Review 2-WCR-1 Reactivity Summary Calculation ENTERGY (IP2) … · 2012. 12. 3. · Review 2-WCR-1 Reactivity Summary Calculation . Page 3 of 15 . INITIAL CONDITIONS . An RO has prepared

Review 2-WCR-1 Reactivity Summary Calculation Page 1 of 15

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: 2000820122-1.doc Time: 15 minutes

Task Number: 2000820122 2-WCR-1 Administrative

Review 2-WCR-1 Reactivity Summary Calculation

Page 2 of 15

JPM Title: Terminate SI per ES-1.1

JPM Number: SRO-Admin 1-1

KA Number and Importance: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc RO - 3.9; SRO - 4.2

Suggested Environment: Classroom

Actual Testing Environment:

Alternate Path: NO

Time Critical: NO

Estimated Time: 15 Minutes Actual Time: ___

References: • 2-WCR-1, Reactivity Summary • 2-GRAPH-CVCS-6, Boration Dilution Tables • 2-GRAPH-RCS-4, Minimum Shutdown Boron Concentration • 2 GRAPH ..RV-2, Total Power Defect (pcm) as a function of

Power and Boron Concentration at MOl/EOl • 2 GRAPH-RV-3, Differential Boron Worth (MOl/EOl) • 2-GRAPH-RV-1, Bank Overlap Remaining Rod Worth • 2 GRAPH-RV-11 Control Bank D Position vs Power Required

to Maintain Constant HFP (Hot Full Power) ARO (All Rods Out) Axial Offset.

TASK STANDARD: Manual Reactivity Summary Calculation Reviewed and error in calculation identified.




INITIAL CONDITIONS

An RO has prepared a Manual Reactivity Summary Calculation in accordance with 2-WCR-1.

Current Plant Conditions: • Reactor Power - 100% • Control bank 0 rods are at 223 Steps • Boron Concentration - 970 ppm • EFPD - 327 • MTC (NuPOP) - 14.3 pcmrF • ITC -16.5 pcmrF • Estimated Shift Reactivity due to core burnup - 71 gallons primary water

INITIATING CUES:

You are the CRS and the SM directed you to Review the Manual Reactivity Summary Calculation.


Task Number: 2000820122 Administrative


« Denotes Critical Step

STEP DESCRIPTIONS t CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below

1. Commence evaluation

2. Obtain current revision of 2-WCR-1

3. Check Given Data on the form

4. Check Graph RCS-4 HSD Boron Conc.

Check A Power Coefficient Value (GRAPH.5. RV-2)

6. Check B Boron Worth (GRAPH-RV-3)

7. Check C. Boration (Boron Dilution Tables)

8. Check D. Dilution (Boron Dilution Tables)

li9. Check E. Rod Worth (GRAPH-RV-1)

1110. Check G. MWD/MTU

11.11. Check Boron for 1°F change

STANDARD StU

Obtains Current Copy of Procedure Check Data on Form Entered correctly Locates proper curve on graph and correct point selected. Checks 1255 Entered Correctly Calculatell nterpolate values for 970 ppm boron at 100% and 90% and calculate Value Correct at 16.09 pcm/% (± 0.02) Not necessary to interpolate. The difference is beyond significant values. Value Correct at 7.86 or 7.85 pcm/ppm Value on graph Value Correct at 3.19 gal/ppm Value on graph Value Correct at 66.9 gal/ppm Value Correct at 2.7 pcm/step (+0.04) Calculate value Value Correct at 12000 MWD/MTU (+1.0)

I ~aci~e correct at 6 gal _ .2)




STEP DESCRIPTIONS I CUES & NOTES

.i12. Check Dilution for 1°F change

.13. Check Rod Step for 1°F change

L..I-14. Check Megawatts for 1°F change

16.

.17.

Check Desired Rod Position 10% Check Boron Addition to compensate for 10%

Candidate should determine that the Boron Addition to Compensate PWR Defect less Rods value for 10% is in error Note candidate may stop at this point because calculation is Unsatisfactory

18. Check Desired Rod Position 30%

.19. Check Boron Addition to compensate for 30%

20.

.21.

.22.

Check Desired Rod Position 50%

Check Boron Addition to compensate for 50%

Inform evaluator that Calculation is incorrect.

JPM Complete

STANDARD S/U Calculate value Value correct at 122 gal (±1.0) Calculate value Value Correct at 5 or 6 steps Calculate value Value Correct at 10 or 11 Select from graph RV-11 Value Correct at 203 (±1.0) steps

Determines Value Incorrect. Correct value should be 29

Select from graph RV-11 Value Correct at 182 (±1.0) Calculate value Value Correct at 89 or88 Select from graph RV-11 Value Correct at 172 (±1.0) Value Correct at 188 or189




DATE: 'T6Qbx (Page 1 of 3)

Reactivity Summary

1. Reactor Operator periorms calculations during midnight shift Saturday night for Sunday.

2. The STA (Preferred) or CRS will independently verify the calculations (or inputs if computer generated)

3. On-coming Reactor Operators will present items 5 - 12 during the formal crew turnover meetings.

4. linear interpolation between bumup values is permitted on RV-11.

5. Reactor power 100 "/0ANSWER KEY 6. RCS Boron Concentration glQ PPM

The Values shown 1. HSO Boron Concentration (RCS-4) here are correct

1),0B. Boron for jOF change (C· HIS) L GalThe circled value is incorrect on the9. Diltltion for 1 "F change (0 • H/B) IJ;;l, Gal candidate copy

10. Rod Steps for 1°F change (HIE) ;2 Steps

11. Megawatts for 1"F change 10' IfA IQ rvrN 12. Estimated Shift Reactivity additions due to core bum up If Gal

CurtlJ'l!le 3~cnae PPM cb:mae per sllifl 11$10, clwIp ()'rer ~e,mol dlIy. ~n

Indian Point Unit 2 Boralion • Dilution Tablea

REOOGAlOF . REODGALOF REQDGAlOF REooGALOF REOO GAL OF Reoo GAL OF

C/) Q)

2.;:::J""

c 0

-.:;

PPM BORON

CONC.

810

ACID

TO

BORATE 1 PPM

3.17

WATER

TO

DILUTE 1 PPM

80.10

ACID

TO

BORATE

2 PPM

6.33

WATER

TO

DILUTE 2 PPM

160.20

ACID

TO

BORATE

5 PPM

15.83

WATER

TO OILUTE SPf'M

401.30

ACID

TO

BORATE

10 PPM

31.66

WATER

TO

DIlUTE 10 PPM

805.20

ACID

TO

BORATE

2Of'PM

63.33

WATER

TO

DILUTE 2.0 PPM

1620.50

ACID

TO

BORATE 50 PPM

158.44

WATER

TO

DILUTE

50 PPM

4129.90

.S; ~ E.2! I.OC::

~'eC1J't).§ IC:( f-

m- 820 3.17 79.10 6.33 158.30 15.83 396.40 31.67 795.30 63.36 1600.50 158.52 4077.90 ::s 830 3.17 78.10 6.34 156.40 15.84 391.60 31.69 785.70 63.39 1581.00 158.60 4027.20 (,)- 840 3.17 77.20 6.34 154.50 15.85 387.00 31.70 776.30 63.42 1561.90 158.68 3977.70 m 0

650 860 870

3.17 3.17 3.17

76.30 75.40 74.50

6.34 6.35 6.35

152.70 150.90 149.20

15.86 15.87 15.87

382.40 377.90 373.60

31.72 31.74 31.75

767.10 758.10 749.30

63.46 63.49 63.52

1543.30 1525.20 1507.40

158.76 158.84 158.92

3929.50 3882.40 3836.40

~ 880 3.18 73.70 6.35 147.50 15.88 369.30 31.77 740.BO 63.55 1490.10 159.00 3791.50 C\'I 890 3.18 72.90 6.36 145.80 15.89 365,20 31.78 732.40 63.58 1473.20 159.08 3747.70

E 900 3.18 72.10 6.36 144.20 15.90 361.10 31.S0 724.20 63.61 1456.60 159.15 3704.80 E ::SID (/)~

>a_0-s: f'-. - Q.)-0)(,) CO ma..CDa::

910 920 930 940 950 960 970 980 990 1000

3.18 3.18 3.18 3.19 3.19 3.19 3.19 3.19 3.19 3.20

71.30 70.50 69.70 69.00 68.30 67.60 66.90 66.20 65.50 64.80

6.36 6.36 637 6.37 6.37 6.38 6.38 6.38 6.39 6,39

142.60 141.10 139.50 138.10 136.60 135.20 133.80 132.40 131.10 129.80

15.91 15.91 15.92 15.93 15.94 15.95 15.95 15.96 15.97 15.9B

357.10 353.20 349.40 345.70 342.00 338.50 335.00 331.50 328.20 324.90

31.82 31.83 31.85 31.86 31.B8 31.89 31.91 31.93 31.94 31.96

716.20 708.40 700.70 693.20 685.90 678.70 671.70 664.80 658.00 651.40

63.65 63.68 63.71 63.74 63.77 63.80 63.84 63.67 63.90 63.93

1440.40 1424.60 1409.10 1394.00 1379.10 1364.60 1350.40 1336.SO 1322.80 1309.50

159.23 159.31 159.39 159.47 159.55 159.63 159.71 159.79 159.87 159.95

3662.90 3622.00 3582.00 3542.80 3504.50 3467.00 3430.30 3394.30 3359.10 3324.70

..-I

0:: 0s:

I C\I

~ Ia::

0

1020 1040 1060

3.20 3,20 3.20

63.60 62.40 61.20

6.40 6.40 6.41

127.20 124.80 122.40

15.99 16.01 16.03

318.50 312.40 306.50

31,99 32.02 32.05

638.60 626.30 614.40

64.00 64.06 64.13

1283.50 1258.60 1234.60

160.11 160.27 160.43

3257.60 3193.60 3131.90

~ N

~ CD->CDa::

1080 1100 1120 1140 1160 1180 1200

3.21 3.21 3.21 3.22 3.22 3.22 3.23

60.00 59.00 57.90 56.90 55.90 55.00 54.00

6.42 6.42 6.43 6.44 6.44 6.45 6.45

120.10 118.00 115.80 113.80 111.BO 110.00 108.10

16.04 16.06 16.07 16.09 16.11 16.12 16.14

300.80 295.30 290.00 264.90 280.00 275.20 270.60

32.09 32.12 32.15 32.18 32.22 32.25 32.28

603.00 591.90 581.30 571.10 561.20 551.60 542.40

64.19 64.25 64.32 64.38 64.45 64.51 64.58

1211.60 1189.30 1167.90 1147.20 1127.30 1108.00 1089.40

160.69 160.76 160.92 161.06 161.24 161.41 161.57

3072.50 3015.30 2960.20 2907.10 2855.80 2806.40 2758.60

C\I N ..-

UOON "0 00 '0

'70 NOC\lN .,... Oi..: NCIJ

SYSTEM TEMPERATURE = 547DEGF 00..0 °EO:J ~z ..CIJ ~ C/)

=(1)LLI

; :,.",~. I/) Q)

l:ti "~' b t'-; tll ~~.:.: 2.~INDIAN POINT STATION UNIT NO.2 CYCLE 19 ~ ""..... ... ,_.-.-.,..... -... ::J ....

MINIMUM SHUTDOWN BORON CONCENTRATION 'L-. .!:E ....e

~ll..I&IIUUlJlltiL .~ 2200

LOI::"'-.----..." ........---.........- ..-~.. .. ~.-. --_...-,-.-~-------.-.-~..-.---.~--.--- G',r ~TU':" .;i~r;, ~ mX'!i:...:. ...----.-.----.-:..."-~--

~

..-.. .-E!f~.50

.000::

~5C

'i'''''

(/)(1)

c o ;; ca-::::s (.)-ca (.)

Boron Cone, (ppm)

{I

SO 100

(I

,:

u 0.0

5

lJ.}J 0

1:,,';:

1:;1

Review 2-WCR-1 Reactivity Summary Calculation

Page 10 of 15

lNDIAN POINT ENERGY CENTER UNIT NO. 2 ~ CYCLE 19

Bank Overlap Remaining Rod Worth

O· Bank

Steps

223

213

Worth peM

0.0

-'}~:t i~ 1::.1 ,"+

f


iNDIAN POINT STATION

UNIT NO.2· CYCLE 19

·:JifferenUal 90ron Worth (MOL EOl)

Floron Concentration I PPM) Differential Boron Worth (pCMlPPM)

\) 8.76

i5 871

150 963

225 8.55

300 847

375 840

.+50 6.32

:;25 825

BOO 8.19

675 8.12

750 8.05

825 799

900 792

--;:> 975 786-;050 7.79

'125 7.73

:2QO 7.67

~275 760

1350 754

1.t25 748

1500 742

'575 7.36

~650 ~31

725

'800 1.20

Effective Date

=

-Ill Q.)=(/) I\.:> 180 ." j " ... '.i '.:C .. '1.. '.. T--::":;'cc:c .":":_ : . .' """-::r:"':'T:: ••,..... ·...':T.-·· ."E ....·; . :i' ..., .. :! . '.: ~

(") 170 ... ; T !: ~ '].-~'~...-::.'. ::';:~~~:!",c ......... :~~± ':';~ .... i-i; ",;:;;: "'f 'J:i

I160 .' . ~T: . ; ..•. . i~"",,~ i. J':.tr' ··T~::·ill}'::.1= I = .. ::0 ...a. 150 '. :.: ·r.}: "~l ;...:- ·····+1 i .:--:·F=·'· T ::0 ~ 140 .1. .... ... .... .r. :.:. :c':.::·.::.... :,f'.]. ; i ,cf>Y .. I":t,'·'l::: -0(1)"0: •. '

Ui 130 ; L, ... 1- .t\:-:. ·'-.·T:::T:T·'·;'L .i...r·! .. :,.., .. , "'; .. Q) I» (0(")

I\.:> 150 (I),..j 120 " ;~. ,:;: ,. l i:J~~.", f r ';Jrr' \FL~liTr t~ .... :C.--6000~ ~ 110 .......-::G:~y'·r .T':·~i' !:'l:'~'FF ':'f'>:-: ,.:1' I',: .:c;. r l'- N _.o - - 12000::::0, e. 100 ... .i. .~lT:r::- ~cT I J ......] ..... ........• ......., .....;. . .1 __ : :r. T o~ ..... • 25347 a 90 ..: ,.':( ':'T' ~T.'· ". !:;tJ'l .......... ! ... ,....,'; ... ': -.... cn . .:. t ..... '-J" :T •.: ... i'., c.:. l. ..,.:... ... ,::.: ..:. T"- ·.r··j ; L- ..:. .J.j; ......• ' :J'.l .. 1:7+1.:[:' 1'1"" ;....... ...... ].2:=:'1"'1':'..... ,~ CJ1C .;,I.

c II)

so 3 (Q 370

I»60 50 ~ ----:::- :; ~~

(")40 S»

30 C-=F'; .·:··..li~l.!.: i


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:



of 15

INITIAL CONDITIONS

An RO has prepared a Manual Reactivity Summary Calculation in accordance with 2-WCR-1 for training evaluation qualification.

Current Plant Conditions: • Reactor Power - 100% • Control bank D rods are at 223 • Boron Concentration - 970 • EFPD - 327 • MTC (NuPOP) - 14.3 pcmrF • ITC - 16.5 pcmrF • Estimated Shift Reactivity due to core burnup - 71 gallons primary water

INITIATING CUES:

You are the CRS and the SM directed you to Review the Manual Reactivity Summary Calculation.

File:

Task Number:

--

Page 15 of 15

DATE: TI>DbY (Page 1 of 3)

Reactivity Summary

1. Reactor Operator performs calculations during midnight shift Saturday night for Sunday.

2. The STA (Preferred) or CRS will independently verify tha calculations (or inputs jf computer generated)

3. On-coming Reactor Operators will present items 5 - 12 during the formal crew turnover meetings.

4. Linear interpolation between burnup values is permitted on RV-11.

5. Reactor power 100 %

6. Res 80ron Concentration '110 PPM

7. HSD Boron Concentration (RCS-4) bl5'S PPM

8. Boron for 1"F change (C .. HIS) (, Gal

9. Dilution for 1"F change (0 * HIS) ~_Gal

10. Rod Steps for 1"F change (HIE) ,- Steps

11. Megawatts for 1OF change 1 0 • IIA 10 wm 12. Estimated Shift Reactivity additions due to core burn up 7/ Gal

Ctlmpute a~mt. PPM change per s1un using chang!: OVCl' $cyrral .uys and W/f:loron requin:d PWlBoron cr Total Dilllll

Ro Performedby ate Reviewedbv

Reactivity Values

A. Power coefficient tRV-2) (10% RanQe from current pawer) jil.()C\ Doml"lo B. Boron worth (RV~3) 7. ~(, pem/ppm C. Boration (OilutiOn/BOfation Tables) 3· ff1 gal/ppm D. Dilution (DnutioniBoration Tables) t..(", tt gal/prim E. Rod Worth (RV~1) {10 Stee Rangel ~.7 pem/step.-. F. EFPDs (obtained from pmtious 2·WCR·l OR fleeClor Engineering) EFPD5 ~1. '''' G. MWO/MTU ( F X 36.68) I;JDDD MWOIMTU H. Moderator Temperature Coefficient (Online NuPOP) r.q,3 pcmI"'F I. Isothermal Temperature Coefffcient (Online NuP,?P, _.. pcl'llJOF,,,."

2-WCR·1 RevS

File:

Task Number:

Identify the Location for Spent Fuel Assemblies Page 1 of 6

ENTERGY (IP2)


Operator Name:

Employee 10 #:

Evaluator:

Date: SAT UNSAT



File: 17S00S0122-1.doc Time:20 minutes

Task Number: 17S00S0102 Tech Specs Administrative

, .

Identify the Location for Spent Fuel Assemblies

Page 2 of 6

.JPM Title: Identify the Location for Spent Fuel Assemblies

JPM Number: SRO Admin 1-2

KA Number and Importance: 1940012142 Conduct of Operations Knowledge of new and spent fuel movement procedures. RO - 2.5; SRO - 3.4.



Alternate Path: NO

Time Critical: NO

Estimated Time: 20 Minutes Actual Time: --References:

Tech Spec 3.7.13 Tech Spec Basis 3.7.13

File: 17S00S0122-1.doc Time:20 minutes

Task Number: 17500S0102 Tech Specs Administrative

Identify the Location for Spent Fuel Assemblies Page 30f6

INITIAL CONDITIONS:

Three fuel assemblies in the spent fuel pit need to be moved to facilitate an inspection of the spent fuel racks in those areas.

Fuel Assembly Data

Fuel Assembly 1 Initial Enrichment 4.5 Wlo Burnup 52,000 MWD/MTU In Spent Fuel Pit since April 2005 Number of IFBA Rods 0

Fuel Assembly 2 Initial Enrichment 4.6 Wlo Burnup 32000 MWD/MTU In Spent Fuel Pit since March 2010 Number of IFBA Rods 0

Fuel Assembly 3 Initial Enrichment 4.95 Wlo Burnup 0 MWD/MTU (New Fuel Assembly) Ins Spent Fuel Pit since January 2010 Number of IFBA Rods 24

INITIATING CUES:

Your are the CRS and the SM has directed you to determine the Spent Fuel Pit Region(s) each fuel assembly can be moved to.

TASK STANDARD:

All acceptable Storage Regions identified for each fuel assembly.

File: 1750050122-1.doc Time:20 minutes

Task Number: 1750050102 Tech Specs Administrative

Identify the Location for Spent Fuel Assemblies Page 4 of 6

• Denotes Critical Step

STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U

Inform operator to BEGIN after his

completion of review of the Initiating Cues

and log time below

1. Commence evaluation

2. Obtain Tech Spec Section 3.7.13 and Basis Obtains TS Determines 1-1,1-2,

.3. Candidate evaluates Fuel Assembly 1 2-1,2-2 Determines 1-2,2-2

.4. Candidate evaluates Fuel Assembly 2 Peripheral Cells Determines 1-1 Checkerboard, 1-2 and 2-2 Peripheral

.5. Candidate evaluates Fuel Assembly 3 Cells

..IPM Complete

ANSWER KEY Region 1-1 Region 1-2 Region 2-1 Region 2-2

Assembly 1 YES YES YES YES

Assembly 2 YES YES NO PERIPHERAL

Assembly 3 CHECKERBOARD YES NO PERIPHERAL



Identify the Location for Spent Fuel Assemblies Page 5 of6

Any area of weakness obselVed? YES DNOD Examinee Signature

All areas of obselVed weakness discussed

Evaluator Initials





of 6

INITIAL CONDITIONS:

Three fuel assemblies in the spent fuel pit need to be moved to facilitate an inspection of the spent fuel racks in those areas.

Fuel Assembly Data

Fuel Assembly 1 Initial Enrichment 4.5 Wlo Burnup 52,000 MWD/MTU In Spent Fuel Pit since April 2005 Number of IFBA Rods 0

Fuel Assembly 2 Initial Enrichment 4.6 Wlo Burnup 32000 MWD/MTU In Spent Fuel Pit since March 2010 Number of IFBA Rods 0

Fuel Assembly 3 Initial Enrichment 4.95 Wlo Burnup 0 MWD/MTU (New Fuel Assembly) Ins Spent Fuel Pit since January 2010 Number of IFBA Rods 24

INITIATING CUES:

Your are the CRS and the SM has directed you to determine the Spent Fuel Pit Region{s) each fuel assembly can be moved to.

File:

Task Number:

Review a Tagout

Page 1 of 18

ENTERGY (IP2)


Operator Name:

Employee ID #:

Evaluator:

Date: SAT UNSAT



File: 2000391601-4.doc Difficulty: 4 Time: 45 minutes

Parent Task # 200*039*01 *01 EN-OP-102 Admin

Review a Tagout

Page 2 of 18

JPM Title: Prepare a Tagout for 21 SI Pump

JPM Number: SRO Admin 2-1

KA Number and Importance: 1940012213, Equipment Control Knowledge of tagging and clearance procedures. RO - 4.1; SRO - 4.3



Alternate Path: NO

Time Critical: NO


References: • EN-OP-102, Protective and Caution Tagging • EN-OP-1 02-1, Protective and Caution Tagging Forms &

Checklist • 208088 One Line Diag of 480V Switchgear 21 & 22 8us 2A,

3A, 5A, 6A • 225134 Elementary Wiring Diagram of Safety Injection

Pump 21 • 208500 One Line Diagram for 480V MCC ..26AA and MCC

2688 & 120VAC Distribution Panels 1 & 2 • 241171 Control Room Panel S8-2 • 9321-2735 Flow Diagram Safety Injection System


Parent Task # 200*039*01*01 EN-OP-102 Admin

Review a Tagout Page 3 of 18

INITIAL CONDITIONS:

1 The eSOMS Clearance Module is unavailable.

2 The Shift Manager has determined that 21 Safety Injection Pump must be tagged out for seal replacement.

3 A spare RO has prepared a manual tagout for 21 Safety Injection Pump.

4 Clearance Number is 2C20

5 Tagout Number is SI-001.

6 No deficiencies exist on valves identified in tagout boundary

INITIATING CUES:

You are the CRS and the SM has directed you to review the manual tagout for 21 Safety Injection Pump using EN-OP-102 and EN-OP-102-01.

TASK STANDARD:

Manual Tagout Reviewed and errors identified.

File: 2000391601-4.doc DifficuIty: 4 Time: 45 minutes



I 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 I

Commence evaluation 1. Time Commenced:

Obtains EN-OP-102 Obtain Correct Procedure 2.

EN-OP-102-01

Ensure requirement of Attachments 9.1 and Review Attachment 3. 9.2 of EN-OP-102 are followed 9.1 and 9.2

Tagout Required for iReview Scope of Work4.

emergent work

Tagout Required for Review Tagging Requirements 5. emergent work

Review Plant Prints 208088

Determine Safe Work Boundary for 21 SI 225134Pump Seal replacement 16. 208500

225134

i241171

9321-2735 Boundary Valves should be reviewed for outstanding deficiencies Determines no

7. outstanding i

CUE: No deficiencies exist on valves • deficienciesidentified in tagout boundary

Complete Attachment 9.1 and 9.2 of EN-OP- See Attached Answer .8. 102-01 Key


Parent Task # 200*039*01 ·01 EN-OP-102 Admin

9.

10.

11.

12.


Utilizing the Isolation Boundaries, Prepare the tagout For each tag include:

• Tag Serial Number • Tag Type • Equipment • Equipment Description • Equipment Location • Placement Sequence • Placement Configuration

Tag Type: Danger

Component: 21 Safety Injection Pump 480V Bus 5A Control Switch

Equipment Location: 480V Room

Desired Position: Pullout

Sequence 1

Tag Type: Danger

Component: 21 Safety Injection Pump Breaker Control Fuses


Desired Position: Removed/Off

Sequence 2

Tag Type: Danger

Component: 21 Safety Injection Pump Breaker


Desired Position: Racked Out

Sequence 3

See attached Answer Key

Identifies Information Correct





13.

_14.

15.

116.


Tag Type: Danger

Component: MOV-850A 21 SI Pump Discharge Valve

Equipment Location: PAB MCC Room

Desired Position: Closed/Neutral

Sequence 4

Tag Type: Danger

Component: MOV-850A 21 SI Pump Discharge Valve Breaker


Desired Position: OFF

Sequence 5

Tag Type: Danger

Component: MOV-850A Manual Operator

Equipment Location: SI Pump Cell

Desired Position: Do Not Operate

Sequence 6

Tag Type: Danger

Component: SI-1807A 21 SI Pump Recirc Test Line Stop


Desired Position: Closed

Sequence 7


Identifies Information NOT Correct Data NOT Entered on the Form

Identifies Information Correct NOTE: Tag Sequence will be incorrect going forward. This is not critical

Identifies Information NOT Correct

Data NOT Entered on the Form



17.

.18.

19.

20.


Tag Type:

Danger

Component:

SI-848A 21 Safety Injection Pump

Suction Stop

Equipment Location:

SI Pump Cell

Desired Position:

Closed

Sequence

8

Tag Type:

Danger

Component: SI-1843A 21 SI Pump Thrust Balance Flow Line Stop

Equipment Location:

SI Pump Cell

Desired Position:

Closed

Sequence

Not Critical

Tag Type:

Danger

Component:

SI-7306-Cap - Cap downstream of

drain valve 7306

Equipment Location:

SI Pump Cell

Desired Position:

Cap Removed

Sequence

Not Critical

Tag Type:

Danger

Component: SI-7306 21 SI Pump Discharge Line Drain Stop


Desired Position: Open

I Sequence Not Critical


Identifies Information NOT Correct

Valve should be tagged closed not Open





21.

22.

23.

24.

25


Tag Type: Danger

Component: SI-4274-Cap - Cap Downstream of vent valve 4274


Desired Position: Cap Removed

Sequence Not Critical

Tag Type: Danger

Component: SI-4274 21 SI Pump Casing Vent Stop




Review Manual Tagout Index Sheet

Review T agout Cover Sheet

Candidate reports 3 errors on the Manual Tagout J PM is complete



Lists 21 SI Pump on index sheet

Verify:

Clearance - Given

2C20 Tagout: Given 51-001 Component to be

Worked

, 21 SI Pump Description: See attached Key






Evaluator Initials




Parent Task # 200'"039'"01 '"01 EN-OP-102 Admin

of 18

• NUCLEAR ~UALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENT"===- Entergy MANUAL INFORMATIONAL USE PAGE 50F 25 Protective and Caution Tagging Forms & Checklist

ATTACHMENT 9.1 MANUAL TAGOUT INDEX SHEET

CLEARANCE ________

TAGOUT# COMPONENT TO BE WORKED DATE DATE HUNG REMOVED

51-001 21 Safety Injection Pump Seal

Answer Key

File: 2000391601-1.doc Parent Task # 200*039*01*01

of 18

• NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENT-~- Entergy MANUAL INFORMATIONAL USE PAGE 6 OF 25 Protective and Caution Tagging Forms & Checklist

ATTACHMENT 9.1 TAGOUT COVER SHEET

Clearance: 2C20 MANUAL Tagout: SI-001 ---------------------Component to be worked:

Description 21 SI Pump has a seal leak. Tagout and drain pump for seal replacement

Placement Inst: See Attached

Hazards: See Attached

Restoration Inst: See Attached

I Attribute Descri~tion

I I

I I

vvork Order N ...III.....

Status Prepared Technical Reviewed Approved Tags Verified Hung Removal Approved Tags Verified Removed

File: 2000391601-1.doc

Desc ri j.,Ln.1II

Description Prepared Reviewed ~pproved

Tags Verified Hung Removal Approved Tags Verified Removed

Parent Task # 200*039*01 *01

Answer Key

-

Attribute Value

I !

User Verification Date

---------

--------- ----------

-------

-------

-- ---------

-------- -------

Paae 12 of 18- ~-,---=~.~~~~ ~ ~ ~ ~ ~~~-~~~

Tag Tag Type Equipment Place Placement Place 1'" Place 2nd Rest Restoration Rest 1"' Place 2nd Placement/Removal Tag Seria Equipment Description Seq. Configuratio Verif Verif Seq Configuratio Verif Verif Notes I No. Equipment Location n~~~_ DatelTime DatelTime n DatelTime_ DatelTime

~---- --~~~-~~---

1 Danger 21 Safety Injection Pump 1 Pullout Auto --

480V Bus 5A Control

Switch

CCR Pnl SBF-2

2 Danger 21 Safety Injection Pump 2 Removed! Installed!On

Breaker Control Fuses Off

480 V Room Bus 5A --- ----- r-~-----~~~-~~~---

3 Danger 21 Safety Injection Pump Racked Out Rackedlln

breaker

480V room Bus 5A

4 Danger MOV-850A 4 Closed! Open!

21 SI Pump Discharge Neutral Neutral

Valve

QQ' DJ'. Q I\Jlf'f' D""......

5 Danger MOV-850A 5 OFF edOmitted on candidate21 SI Pump Discharge

Valve Breaker form

98' PAB MCC Room

6 Danger MOV-850A Manual 6 Do Not Do Not

Operator Operate Operate!

PAB 59' SI Pump Cell Locked -- I-

f uanger ::l1-H:SUfA f L;losea ted Omitted on candidate ! Answer Key 21 SI Pump Recirc Test

Line Stop form d

PAB 59' SI Pump Cell

v ~~••~v' ~.v'v, v ~.~~vw Backseated

21 Safety Injection Open!

LockedPump Suction Stop

PAR J:\Q' ~I P, Imn r.",11

-~~~--

9. Danger SI-1843A 9 Closed ~d

21 SI Pump Thrust Incorrect Position on

Balance Flow Line Stop candidate form


lU uanger ::l1- {jUtl-L;ap 1U L;ap Installed

Cap Downstream of Removed

drain valve 7306


11 Danger SI-7306 11 Open Closed

21 51 Pump Discharge

Line Drain Stop

PAB 59' 51 Pump Cell

---~~~-~~~

File:

Parent Task # Task Number

--------Paae 13 of 18

Danger I SI-4274-Cap 12 I Cap Insta lied Cap Downstream of vent Removed valve 4274

IPAS 59'SI Pump Cell --+----- ----- ----c-- r-13 Danger SI-4274 13 I Open Closed

21 SI Pump Casing Vent Answer Key Stop

PAS_59' SI Pump Cell

File:


of 18

INITIAL CONDITIONS:



3 A spare RO has prepared a manual tagout for 21 Safety Injection Pump.




INITIATING CUES:

You are the CRS and the SM has directed you to review the manual tagout for 21 Safety Injection Pump IJsing EN-OP-102 and EN-OP-102-01.

File:


of 18

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENT--- Entergy MANUAL INFORMATIONAL USE PAGE 5 OF 25

Protective and Caution Tagging Forms & Checklist


CLEARANCE ________


51-001 21 Safety Injection Pump Seal

File:


------------------

Page 16 of 18

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENTEntergy MANUAL PAGE 6 OF 25



Clearance: 2C20 MANUAL Tagout: SI-001

Component to be worked:

Description 21 SI Pump has a seal leak. Tagout and drain pump for seal replacement

Placement Inst: See Attached

Hazards: See Attached

Restoration Inst: See Attached

n Attribute Value

Status Description User Verification Date Prepared Prepared Technical Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed

File:


NUCLEAR e NON-QUALITY RELATEO EN-OP-102-01MANAGEMENT MANUAL~-En ter,!::ry INFORMATIONAL USE PAGE


..............'--~ ""'-----~==~~~~,

ATTACHMENT 9.3

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CLEARANCE: _MANUAL d C :.1.D__ TAGOUT: ~J. . pb f

Equipment . , I'

Equipment De.sC..n.;ption Pla.~.P!acemen

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NUCLEAR NON-QUALITY RELATEO !... EN-OP·102·01 REV.SMANAGEMENT I~;~Enfe'6'Y MANUAL

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'-__~E!~tectiYE:1 and Cal!tion Tagging.£orm~& Checklist

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ATTACHMENT 9.3 -~-. T AGOUT TAGS SHEET

CLEARANGE:_MANUAL Sf C: "0 TAGOUT: '0 ( -- liCit r-Tag 1- Tag EqUipment ~ ==r-- r I Place. I Place. Rest. 1st Rest. 2nd _vvv'''~11tf' Se",i Type EqWpmM' """'pt"" P"" I Pi,oem.o' '" V",, I 'od Veo' R~",,"o, V",, V"if Rem"",'

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Review a Liquid Radioactive Release Permit for #14 Liquid Waste Distillate Storage Tank

Page 1 of 11

ENTERGY (IP2)


Operator Name:

Employee 10 #:

Evaluator:

Date: SAT UNSAT




Parent Task # 200*024*01*02 2-S0P-5.1.5 Admin


Page 2 of 11

JPM Title: Review a Liquid Radioactive Release Permit for #14 Liquid Waste Distillate Storage Tank

JPM Number: SRO-Admin - 3-1

KA Number and Importance: 1940012311 Radiological Controls - Ability to control radiation releases. RO - 3.8; SRO - 4.3



Alternate Path: NO

Time Critical: NO

Estimated Time: 25 minutes Actual Time: --

References: 2-S0P-5.1.5, Calculation and Recording of Radioactive Liquid Releases




Page 3 of 11

INITIAL CONDITIONS:

1. The Unit is operating at 100% power.

2. All radiation monitors are source checked and operable.

3. The Discharge Flowmeter and Recorder are operable

4. #14 Waste Distillate Storage Tank (WDST) is to be discharged, tank level, as reported by the NPO, is 71 inches.

5. #14 WDST has been isolated and on recirc for the past 5 hours.

6. R-54 is aligned to #14 WDST.

7. Chemist has reported total gamma activity is less than the limit in IPSMM-CY-001 (5.0E-5 IJCi/ml).

8. R54 activity is 2.4E-5IJCi/cc

9. Additional Data:

Permit Number 100300 TanklD 14 WDST Initial Tank Level 71 Inches Pre-release volume 16,351 Gallons Recirculation Rate 150 gpm Recirc Start- Today 5 hours ago Recirc Stop Today Now Chern Sample Number 3906 Sample Daterrime Today 15 minutes ago Total Gamma Activity 4.0E-5 IJCi/ml ADC 5.31 E-7 IJGi/ml ppm Boron in tank 632 ppm Pump Configuration 6 GWPs in Fast, 3 SWPs, 0 RWPs


Parent Task # 200*024*01 *02 2-S0P-5.1.5 Admin


Page 4 of 11

INITIATING CUE:

You are the CRS and the SM has directed you to review and approve the Liquid Release Permit in accordance with 2-S0P-5.1.5.

TASK STANDARD:

Radioactive liquid waste release calculation reviewed and release permit (Attachment 1 to SOP-5.1.5) approved.


Parent Task # 200*024*01*02 2-S0P-5.1.S Admin

Review a Liquid Radioactive Release Permit for #14 Liquid

Waste Distillate Storage Tank

Page 5 of 11

•• Denotes Critical Step


Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below


Review Precautions and Limitations

2. CUE: When requested, inform operator all P&Ls are satisfied

Determine required recirculation time for the .3. tank to be released

Determine Total Dilution Flow

.4. CUE:

6 CWP Fast Speed

3SWP

ORWP

Assign Permit Number 5.

Review data on Attachment 1 6.

Verify from Chemistry total gamma activity without noble gas is less than 5.0E-5 ~Ci/ml.

7.

Record Available Dilution Flowrate 8.

File: 2000241602-3.doc Difficulty: 4 Parent Task # 200*024*01*02 2-S0P-5.1.5

STANDARD S/U

Precautions and Limitations Reviewed

Determine minimum recirculation time to be 218 minutes from Table 1

Sum flowrate based on current pump combinations. Calculate 855,000 gpm Determines data correct on permit

Given in Initial Conditions

Supplied with Initial condition. Check data on form

Supplied with Initial condition. Check data on form

Previously calculated 855,000 gpm

Time: 25 minutes Admin

Review a Liquid Radioactive Release Permit for #14 Liquid

Waste Distillate Storage Tank

Page 6 af11


Calculate pounds of Boron in Tank and .9. Maximum Allowable Chemical Release Rate

Calculate the Permissible Radioactive Release '.10. Rate

Candidate may terminate JPM at this time due to identified error

Determine most restrictive release rate 11.

Determine effluent rad monitor in service and 12. calculate maximum alarm

Determine permit improperly completed and 13. does not sign Release Authorized By block

STANDARD S/U

Performs calculation determines 86 (±1) pounds of boron and Chem release rate 1352 (±2) Determines data correct on permit

Performs calculation determines rad. Release rate 11350 (±5)

Determines data NOT correct on permit

Identifies Pump Capacity 250 most restrictive

Determines data correct on permit

Calculates Max Alarm Setpoint 1.816E-3I-1Ci/ml

Determines data correct on permit

Does Not Sign Release Authorized By block




Page 7 of 11

Any area of weakness observed? YEsDNOD Examinee Signature


Evaluator Initials




Parent Task # 200*024*01 *02 2-S0P-S.1.S Admin

II

No: 2-S0P-5.1.5 Rev: 36 CALCULATION AND RECORDING OR

RADIOACTIVE LIQUID RELEASES Page 16 of 23

ANSWER KEY EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT

(Page 1j:!f---=12--______________----,

INITIAL

PERMIT # 10300 TANK ID 14 WDST Tank Level:2L- (Inches) Volume (V), gal

RECIRC Recirc Start: (Date) 00:00 (Time)

RATE: gpm

Recirc Stop: 7/14/10 (Date) 05:00 (Time)

Chemistry

Sample No. 3906 Sam Ie Collection: 7/14/10 (Date) 04:30 (Tima)

Gamma Activity without Gas and Tritium is less than the admin limit of SMM-CY-001: Yes No

Total Gamma Activity _~4.~0=.E·~5'_____~Ci/ml Allowed Diluted Concentration (ADC) 5.31E·7 ~Ci/ml

_-=_ Unit 2 Circulators TOTAL DILUTION FLOW (T) _-c8=5=5=,0=00"---_(GPM) From: _-,,:-0_ Unit 3 Circulators

_-=3_ Service Wate~~lUlJJ"'------~

Value on BORON: _==--=,--- x 16351 x B.33E-6 = _---=.86=--1 cand idate copy

tank vol (V), gal is incorrect

These are the

Maximum Chemical Release Rate (Rc) = ( 855,000 x 1 ppm) + 632 = 1352 correct values

Avail Dil Flow (B), gpm ppm B

(Rr) = (855,000 x 5.31 E·7

Avail Dil Flow (B), gpm ADC, uCi/ml

Most Restrictive Release Rc:lt~ (R) = 250 gpm (pump capacity~m---'-o~st'_'li"--m-"-'it"'_in=_____1

Rad Monitor # 54 SOURCE CHECKED OPERABLE ~YES NO (IF NO, COMPLETE ATT 3)

Maximum Alarm Setpoint = (855,000 x 5.31 E·7 ) + 250 = 1.816E·3 uCi/ml

Avail Dil Flow (B), gpm ADC, uCi/ml Most Restrictive

Release Rate (R), gpm

Actual Alarm Set oint = _....:4"".0;.::E:--4.:..____-'u::,:Co..:.:i/-'..:m-"-I___.-:W:..::.=;ar:.:.:-n§El!p(),-",in~t~=_--"3"".0;.::E:--4.:..___---"'-u.:::C"-'.i/m.:.::I'____----'

DISCHARGE FLOW METER & RECORDER OPERABLE NO, COMPLETE ATTACHMENT 3)

Release Authorized By: ________________ _ ______ (Date)

RELEASE INITIATED: ____(Data) _____ (Time)

RELEASE TERMINATED: ____(Date) _____ (Time)

FINAL TK LEVEL: __ (Inches) ____gal TOTAL VOLUME RELEASED _____9al

Remarks:

I No: 2-S0P-5.1.5 Rev: 36 . CALCULATION AND RECORDING OR

RADIOACTIVE LIQUID RELEASES I Page 16 of 23

INITIAL CONDITIONS:

1 . The Unit is operating at 100% power.

2. All radiation monitors are source checked and operable.

3. The Discharge Flowmeter and Recorder are operable

4. #14 Waste Distillate Storage Tank (WDST) is to be discharged, tank level, as reported by the NPO, is 71 inches.

5. #14 WDST has been isolated and on recirc for the past 5 hours.

6. R-54 is aligned to #14 WDST.

7. Chemist has reported total gamma activity is less than the limit in IP-SMM-CY-001 (5.0E-5 J,.ICi/ml).

8. R54 activity is 2.4E-5J,.1Ci/cc

9. Additional Data:

Permit Number 100300 TanklD 14 WDST Initial Tank Level 71 Inches Pre-release volume 16,351 Gallons Recirculation Rate 150 gpm Recirc Start- Today 5 hours ago Recirc Stop Today Now Chem Sample Number 3906 Sample DatelTime Today 15 minutes ago Total Gamma Activity 4.0E-5 J,.IC i/m I ADC 5.31 E-7 J,.ICi/ml ppm Boron in tank 632 ppm Pump Configuration 6 CWPs in Fast, 3 SWPs, 0 RWPs

INITIATING CUE:

You are the CRS and the SM has directed you to review and approve the Liquid Release Permit in accordance with 2-S0P-5.1.5.

No: 2-S0P-S.1.S Rev: 36 CALCULATION AND RECORDING OR

RADIOACTIVE LIQUID RELEASES Page 16 of 23

ATTACHMENT 1

EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT

,--_____________o:a e 1 of 1

INITIAL

PERMIT # 10300 TANK 10 14 WDST Tank Level:~ (Inches) ---'-1=63=5~1'____ Volume (V) , gal

7/14/10 (Date)RECIRC Recirc Start: --'-'--'--'-'--'---"'__ 00:00 (Time) RATE: gpm

Recirc Stop: 7/14/10__ 05:00 (Time)--"-'--'-2'-'-". (Date)

Chemistry

SamplElNo. 3906 Sam~le C()IIElction : 7/14/10 (Date) 04:30 (TIme)

Gamma Activity without Gas and Tritium is less than the admin limit of SMM-CY-001: Yes No

Total Gamma Activity _~4.~0.!::.E-~5,--___IJCi/ml Allowed Diluted Concentration (ADC) 5.31E-7 IJCi/ml

_-=6_ Unit 2 Circulators

TOTAL DILUTION FLOW (T) __8=5=5""",0"",00!

of 11


t •

Classify Emergency Events requiring Emergency Plan

Implementation (Time Critical)

Page 1 of 8

ENTERGY (IP2)


Operator Name:

Employee ID #:

Evaluator:

Date: SAT UNSAT




Task Number: 1500010503 IP-EP-120 Administrative

< •



Page 2 of 8

JPM Title: Classify Emergency Events requiring Emergency Plan Implementation (Time Critical)

JPM Number: SRO ADMIN 4-1

KA Number and Importance: 1940012438 Emergency Procedures/Plan - Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. RO- 2.4; SRO - 4.4.



Alternate Path: NO

Time Critical: NO

Estimated Time: 25 minutes Actual Time: --

References: • IP-EP-120, Emergency Classification • IP-EP-210, Central Control Room • IP-EP-410, Protective Action Recommendations • EAL Wall Chart • EAL Technical Basis Document





Page 3 of 8

INITIAL CONDITIONS

• The crew was responding to a Steam Generator Tube Leak in 21 Steam Generator per 2-AOP-SG-1, Steam Generator Tube Leak.

• At 48% power Tube Leakage was estimated to be 90 gpm. • The reactor was tripped and SI actuated. • 21 MSIV is closed • 21 Atmospheric Steam Dump is closed. • RCS Activity is 310 jJCi/ml dose equivalent 1-131 • 30 minutes after the Reactor Trip the following conditions exist:

• RCS Temperature 482°F and lowering • 21 SG pressure 22 psig and stable • 22-24 SG Pressure 580 psig and lowering • VC pressure 0.5 psig and stable

METEOROLOGICAL CONDITIONS:

Wind Speed: 7 meters/second

Wind Direction: 270 degrees @ 10 meters

Stability Class: C



Classify Emergency Events requiring Emergency Plan Implementation (Time Critical)

Page 4 of 8

INITIATING CUES:

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.

The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement SM can arrive on site.

You must make the Classify the above event and complete the NYS Part 1 form.

TASK STANDARD:

Emergency Plan Event properly classified and NYS Part 1 form completed.



11



Page 5 of 8

Denotes Critical Step



Obtain correct procedure IP-EP-120 1. Time Commenced:

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.

12.

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", IP-EP-115 EP-1

NOTE: Must be completed within 15 minutes of .3. declaration

Time IP-EP-115 Form 1 completed:

Refer to procedure IP-EP-210, Attachment 9.14. (SM I POM I ED Checklist)

Initiate County, State and NRC notification per IP-EP-115, Form EP-4, 5 or6 as applicable

5. CUE: Acknowledge as communicator when requested to commence notifications.

STANDARD S/~I

Determines Event is a General Emergency per EAL4.2.2

Complete Data Form Part 1

Verify data using Radiological Emergency Data Form information, item #s 1 - 8

Attach 9.1

Request for CCR communicator



Classify Emergency Events requiring Emergency Plan Implementation (Time Critical)

Page 6 of 8



Evaluator Initials



File: 1S00011602-S.doc Time: 25 minutes

Task Number: 1S00010S03 IP-EP-120 Administrative

of 8

New York State

Indian Point Energy Center RADIOLOGICAL EMERGENCY DATA FORM - PART 1 Notification #

This is the Indian Point Energy Center with a Part 1 Notification

1. Reactor Status:

. This is an: ACTUAL EMERGENCY at 8 UNIT 3 BOTH UNITS \ Unit 2 ! (Time) (24 hr clock)

Shutdown Unit 3 Operational

(Oate) _____ (Time) ________ (24 hr clock) Shutdown

2. TheEm~ A. Unusual Event B. Alert C. Site Area Emergency Classification is: ~eneral Emergency E. Emergency Terminated

This Emergency Classification declared on: --LJL:~'--L__-:-:::-.

3.. EAL#:

I~ 4. Release of Radioactive Materials dlJe to tht/ Classified Event: I'

A. No Release B. Release BELOW Federal limits To Atmosphere ToWalerit {"--

C. Release ABOVE Federal limits \IQ.Atmospher To Water D. Unmonitored release requiring evaluation

Wind Speed; Meters/Sec at elevation 10 meters

~8'~~w=jn=d=D=j=re:g:tj:::on:;::,(=F=ro=m=)==:=========-D~eg~r.:e:es:."at elevation 10 melerS__~____~______--i 1. . Stability Class: D E F G

8. 1 The following Protective Actions are recommended 10 be implemented as soon as practicable:

1t A. NO NEED for PROTECTIVE ACTIONS outside the site boundary

@EVACUATE and IMPLEMENT the KI PLAN for the following Sectors

C. SHEL TER-IN·PLACE and IMPLEMENT the KI PLAN fOr the following Sectors

r---."-----~-._~_r~~~~~ Areas MONITOR the EMERGENCY ALERT SYSTEM

5 miles around 10-miles downwind Entire EFZ

~ 7 8 9 10 11 12 13 14 15 16 NOTE: OFFSITE AUTHORIT[I;.;'LSHOUJ.J;Lr:;ONSIDER SHELTER-IN-PLACE + TAKE KIIF EVACUATION IS NOT Fe~.SJ!ll,£

HP.innr!eO by - Communicator: _____.___.________ Telephone # ______~_.___ (CommL/nicator's Name)

Approval: _,____~_______~.___ Date/Time: ___~._________

(DirfICtor'S Name)

Page 1 of 1 Form EP-1, Rev 3

File:

Task Number:

of 8

INITIAL CONDITIONS

• The crew was responding to a Steam Generator Tube Leak in 21 Steam Generator per 2-AOP-SG-1! Steam Generator Tube Leak.

• At 48% power Tube Leakage was estimated to be 90 gpm. • The reactor was tripped and SI actuated. • 21 MSIV is closed • 21 Atmospheric Steam Dump is closed. • RCS Activity is 310 I-ICi/ml dose equivalent 1-131 • 30 minutes after the Reactor Trip the following conditions exist:

• RCS Temperature 482°F and lowering • 21 SG pressure 22 psig and stable • 22-24 SG Pressure 580 psig and lowering • VC pressure 0.5 psig and stable

METEOROLOGICAL CONDITIONS:

Wind Speed: 7 meters/second

Wind Direction: 270 degrees @ 10 meters

Stability Class: C

INITIATING CUES:

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.

The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement SM can arrive on site.

You must make the Classify the above event and complete the NYS Part 1 form.

File:

Task Number:

Calculate Shutdown Margin with Untrippable Rod

Page 1 of 8

ENTERGY (IP2)


Operator Name:

Employee 10 #:

Evaluator:

Date: SAT UNSAT






Page 2 of 8

JPM Title: Terminate SI per ES-1.1

..tPM Number: RO Admin 1-1.

KA Number and Importance: 2.1.19 Ability to use plant computers to evaluate system or component status. RO - 3.9; SRO - 3.8.



Alternate Path: NO

Time Critical: NO

Estimated Time: 20 minutes Actual Time: ___

References: 2-WCR-1, Reactivity Summary 2-GRAPH-RPC-6, Core Operating Limits Report

File: 2000770S21-1.doc Time: 20 minutes

Task Number: 2000770S01 2-WCR-1 Administrative

Calculate Shutdown Margin with Untrippable Rod Page 3 of 8

INITIAL CONDITIONS:

During performance of 2-PT-Q089 Control Rod Exercise Test, Rod F-14 did not move. I&C has determined that the rod is mechanically bound in place (Untrippable).

INITIATING CUES:

The CRS has directed you to Calculate Shutdown Margin with an Untrippable Rod using WCR-1 Page 2 Steps 1-11.

Current Plant Data: Cycle Burnup 999 MWD/MTU Current Boron concentration 1140 ppm Relative Power 100%

TASK STANDARD:

Shutdown Margin Calculation complete. CRS informed of results.




Page 4 of 8

til Denotes Critical Step



Commence evaluation 1.

2. Obtain Correct Procedure

'3. Go to Indian Point Energy Center web page and select Operations Department

On the Operations Web Page select Unit 2 .4. NuPOP

Select the "Run" button to Open File li5.

.,6.

Observe NOTE before step 4

When Acrobat Reader is up, select .7. Bookmarks on the left pane then select '+' box associated with "B Supporting Excel Files" to Open the files

Select Table B-1, Summary of Supporting.8. Excel Files

Scroll down and select TPD7 File Name.xls .9. and Select open/enable Macros.

Enter current data for the following: 10.

• Cycle Burnup • Enter specific boron concentration ter Relative Power Record Total Power Defect on Line #1.ii11.

Go to Table B-1 Summary of Supporting Excel .12. Files, Select Shutdown Margin and Open when prompted to open spreadsheet

Select HZP SDM Rackup tab .13.

File: 2000770521-1.doc Task Number: 2000770501 2-WCR-1

STANDARD S/U

Record Time

Obtains current revision of 2-WCR-1

Log into a computer and open Operations web page.

"Click" on Unit 2 NuPOP

"Click" on Run button

Observes Note to leave spreadsheet open

"Click" '+' box

Select Table B-1

Select TPD7

See Below

Enter 999

Enter 1140

Enter 100

Record 1509

Select Shutdown Margin and Click Open when prompted

Select correct tab

Time: 20 minutes Administrative


STEP DESCRIPTIONS t CUES & NOTES Multiply row 11 value by 1000 and record on .14. Line 2

Enter 900 on Line 3 to account for Untrippable .15. rod

Add lines 1 - 3 to record Shutdown Margin .16.

Ensure Shutdown Margin is greater than value 17. in COLR

CUE: Examiner should hand candidate 2GRAPH-RPC-6 Core Operating Limits Report (COLR) when asked for.

Close Unit 2 NuPOP Excel Spreadsheets Do 18. not save data

..IPM is complete 19.

STANDARD StU

Records 5730

Enter 900

Calculate 3321

Determines SDM is greater than COLR

Close Spreadsheet does not save data

NA




Any area of weakness observed? YES Examinee Signature


Evaluator Initials






(Page 2 of 3)

CALCULATE SHUTDOWN MARGIN (SOM) AT POWER WITH AN UNTRIPPABLE ROD

1 , Determine Power Defect (+) 15~ PCM 2. Determine control bank worth and shutdown bank worth

with the most reactive rod cluster stuck out

3. In the event a rod is known to b& untrrppable. SDM verification must

account for the worth of the untrippabfa rod as weH as another rod of

maximum worth Cycle 19: (BOL=900; EOl=780)

4. Shutdown Margin {SR 3.1.1.1 bases} (total items 1 through 3)

1) IF desired to CALCULATE SDM at power with an untrippable rod,

THEN GO TO the indian Point Entergy Center web page

AND select (click. using the mouse) Departments and select (click) Operations.

2) On the Operations page, SELECT (click) Unit 21 Unit 2 NuPOP.

3) WAIT and when prompted, SELECT the 'Run' button to open the file.

NOTE

Leave the coefficients spreadsheet (CoeHa.xls) open while using the NuPOP.

4) WHEN the Acrobat Reader is up, SELECT Bookmarks on the left pane THEN SELECT the'+' box associated with "8 Sopporting Excel Files» to OPEN the files.

5) SELECT Table B·1, Summary of Supporting Excel Files.

6) To OBTAIN Power Defect, scroll down (second page) to select the 'TPD7' File Name.xls AND select open I finable Macros.

7) ENTER current data for the following (using the 'Tab' or T Of click the applicable box): a. Cycle 8urnup (MWO/MTU). b. Specified Boron Concentration (pcm).

c. Relative Power (%).

d. WHEN all the values are submitted, THEN RECORD on line #1 above, the Total Power Defect for ECP (pcm).

2-WCR-1 Answer Key RevS



of 8

INITIATING CUES:

During performance of 2-PT-Q089 Control Rod Exercise Test, Rod F-14 did not move. I&C has determined that the rod is mechanically bound in place (Untrippable).

The CRS has directed you to Calculate Shutdown Margin with an Untrippable Rod.

Current Plant Data: Cycle Burnup 999 MWD/MTU Current Boron concentration 1140 ppm Relative Power 100%

File: 2000770521-1.doc Task Number: 2000770501

Perform a Manual QPTR Calculation (3 Detectors 100%)

Page 1 of 10

ENTERGY (IP2)


Operator Name:

Employee 10 #:

Evaluator:

Date: SAT UNSAT



File: (0150071601.doc) Difficulty: 3 Time: 20 minutes SOP 15.3 DSR-4B Admin

Perform a Manual QPTR Calculation (3 Detectors 100% )

Page 2 of 10

JPM Title: Perform a Manual QPTR Calculation (3 Detectors 100%)

JPM Number: RO ADMIN - 1-2

KA Number and Importance: 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. RO - 4.3; SRO - 4.4



Alterl1ate Path: NO

Time Critical: NO


References:

2-S0P-1S.3, Quadral1t Power Tilt Calculation 2-DSR-4B, Unit Two Quadrant Power Tilt Calculation Sheet Technical Specifications


Perform a Manual QPTR Calculation (3 Detectors 1000/0)

Page 3 of 10

INITIAL CONDITIONS:

1. Reactor power is stable at 100% power.

2. There is indication of a misaligned rod.

3. The Control Power and Instrument Power fuses for Power Range Channel N-44 have been removed.

4. No Physics testing is in progress.

INITIATING CUES:

You are the BOP, and the CRS has directed you to Calculate QPTR with a misaligned control rod in accordance with SOP-15.3, Quadrant Power Tilt Calculations, step 4.2.

Determine if the calculated QPTR meets Tech Spec Limits and what compensatory actions, if any, are required to meet Tech spec Limits.

TASK STANDARD:

Quadrant Power tilt Ratio calculated based on given detector currents using Form DSR-4B and, any required actions by Tech Spec reported to the CRS including maximum allowable power operation and time limits.


Perform a Manual QPTR Calculation (3 Detectors 100%) Page 4 of 10

I; Denotes Critical Step

DESCRIPTIONS I CUES & NOTES

EVALUATOR NOTE: Give the examinee the attached Detector Current Data Sheet and a DSR-4B form that has the proper normalization factors recorded.

1 Obtain correct procedure and form DSR-4B.

2 Record top and bottom detector currents

3 Record Date, Time and Average Reactor Power

W4 DIVIDE each detector output by

corresponding normalization factor.

5 If three detectors are to be used in the calculation, change denominator from 4 to 3.

STANDARD StU

SOP 15.3, "Quadrant Power Tilt Calculation"

Detector currents recorded from QPTR Data Sheet

Current Date and Time and average Reactor Power of 100%

PERFORMS both of the following:

• CALCULATES normalization ratio

• RECORDS on form DSR-4B

[See Key for actual values]

RECORDS "3" for denominator on top and bottom average equations

File: (0150071601.doc) Difficulty: 3 Time: 20 minutes SOP 15.3 DSR-48 Admin


STEP DESCRIPTIONS I CUES & NOTES STANDARD SIU

,6 CALCULATE average normalized ratio for PERFORMS both of top and bottom the following:

CALCULATES the NOTE: QPTR to be calculated using 3 • top and bottom detectors normalized averages

• RECORDS on form DSR-4B


'7 CALCULATE Quadrant Power Tilt for top and PERFORMS both of bottom detectors the following: • CALCULATES the

top and bottom QPTR by using the highest top (bottom) and dividing by the top (bottom) average

RECORDS on form • DSR-4B


I/S RECORD highest Quadrant Power Tilt and RECORDS the highest

appropriate signatures. of the top or bottom

Quadrant Power Tilt

EVALUATOR NOTE: values as the QPTR on Signatures are not required for the form DSR-4B performance of the JPM. Continue on with the assigned task.

II I


11

Perform a Manual QPTR Calculation (3 Detectors 100% )

Page 6 of 10

STEP DESCRIPTIONS t CUES & NOTES STANDARD StU

.9 If quadrant power tilt exceeds 1.02 in either PERFORMS both of top or bottom of core, ensure requirements of the following: Technical Specification 3.2.4, Quadrant Power Tilt Limits are met.

1110 DETERMINE Required Tech Spec Actions.

REPORT to CRS both of the following:

• QPTR surveillance has been completed and the calculated value is greater than allowable Technical Specification

• List of required actions of T.S. 3.2.4,

• COMPARES the calculated QPTR to Tech Spec 3.2.4

• DETERMINES that the calculated QPTR is GREATER THAN the Tech Spec allowable value of 1.02.


PERFORMS both of the following:

• REFERS to Tech Spec action 3.2.4

• DETERMINES the following actions are required:

Within 2 hours,

a. Reactor Power must be reduced to below 75.7% ( ±O.5%)

Communicates results of QPTR calculation and TS actions of T.S . 3.2.4


i


Any area of weakness observed? YEsDNOD Examinee Signature


Evaluator Initials




------------------------ ------------------


UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. XX

Previous SNSC #XXXX XX/XXlXX (QT-20-05) DATE,-:____ SNSC REVIEW DATE TIME:

AVE REACTOR PWR:'----;;1""00,.--APPROVED (RE) DATE

USING DETECTOR OUTPUT CURRENT APPROVED DATE

Current QT number and Normalization Factors provided by Reactor Engineer.

1. Determine normalized ratios by dividing indicated detector current by normalization factor as follows: [ITS] Technical Requirements ManuaI3.2.A:

Channel Det Current Nor Ratio


41 Top = 41T = 128.1 I*~=---".;..;:..;;;..-,-,-_ 41 Bottom=41B=_.L-,",,~_1"107.4= 1.0512

42 Top = 42T =_QQ"Z_ 1* = 1.0389 42 Bottom =42B =_lilllL 1* 104.8 = 10410 43 Top = 43T =_~~_ I" 115.0 =--~""'-!..'--_ 43 Bottom = 43B =_-'-=~_ 1* 113.4 =~~~~

44Top=44T= 1*113.0 = OOS 44 Bottom = 44B =

2. Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top = ANRT = 41T + 42T + 43T + 44T= 1.0008 4

Average Normalized Ratio Bottom = ANRB = 41 B + 42B + 43B + 44B=_~..:.=,,--_ 4

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio. [ITS] Technical Requirements ManuaI3.2.A:

Quadrant Power Tilt Top = QPTI = Highest value of 41T, 42T, 43T, or 44T

ANRT

Value= 1.0819

QPTI = ANRT = 1.0008 = 10810

--~~~----------------

Quadrant Power Tilt Bottom = QPTB = Highest value of 41 B, 42B, 43B, or 44B

ANRB

Value = 1.0512

QPTB = ANRB = 1.0125 =

--~~~-----------------

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200. [ITS] Technical Requirements ManuaI3.2.A:

Enter the Higher QPT(Top or Bottom) = 1. 0 8 1 0

Technical Specification Limit = -1. 0 2" -0 0

NOTES:

1. If the quadrant power tilt exceeds the Tech, Spec. limits, the SM. OM, RE and GM-NPG shall be informed ASAP.

2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

RO: SM:

Page 1 of 1


Perform a Manual QPTR Calculation (3 Detectors 100%)

Page 9 of 10

Detector Current Data Sheet for QPTR Calculation

Average Reactor Power 100%

Channel Detector Nor Ratio Detector Nor Ratio "TOP"

Current TOP "BOTTOM"

Current I BOTTOM

N-41 128.1 1.0819 112.9 1.0512 N-42 90.7 1.0389 109.1 1.0410 N-43 101.4 0.8817 107.2 0.9453 N-44 OOS OOS OOS OOS

Normalization Factors: 41T-118.4 418 107.4 42T 87.3 428 104.8 43T 115.0 438 113.4 44T 113.0 448 117.4

QPTT = 1.0819/1.0008 1.0810

QPT8 =J.0512/1.0125 1.0382

QPTR = 1.0810

A Power reduction is required per Tech Specs. Maximum core power equals, 100% - (3 x 8.1) = 100% - 24.3% =75.7% (± 0.5%) acceptable.


of 10

INITIAL CONDITIONS:

1. Reactor power is stable at 100% power.

2. There is indication of a misaligned rod.

3. The Control Power and Instrument Power fuses for Power Range Channel N-44 have been removed.

4. No Physics testing is in progress.

INITIATING CUES:

You are the BOP, and the CRS has directed you to Calculate QPTR with a misaligned control rod in accordance with SOP-1S.3, Quadrant Power Tilt Calculations, step 4.2.

Determine if the calculated QPTR meets Tech Spec limits and what compensatory actions, if any, are required to meet Tech spec limits.


of 10

Detector Current Data Sheet for QPTR Calculation

Average Reactor Power 100%

Excore Instrument Detector "A" Detector "B" N-41 128.1 112.9 N-42 90.7 109.1 N-43 101.4 107.2 N-44 Blank Blank


---------------------

----------------- ------------------

Page 12 of 10

UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. XX

Previous SNSC #XXXX XX/XX/XX (QT-20-05) DATE'--____ SNSC REVIEW DATE TIME

AVE REACTOR PWR'-----APPROVED (RE) DATE

USING DETECTOR OUTPUT CURRENT APPROVED DATE

Current QT number and Normalization Factors provided by Reactor Engineer.

1. Determine normalized ratios by dividing indicated detector current by normalization factor as follows: [ITS] Technical Requirements Manual 3.2.A:



41 Top=41T= /* 118.4 = 41 Bottom = 41B = 1* 107.4 =

42 Top = 42T = I*~= 42 Bottom = 42B = 1* 104.8 =

43 Top = 43T = 1* 115.0 = 43 Bottom = 43B = 1* 113.4 =

44 Top = 44T = 1* 113.0 = 44 Bottom = 44B = 1*117.4=

2. Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top = ANRT = 41T + 42T + 43T + 44T=_____ 4

Average Normalized Ratio Bottom = ANRB = 41 B + 42B + 43B + 44B=_____ 4

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio. [ITS] Technical Requirements Manual 3.2.A:

Quadrant Power Tilt Top = QPTT = Highest value of 41T, 42T, 43T, or 44T

ANRT

Value =

QPTT= ANRT= ---=

Quadrant Power Tilt Bottom = QPTB = Highest value of 41 B, 42B, 43B, or 44B

ANRB

Value =

QPTB = ANRB = --- = _________________

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200. [ITS] Technical Requirements Manual 3.2.A:

Enter the Higher QPT(Top or Bottom) = __ . ______ __

Technical Specification Limit = 1. 0 2 0 0

NOTES:

1. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be informed ASAP.

2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

RO: SM:

Page 1 of 1


of 10


..

Prepare a Tagout Page 1 of 15

ENTERGY (IP2)


Operator Name:

Employee 10 #:

Evaluator:

Date: SAT UNSAT





. ,

Prepare a Tagout

Page 2 of 15

",IPM Title: Prepare a Tagout for 21 SI Pump

JPM Number: RO Admin 2-1

KA Number and Importance: 1940012213, Equipment Control Knowledge of tagging and clearance procedures. RO - 4.1; SRO - 4.3



Alternate Path: NO

Time Critical: NO


References: • EN-OP-102, Protective and Caution Tagging • EN-OP-1 02-1, Protective and Caution Tagging Forms &

Checklist • 208088 One Line Diag of 480V Switchgear 21 & 22 8us 2A,

3A, 5A, 6A • 225134 Elementary Wiring Diagram of Safety Injection

Pump 21 • 208500 One Line Diagram for 480V MCC-26AA and MCC

2688 & 120VAC Distribution Panels 1 & 2 • 241171 Control Room Panel S8-2 • 9321-2735 Flow Diagram Safety Injection System




INITIAL CONDITIONS:






INITIATING CUES:

You are a spare operator and the SM has directed you to prepare a manual tagout for 21 Safety Injection Pump using EN-OP-102 and EN-OP-102-01.

TASK STANDARD:

Manual Tagout Complete and ready for review.




•• Denotes Critical Step

STEP DESCRIPTIONS t CUES & NOTES



Obtain Correct Procedure 2.

Ensure requirement of Attachments 9.1 and 3. 9.2 of EN-OP-1 02 are followed

Review Scope of Work4.

Review Tagging Requirements 5.

Determine Safe Work Boundary for 21 SI Pump Seal replacement .6.

Boundary Valves should be reviewed for outstanding deficiencies

7. CUE: No deficiencies exist on valves identified in tagout boundary

Complete Attachment 9.1 and 9.2 of EN-OP.:8. 102-01

STANDARD StU

Obtains EN-OP-102

EN-OP-102-01

Review Attachment 9.1 and 9.2

Tagout Required for emergent work

Tagout Required for emergent work

Review Plant Prints 208088 225134 208500 225134 241171 9321-2735

Determines no outstanding deficiencies

See Attached Answer Key



9.

i10.

.11.

.12.


Utilizing the Isolation Boundaries, Prepare the tagout For each tag include:

• Tag Serial Number • Tag Type

Equipment• • Equipment Description • Equipment Location • Placement Sequence • Placement Configuration

Tag Type: Danger

Component: 21 Safety Injection Pump 480V Bus 5A Control Switch


Desired Position: Pullout

Sequence 1

Tag Type: Danger

Component: 21 Safety Injection Pump Breaker Control Fuses


Desired Position: Removed/Off

Sequence 2

Tag Type: Danger

Component: 21 Safety Injection Pump Breaker


Desired Position: Racked Out

Sequence 3

See attached Answer Key

I

Enters data on form

Enters data on form

Enters data on form



113.

.14.

.15.

.16.


Tag Type: Danger

Component: MOV-850A 21 SI Pump Discharge Valve


Desired Position: Closed/Neutral

Sequence 4

Tag Type: Danger

Component: MOV-850A 21 SI Pump Discharge Valve Breaker


Desired Position: OFF

Sequence 5

Tag Type: Danger

Component: MOV-850A Manual Operator


Desired Position: Do Not Operate

Sequence 6

Tag Type: Danger

Component: SI-1807A 21 SI Pump Recirc Test Line Stop



Sequence 7

Enters data on form

Enters data on form

Enters data on form

Enters data on form




Tag Type: Danger

Component: SI-848A 21 Safety Injection Pump Suction Stop

i17. Equipment Location: Enters data on form SI Pump Cell


Sequence 8

Tag Type: Danger

Component: SI-1843A 21 SI Pump Thrust Balance Flow Line Stop

~18. Equipment Location: Enters data on form SI Pump Cell



Tag Type: Danger

Component: SI-7306-Cap - Cap downstream of drain valve 7306

~19. Equipment Location: • Enters data on form SI Pump Cell



Tag Type: Danger

Component: SI-730621 SI Pump Discharge Line Drain Stop

_:20. Equipment Location: Enters data on form SI Pump Cell


Sequence Not Critical I

•




Tag Type:

Danger

Component: SI-4274-Cap - Cap Downstream of vent valve 4274

tI.21. Equipment Location: SI Pump Cell



Tag Type: Danger

Component: SI-4274 21 SI Pump Casing Vent Stop

Equipment Location:.22. SI Pump Cell

Desired Position:

Open

Sequence

Not Critical

23. Complete Manual Tagout Index Sheet

24. Complete T agout Cover Sheet

JPM is complete

Enters data on form

Enters data on form

Lists 21 81 Pump on index sheet

Fill in: Clearance - Given 2C20 Tagout: Given 51-001 Component to be Worked 21 SI Pump

. Description: I See attached Key




Any area of weakness observed? YES Examinee Signature


Evaluator Initials





of 15

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENTEntergy MANUAL INFORMATIONAL USE PAGE 5 OF 25

Protective and Caution Ta Forms &Checklist


CLEARANCE ________


SI-001 21 Safety Injection Pump Seal

Answer Key


----------------------

Page 11 of 15

NUCLEAR NON-QUALITY RELATED EN-OP-102-01 REV. 6 MANAGEMENT-E"tn ergy ~--MANUAL INFORMATIONAL USE PAGE 6 OF 25



Clearance: 2C20 MANUAL Tagout: 51-001

Component to be worked:

21 SI Pump

Description

21 SI Pump has a seal leak. Tagout and drain pump for seal replacement

Placement Inst:

See Attached Answer Key

Hazards:

See Attached

Restoration Inst:

See Attached

I Attribute Desc~iPl:..lt=-io:...::n-=--__________I---_____---,-A.::.:;ttc:.:.r..:..:ib:...::u.:..:.te-=-..:..Vc:.:.a.:..:.lu;..;;;.e_~~____-1

Status Description User Verification Date Prepared Prepared Technical Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung ~.......

Removal Approved • Removal Approved

Tags Verified Removed Tajls Verified Removed

File: 2000391601-1.doc Parent Task # 200"039*01*01

http:A.::.:;ttc:.:.r..:..:ib:...::u.:..:.te-=-..:..Vc:.:.a.:..:.lu

of 15

NUCLEAR NON-QUALITY RELATeo EN-OP-102·01 REV.S

MANUAL MANAGEMENT

INFORMATIONAL USE PAGE 7 OF 25

Protective and Caution Ta ging Forms & Checklist ~ ~~~"~"""""-~"'~~~,~~~~,-~~~=

ATTACHMENT 9.3 TAGOUT TAGS SHEET ~~_~=_==-~"~"~~~____~~~====m==-____============~~=======____========~~~====~==__~u====-==~=-========

CLEARANCE: _MANUAL Jt,jo

Description

Location

Answer Key

3

/;

File:


I

Page 13 of 15

NUCLEAR NON-QUALlTY RELATED EN-OP-102-01 REV. aMANAGEMENTe I

-::~:::- Enter.ay MANUAL .~ INFORMATIONAL USE PAGE 7 OF 25


""'~-.~-~. ---"'-"".,,---~.--- -----.-~.---"'- ...----~..-..~=~-=~==== ATTACHMENT 9.3 TAGOUT TAGS SHEET

-=======-====-~---=~=---==~==~--~--=====--=-=====~-=--=-==--~~====-

CLEARANCE: _MANUAL ,J t ~o TAGOUT: Equipment 1st Rest. 2nd Placemen.u/ Equipment Description Verif Verif Removal~~I Equipment Location Date/Time >-/T";--T",g Note~____

--II Ans~er Keyq I ... "-~·--i------' 1/-----+----~

to IL-f--I --1-1

I I File:


of 15

NUCLEAR.... MANAGEMENT NON-QUALITY RELATED EN-OP-1 02-01 REV. 6 I===-[' MANUAL--:-:::- "jll1erlXY

Documents

Review 2-WCR-1 Reactivity Summary Calculation ENTERGY (IP2) … · 2012. 12. 3. · Review 2-WCR-1 Reactivity Summary Calculation . Page 3 of 15 . INITIAL CONDITIONS . An RO has prepared