Isolation Simulate Closing
- CH-MOV-250D 34 RCP Seal Injection Breakers Isolation
- SI-MOV-882, RHR Pump RWST Suction Isolation
- SI-MOV-885B Containment Sump RHR Suction JPM Complete File: Difficulty: 3 Time: 20 minutes Task Number: 3-S0P-C8-11 In Plant
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 minutes Task Number: 3-S0P-C8-11 In Plant
Page 7 of 7 INITIAL CONDITIONS: The plant experienced a Large Break LOCA. The operating crew is in 3-ES-1 .3, Transfer to Cold Leg Recirculation Internal Recirculation is established. All RCPs are stopped . INITIATING CUES: You are the Nuc Side NPO and the CRS has directed you to perform 3-S0P-CB 11 Attachment 1 steps 1-5 Containment Isolation Valves Local Lineup. File: Task Number:
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 Malf. No. Event Event No. Type* Description 1 N/A R(ATC) Perform power ascension. N(BOP) N(CRS) 2 MAL I(ALL) Controlling PZR level instrument fails low causing letdown to PRS006 isolate. Channel is defeated and letdown is restored. B TS(CRS) 3 MAL C(ALL) Letdown leak inside containment. Leak will be isolated. CVC003 TS(CRS) 4 MAL C(ALL) 480V Bus 6A fault. EPS005 D 5 MAL M(ALL) Sequential loss of Main Feedwater Pumps leading to plant trip. ATS004 PORV fails open, cannot be isolated. AlB PRSOO3 D 6 MAL C(CRS) 31 and 32 Safety Injection Pumps will not auto-start. (Neither SIS004A board operator credited since either one may start pump.) IB 7 MAL C(ALL) Station Blackout when Containment Phase A is reset. EPS001
* (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 auto 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
Simulator Setup and Instructor Directions INSTRUCTOR Setup/Event Expected response/instructor cues ACTIONS IC Reset Reset Simulator to 46% power IC SES Setup Run setup schedule (U3 Loads LT -460 fails low on trigger 2 Batch File 2010 Scenario 1) and Loads letdown leak inside VC on verify malfunctions and trigger 3 over-rides have been Loads 6A fault on trigger 4 entered. 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. HANG PROTECTED EQUIPMENT tags for: Update the Protected 32 and 33 EDG Equipment PC. PTO 31 EDG Risk is Yellow Event 1 Power Ascension Make notifications as requested by team. Event 2 Click the Trigger 2 LT -460 fails low w/o ramp or delay button MAL-PRS006B at lead evaluator direction. Role Play If I&C requested to Inform team that a troubleshooting investigate: package is being developed. Event 3 Click the Trigger 3 Letdown leak in VC w/o ramp or delay button MAL-CVC003 at lead evaluator direction. Role Play When called to support Open/adjust 33 charging pump recirc Excess Letdown valve Event 4 Click the Trigger 4 Fault on Bus 6A w/o ramp or delay button at lead evaluator MAL-EPS005D direction 2010 IP3 NRC Exam Scenario 1 Page 30f 13
Simulator Setup and Instructor Directions INSTRUCTOR Setup/Event Expected response/instructor cues ACTIONS Role Play If asked to investigate Bus has smell of ozone and probably Bus 6A tripped on actual fault. More troubleshooting will be required. Event 5 Click the Trigger 5 MBFPs trip sequentially button 31 trips on trigger MAL-ATS004A at lead evaluator 32 trips with 60 second delay MAL direction 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 immediate 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. II 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 0 Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Page 1 of 1 Event
Description:
Sequential loss of Main Feedwater Pumps leading to plant trip. Time Position Applicant's Actions or Behavior BOP/ATC Diagnose loss of first MBFP based on alarm and pump indication CRS Direct team to perform immediate operator actions of AOP-FW-1, Loss of Feedwater BOP/ATC Diagnose loss of second MBFP ATC Trips the reactor CRS 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 open ATC Verifies turbine trip based on stop valve indication BOP 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 1 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 ste~ 8 of e-o.
BOP 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)
CRS/ATC 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 ATC 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 Applicant's Actions or Behavior CREW Diagnose Loss of Offsite Power CRS Enters LOOP-1 Loss of Offsite Power after SI Reset
- 'i:;"
BOP Critical Task 3: Starts 34 SWP before 33 EDG trJPa due fD .......~ ..... " BOP Places all CCW Pumps in trip pullout ATC/BOP Starts 31 SI Pump (failure to do this constitutes failure of Critical Task) ATC/BOP Starts 31 and 33 Fan Cooler Units ATC/BOP Establishes AFW flow to 31 and 32 SG from 32 AFW pump ATC Start 31 Charging Pump CRS/ATC Back in E-O determine need to transition to E-1 for stuck open PORV Lead Evaluator 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 Information Date/Time: Today/Now Condition: Power Ops
% Power: 46%
Xenon: Equilibrium RCS Boron: 1222 ppm Rod Position CB D 173 steps 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 I-lCi/cc Risk Assessment: Yellow Plant Equipment Status: 31 EDG is OOS for oil system modification. Instructions: Return unit to 100% at 10% per hour. 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 Malf. Event Event No. No. Type* Description 1 N/A R(ATC) Perform power ascension . N(CRS) N(BOP) 2 XMT I(ALL) 32 SG Pressure Channel Failure causing ADV to open. 040A TS(CRS) 3 MAL C(CRS) 31 CCW Pump trips and 32 CCW fails to auto-start. CCWOO 1NB C(BOP) TS(CRS) 4 MAL TS(CRS) CCW leak at 31 CCW Pump . Can be isolated CCWOO 5A 5 MAL C(CRS) Main Steam header break with no MSIVs auto-closing and 1 MSIV MSS009 failing open. A C(ATC) 6 MAL M(ALL) Failure of the Reactor to trip both Auto and Manual. Team will RPS002 emergency borate and manually insert control rods. NB 7 MAL C(BOP) Containment Sump Pump Isolation Valves fail to close requiring CNM001 manual action. 12
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2010 IP3 NRC Exam Scenario 2 Page 10f 16
Session Outline: The evaluation beg ins 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 (PT 429C) will occur. This 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 will fail 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 ing . 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
Simulator Setup and Instructor Directions EXPECTED RESPONSE/INSTRUCTOR Setup/Event INSTRUCTOR ACTIONS CUES IC Reset Reset Simulator to 5% power IC (IC-50) SES Setup Load setup Schedule Holds off 31 Charging pump Schedule file (U3 2010 Scenario Inserts failure of 1723/1728 to close (simulated) File and events to remove failures when switches
- 2) placed in closed.
Loads Rx trip breakers failure to auto-open Loads Rx trip breakers failure to manually open Transfer Actions to the (from CCR) Director Loads 32 SG Press Channel C Failure on Event Verify malfunctions I 1 overrides entered 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 Place cIs in TPO and hang Danger tag for: Distribute turnover sheets 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 32 SG Pressure Channel C will fail high wlo ramp or delay MAL SGN002F to 1400 At lead evaluator direction Role Play If NPO sent to Nothing unusual at transmitter. investigate Role Play If I&C ask to A troubleshooting package is being developed. investigate. Event 3 Actuate Event 3 31 CCW Pump trips and 32 fails to autostart. MAL-CCW001 B to failure to autostart at setup MAL-CCW001A to trip At lead evaluator direction 2010 IP3 NRC Exam Scenario 2 Page 30f 16
Simulator Setup and Instructor Directions EXPECTED RESPONSE/INSTRUCTOR Setup/Event INSTRUCTOR ACTIONS CUES Role Play If NPO sent to Indications are that 31 CCW Pump breaker investigate tripped on overcurrent. Motor is hot and smells like winding damage may have occurred. Event 4 Actuate Event 4 CCW Leak at 31 HX (will be reported as from 31 CCW seal) MAL-CCW005A to 500 with 120s ramp At lead evaluator direction Role Play If NPO sent to After NPO dispatched to locate leak, wait investigate 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 MAL 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 OPEN CCW makeup valves: makeup to CCW: LOA RMW012, 1 PW-831A LOA RMW013, 1 PW-831 B Role Play If NPO dispatched to Operate valves as requested: split headers: NOTE: 832A I 764A not modeled LOA CCWOO7 766A LOA CCWOO8 766B LOA CCW035 766C LOA CCW036 7660 LOA CCW015 759C LOA CCW016 7590 EventS Activate Event 5 Inserts Steam Break in Turbine Building on East Header at 100,000 Ib/hr ramped over 300 seconds . At lead evaluator direction MAL-MSS009A to 100000 with 300s ramp 2010 IP3 NRC Exam Scenario 2 Page 40f 16
Simulator Setup and Instructor Directions EXPECTED RESPONSE/INSTRUCTOR Setup/Event INSTRUCTOR ACTIONS CUES NOTE: MAL MSSOO9A If the Team delays, increase the size of the steam break until the Team Trips the As directed by lead Rx. evaluator Role Play After the Team Call as the NPO to the CCR and report diagnoses the steam there is a lot of steam in the Turbine break Building and appears to be from the 33' elevation. Role Play If asked to locally close NPO is unable to close 34 MSIVs. It 34 MSIVs in the ABFP appears to stuck open. building Event 6 ATWS Rx trip breakers fail to open from the CCR. They will open when tripped open Entered in Setup locally by the NPO Role Play When NPO sent to Wait until Emergency Boration is locally open Rx Trip commenced before locally opening Breakers reactor trip breakers Delete reactor trip MAL-RPSOO2A RTBs fail to open breaker malfunctions (auto) MAL-RPSOO2B RTBs fail to open (manual) Role Play When NPO dispatched 241A LOA-CVCOO7 to isolate seal injection 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 . Time Position Applicant's Actions or Behavior CREW Diagnose steam break downstream of MSIVs:
- Noise
- Steam flow increase all channels
- T avg lowering
- Turbine power lowering
- Reactor power increasing CRS May enter AOP-UC-1 or may just give order to:
- Trip the reactor
- Then close MSIVs ATC Will attempt to trip reactor Note:
At this point actions will be tracked on D-2 for Events 6 and 7 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. Time Position Applicant's Actions or Behavior CRS Instruct team to perform immediate operator actions of FR-S1 ATC Will insert control rods BOP Will trip the turbine BOP Direct NPO to locally trip the reactor BOP Will establish greater than 686 gpm AFW flow BOP/ATC Critical Task 1: EstablIsh EtntirgEmCY. Boration as follows: (prior to ~ step f ofFR . S1): Check charging pump running Open MOV-333 .:: Cla$e. HCV-1M and 105 Sfait bolt BATPa mfast ..... :'~'.
- 1~CJ'uqIi1g~~.~
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. Time Position A licant's Actions or Behavior BOP 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 Return to E-O ATC If not alread done, close MSIVs - 34 will not close CRS/ATC Perform E-O actions:
- Verify reactor trip
- Verify turbine trip
- Verify power to 480V busses
- Verify 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):
- Verifies 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 Information 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 ~Ci/cc 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. 3 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 XMT I(ALL) VCT level instrument fails low. CVC049 2 MAL C(ALL) 33 Charging Pump Trip. CVC005C TS(CRS) 3 MAL 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 MAL M(ALL) SGTL becomes SGTR. PORV and Instrument Air to VC Valve SGN005C failures will lead to loss of pressure control. MAL PRS003D SWI AIR002C 6 MAL C(CRS) 33 AFW Pump fails to auto-start. CFW001C C(ATC) 7 MAL 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 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> 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 will trip the Reactor and initiate SI. 33 AFW pump will fail to auto 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 AOP-SG-1, E-O, E-3, ECA-3.3 J 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 3 Page 20f 16
Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSEIINSTRUCTOR CUES Ie Reset Ie 11 Reset Simulator for proper IC SES Setup Deenergizes 31 ABFP Schedule File VerifY malfunctions / overrides Deenergize PCV-455C & Block Valve 535 entered 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 Perfonn setup checklist Ensure 33 Charging pump is in service Place cis in TPO and hang Danger tag for: Distribute turnover sheets 31 ABFP Ensure Rx Vessel Head Vent Place PORV 455C in Closed valve fuses are available in ATC 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 At lead evaluator i /nsert maljimction XMT- I LT-112fails [ 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 l
~
At lead evaluator Insert malfunction MAL- CHARGING 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 At lead evaluator ! /nsert malfunction MAL- STEAM SGN005C to 0.005 on GENERATOR 33 direction j event 3 TUBE LEAK Event #5 Click the Event 5 button SOTR on 33 S/O 400 gpm ramped in 10 min. At lead evaluator I Insert malfunction MAL-SGN005C to 20.00 on STEAM GENERATOR 33 direction I event 5 TUBE LEAK Role Play At CCR request Perform various LOA's per NPO local task list Role Play 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 0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: ~ Event No.: _1_ 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 3 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 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> 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 Note: Actions will continue on Event 4 D-2 2010 IP3 NRC Exam Scenario 3 Page 80f 16
Appendix D Required Operator Actions Form ES-D-2 Op-Test No. : _1_ Scenario No.: ~ Event No.: ~ Page _1_of -.1 Event Description : Tech Spec Shutdown Time Position Applicant's Actions or Behavior ATC Develops reactivity plan using reactivity summary sheet CRS Uses POP-2.1 attachment for load reduction Note:
- Team may use ONOP-TG-3, Rapid Shutdown
- If requested , notifications will be made for CRS by personnel outside the control room .
CREW Hold reactivity briefing. ATC 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.
BOP Peer checks boration BOP Begins load reduction using the MTG Governor ATC Peer Checks MTG Governor manipulations Lead Evaluator When sufficient actions for shutdown are observed instruct booth to insert Event 5 2010 IP3 NRC Exam Scenario 3 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 ~ain 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 D 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 Time Position Applicant's Actions or Behavior ATC/BOP CrItIcal Task 1: EstabUlttat least 385 gpm AFWftow (~8GBg Yllllbe es1ab1lshed): Start 33 AfW Pump whi£h.wiU feed 33' ~ SG8
- Increaae" on 32 AFW Pump
- fnJtfate~tQ31 aiId:32 SGa ftdm 32/i#W Piilm~ .~
BOP Will perform RO-1 , BOP Operator Actions during EOPs:
- 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 3 Page 120f 16
Appendix D Required Operator Actions Form ES-D-2 CRS/ATC Perform E-O diagnostic steps and determine that transition to E-3, Steam Generator Tube Ru ture is re uired. CRS/ATC Check if RCP tri criteria are met CRS/ATC CRS/ATC .Cr1tk:ar Task 2: I.... 33 SG- nota these actIon8 tNiy not all be perf'ormed at the ana ti~ WHen 33 SG level reach_.: o Secure feeding 33 SG by ~ AFW FRY for 33 SG
- seta3 SG ADV to 74",
Isolate Iteam Craps upstream of 33 MStV Close 33 MSIV CIoseMS42
- Verify Btowdown Valves _closed far 33 SG CRS/ATC cl1bl Task 3:
Usa cQndal1l8l' aIaaIrI duriIps to lnitlata cooldoWr'l (max 0 IbmIhr) SlopCooldownwhenCmareat. . ~ '~rons 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 3 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 Pum~s 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 Information DatelTime: Today/Now Condition: Power Ops
% Power: 100%
Xenon: Equilibrium RCS Boron: 1040 ppm 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 1.78E-2 IJCi/cc Risk Assessment: Yellow Plant Equipment Status:
* # 31 ABFP was declared inoperable 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> 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 3 Page 160f 16}}