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Text

Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML103080923
Person / Time
Site:	Indian Point
Issue date:	08/13/2010
From:	; NRC Region 1
To:	; Entergy Nuclear Operations
	Hansell S
Shared Package
ML100980645	List: IR 05000286/2010301; ML102670379; ML102720572; ML103080903; ML103080910; ML103080920; ML103080923; ML103090017; ML103090020; ML103090036; ML103090054; ML103410223;
References
	TAC U01789
	Download: ML103080923 (213)
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Review a Gross Leakrate Determination Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 2000051602.doc Difficulty:

3 Time: 20 Task Number: 2000050102 0-SOP-LEAKRATE-001 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 judgments based on operating characteristics, reactor and instrument SRO Suggested Environment:

Classroom Actual Testing Environment:

Alternate Path: NO Time Critical:

NO Estimated Time: Actual Time:

References:

o SOP LEAKRA TE-001 RCS Leakrate Surveillance, Evaluation and Leak Identification File: 2000051602.doc Difficulty:

3 Time: 20 Task Number: 2000050102 0-SOP-LEAKRATE-001 Review a Gross Leakrate Determination Page 3 of INIl"IAL CONDITIONS:

The plant has been operating at 100% Power for 200 An increase in containment humidity has been An RO performed a Gross Leakrate Determination in accordance with LEAKRA Non-RCPS Leakage from previous evaluation 0.15 Previously identified leakage from previous evaluation 0.03 INITIATING CUES: You are the CR8 and the 8M has directed you to review the Gross Leakrate Determination.

TASK STANDARD:

Gross Leakrate Calculation reviewed and errors found. File: 2000051602.doc Difficulty:

3 Time: 20 Task Number: 2000050102 0-SOP-LEAKRATE-001 Review a Gross Leakrate Determination Page 4 of 10 I Denotes Critical Step DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Obtain current copy of procedure

3. Evaluate Manual Calculations

14. Calculate Total Time Calculate Change in Mass due to Change in 5. Pressurizer Level Calculate Change in VCT Mass due to change 6. in level Calculate Change in RCS mass due to change 17. in Tavg 18. Calculate Gross Leakage 19. Calculate Gross Leakage LR1 110. Calculate Unidentified Leakage 111. Candidate does Not Sign the form i 12. JPM Complete STANDARD Candidate will be given the procedure See Below Determine Total Time is 127 minutes NOT 137 minutes Determine 6.26 gallons is correct Determine 104.48 gallons is correct Determine

-8.64 is incorrect it should be + 8.64 gallons Determine 102.1 is incorrect; it should be 119.38 gallons Determine 0.74 gpm is NOT correct; it should be 0.94 Determine 0.56 gpm is NOT correct; it should be 0.76 gpm File: 2000051602.doc Difficulty:

3 Time: 20 Task Number: 2000050102 O-SOP-LEAKRA TE-OO 1 Review a Gross Leakrate Determination Calculation Page 5 of 10 No: o-SOP*lEAKAATE-001 Rev: 1 RCS LEAKRATE EVALUATION AND LEAK Page 49 of 63 CALCULATING GROSS RCS (Page 1 of Date: TC1)A PERFORM this attachment only when PZR is!: 2200 psi and .s. 2245 pel, Q.B TAVG is!: 563 OF ANC T AVG is within +/-1.5°F from T AlP. RCS Manual Leakrate Calculation Worksheet:

Circle one: YntU (): Indicates mathematical sign must be observed.

.) CALCULATE total tlrM [TJ Answer Key Final: Time I :3. : d Initial: Timtl * , Co; I Elapsed Tme \37 )J '1 mtnul.. b) Change In RCS mass due to change In PZA Level [AJ. [DJ Is normalized PZA volume change.

Level .....,:'1..,7..;;.0

____% InKlaI: PZA Level

_If..;..)_'

____% Olfference:

(-) r \ % x (-62.6 gtIII%) .. fl' .)k p[O] [A) 0) Change In vcr Masa due to change In vcr Level [B). [E] is the normalized VCT volume ctlange. Final: VeT Level ':)0. 'I ? Initial: VeT Level

___ Oifference:

__ %X(.19.1 11811%)=(1-)

gal IE)[8] Change In RCS Mass due to change In T AVE [C). (F] is normalized RCS Water Volume change. Final: T ,\\IE _ .....')...

..;;..D___ Initial: TAVIE ') r..S. .1

-+ 61.,'1 Oifference:

H (). I + \ OF X (86.444 gaII"F)

8. k[e] File: 2000051602.doc Difficulty:

3 Time: 20 Task Number: 2000050102 0-SOP-LEAKRATE-001

__________________________________________________

__ Review a Gross Leakrate Determination Calculation Page 6 of 10 No: o-SOP*LEAKRA TE-001 Rev: 1 RCS LEAKRATE SURVEILLANCE.

EVALUATION AND LEAK IDENTIFICATION Page 50 of 63 ATTACHMENT 2 CALCULATING GROSS RCS LEAKAGE (Page 20f 2) Answer Key CALCULATE:

Gross Leakage (gpm) [LA,}: '" [(Normalized values: ([D) + IE] + [F]) J 6 Time (minutes T)] 8-/.aI HlUi .. ([DJ

+ [EJ + lFU.b.L ). I OJ. ( (G) gal. Change in System Volume !lif.Jr

Ie).\ (OJ gal. JT * ",'/"' 0 .tJ gpm Gross Leakage [LAd a) RECORD Non-RCPS Leakage (from previous Evaluation (lAtD: 6, I)' gpm b) RECORD previously Identified Leakage (from previous Evaluation

[LAaD: 6 C' j gpm A positive number Indicates a net removel of mass from the '3.0 CALCULATE Unidentified O. N gpm -O. \[LAd RECORD [LAd and [LA UnldW1t1l'-ll on the applicable Ones of step 6.0.

Use two decimal places to the right of the decimal point for the final value (I **. 0.04 gpm). 1E there Is an unanticipated gross leakage Increase of 0.05 gpm. Qfllt has been 7 days Since section 4.4 or 4.5 was lasl performed, PERFORM section 4.4, or 4.5 ReS Leak Rate Evaluation as soon 8S practical.

a) REFER TO Section 4.3, for Review and Approval of Gross Leakage Calculation.

b) WHEN section 5.0 is completed.

I!:!.Sl:{

PLACE completed rorms in appropriate CCR binder. Gross Leakage [LR,): 0.1'\-Q.N gpm Unidentified Leakage [LR t' . 'H... 0.1'" gpm Performed by:

C:¥:",I<" l2'qp4t\ (,Pl.""'!"+" ,1>t1KfF (RO) Reviewed by:--:::-:-:

_______-=---:-_______(CRSlSM) Print name Signature Oaw)

File: 2000051602.doc Difficulty:

3 Task Number:

Time: 20 minutes 0-SOP-LEAKRATE-001 Administrative Review a Gross Leakrate Determination Calculation Page 7 of 10 Any area of weakness observed?

YES D NoD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information:

File: 2000051602,doc Difficulty:

3 Time: 20 Task Number: 2000050102 0-SOP-LEAKRATE-001 Page 8 of 10 INITIAL CONDITIONS:

The plant has been operating at 100% Power for 200 An increase in containment humidity has been An RO performed a Gross Leakrate Determination in accordance with Non-RCPB Leakage from previous evaluation 0.15 Previously identified leakage from previous evaluation 0.03 INITIATING CUES: You are the CRS and the SM has directed you to review the Gross Leakrate Determination. Task Page 9 of 10 No: 0-SOP-LEAKRATE-001 Rev: 1 RCS LEAKRATE EVALUATION AND LEAK Page 49 of 63 ATTACHMENT CALCULATING GROSS RCS (Page 1 of Date: 1"D6 \{ NOTE: PERFORM this attachment only when PZA is 2200 psi and ;s 2245 psi, .QI! T"VG is 2. 563 of AND TAVG is within +/-1.5°F from TFIEJI. RCS Manualleakrate Calculation Worksheet:

Circle one: Unit (): Indicates mathematical sign must be observed * ) CALCULATE total time {TJ Final: Time I d.. : ,]. Initial: Time -, C: Elapsed Time --=-'_3:.....l7

___ mlnut.. Change In RCS mass due to change in PZR level [A]. (D) Is normalized PZR volume change. Final: PZR Level q 7. 0---.;...;..;....-----

% Initial: PZA Level -In. I % Difference:

% X ( -62.6 gaII%) =(t)'....J':.;.:.,q..;.:..,)=k

__gal [D) [AJ 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 )').'$

Difference:

t-) ') }*C) % X (-19.1 gall%) =-M 4 j gal [E]Change In RCS Mass due to change in T AVE (e]. [F] is normalized ReS Water Volume change. Anal: InHial: TTask Page 10 of 10 No: O-SOP-LEAKRA TE-001 Rev: 1 RCS LEAKRATE SURVEILLANCE.

EVALUATION AND LEAK IDENTIFICATION Page 50 of 63 ATTACHMENT CALCULATING GROSS RCS (Page 2 of CALCULATE:

Gross Leakage (gpm) [LR1]: ={(Normalized values: ([D) + (El + [FJ) I A Time (minutes 1)] =([DJ L.2L+ [E] + [F1.:.1J:.L)

III I Dd., (G) gal. Change In System Volume ... I tJ). I (G) gal. I T... C*7 tJ gpm Gross Leakage [LAd a) RECORD Non-RCPS Leakage (from previous Evaluation

[LRiI): t, I ') gpm b) RECORD previously Identified Leakage (from previous Evaluation

[LR,D: C,.O) gpm A positive number Indicates a net removal of mass from the system. -3.0 CALCULATE Unidentified Leakage: gpm-D.'<; gpm.

gpm [LA,l [LR,] RECORD [LAt] and [LA unlden1ltltodl on the applicable nnes of step 5.0. Use two decimal places to the right of the decimal point for the final value (I.e. 0.04 gpm). IF there Is an unanticipated gross leakage increase of 2: 0.05 gpm, QB it has been 2: 7 days since section 4.4 or 4.5 was laat perlormed.

I.!::l.&r!

PERFORM section 4.4, or 4.5 RCS Leak Rate Evaluation as soon as practical. REFER TO Section 4.3, for Review and Approval of Gross Leakage Calculation. WHEN section 5.0 is completed, THEN PLACE completed forms in appropriate CCR binder. Gross Leakage [LA,): D ,1-; gpm Unidentified leakage [LA UIlIcI.mIflllCl):

b.';L* gpm Perlormed by. .ldl"

'J\'(" 12'11 cit? t 6f!,pdbt \'.b f 14tp (RO) Reviewed

______---=:_________....",-__

Print name Signature

__________________________________________________________Task Review Reactor Vessel Venting Time Calculation per FR-1.3 Page 1 of 8 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This ..IPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0001251602-1.doc Difficulty:

2 Time: 15 Task Number: 0001250502 3-FR-1.3

, , Review Reactor Vessel Venting Time Calculation per Page 2 of JPM Title: Review Reactor Vessel Venting Time Calculation per FR-I.3 JPM Number: SRO A 2 KA Number and Importance:

1940012125 Conduct of Operations

-Ability to interpret reference materials such as graphs, curves, tables etc. SRO-4.2 Suggested Environment:

Actual Testing Alternate Path: Time Critical: Estimated Time: Actual Time: __

3-FR-1.3 Response to Voids in Reactor Vessel File: 0001251602-1.doc Difficulty:

2 Time: 15 Task Number: 0001250502 3-FR-1.3 Review Reactor Vessel Venting Time Calculation per FR-1.3 Page 30fa f" INITIAL CONDITIONS: , An event occurred 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. The TSC has calculated Reactor Vessel Venting Time in accordance with FR-1.3 Attachments 4 and 5 using the following information.

Containment pressure 2.5 psig Containment temperature 160°F Containment hydrogen conc 1.0% RCS 1000 psig INITIATING CUES: You are the CRS and the SM has directed you to review the Reactor Vessel Venting Time calculation.

TASK STANDARD:

Calculation reviewed and errors identified.

File: 00012S1602-1.doc Difficulty:

2 Time: 15 Task Number: 0001250502 3-FR-1.3 I Review Reactor Vessel Venting Time Calculation per FR-1.3 Page 4 of 8 Denotes Critical Step STEP DESCRIPTIONS I CUES &NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Obtain Current Rev of Procedure 13 Determine Containment Volume at STP (A) Determine Maximum Hydrogen volume that can be vented (8) .14 Note this is incorrect because previous calculation was incorrect.

Determine Hydrogen flow rate as a function of 15 RCS pressure (C) Calculate maximum venting time Note this is incorrect because previous calculation was incorrect.

JPM Complete ! STANDARD S/U Candidate will be given procedure Calculates 2.40E6 to 2.45E6 Determines TSC did not add 460 0 Calculate 4.845E4 to 5.0E4 2800 to 2950 Calculate 15 to 18 minutes File: 0001251602-1.doc Difficulty:

2 Time: 15 Task Number: 0001250502 3-FR-1.3 Review Reactor Vessel Venting Time Calculation per FR-I.3 Page 5 of 8 NII.,r: IReV!Slon Nw.oer: 0 3-FR-J.3 10 V010S 1M REACTOR VESSEL h ttac IIS18UCTI015 fOB DETERMINING YENTING TIME Att'Ule°t__ 4 (A hlllen*page 1 of 1) 1. DETERMINE Contain.ent Volu.. It ST' -A J( __.:%.4",92"=-;-"R"--_A -( 2.61x106 Ft3 ) x psia T -Containment pressure (psig) + 14.7 -Containment temperature(*F)

+ 460 A -( 2.6lxl06 Ft3 ) x ____ x 14.7 psiil A .JA:lXJu"Ft3

2. DETERMINE Max1.ua-Hydrogen YO 1 u.. that can be vented -B , ".:>> Containment Hydroaen Concentration) x A'i. laOS <} 4. 8 3. DETERMIN[

Hydrogen flow rate IS I funct10n of Res pressure -C a. CHECK ReS pressure.

DETERMINE Hydrogen flow rate using Attachment

5. HYDROGEN FLOW RATE b. VERSUS ReS PRESSURE, Page 29. c .. :J'icl' SCFM Maximum venting time venting time -

minutes Answer Key 'END OF " Page 28 of 29 File: 0001251602-1.doc Difficulty:

2 Task Number: 0001250502 Time: 15 minutes 3-FR-1.3 Administrative Review Reactor Vessel Venting Time Calculation per FR-I.3 Page 6 of 8 Any area of weakness observed?

YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information:

File: 0001251602-1.doc Difficulty:

2 Time: 15 Task Number: 0001250502 3-FR-1.3 Page 7 of 8 INITIAL An event occurred 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. The TSC has calculated Reactor Vessel Venting Time in accordance with FR-1.3 Attachments 4 and 5 using the following information.

Containment pressure 2.5 psig Containment temperature 160°F Containment hydrogen conc 1.0% RCS 1000 psig INITIATING CUES: You are the CRS and the SM has directed you to review the Reactor Vessel Venting Time calculation. Task Page 8 of 8 NlllN:ler:

Title: 3-FR-1.3 RESPONSE TO VOIDS IN REACTOR VESSEL Atttchaent

! (Attachment page 1 of 1) INSTRUCTIONS FOR DETERMINING VENl186 TIME 1. DETERMINE ContainMent Yolu.e at SIP -A A -( 2. 6lxl 06 Ft3 ) X _____ X __..:z.49....

14.7 T P (psig) .. Containment pressure (psig) + 14.7 I(OB) -Containment temperature(*F)

+ 460 A -2.6lxl06 Ft 3 ) )Ii \1. ;t x 492-8 14.7 psia I 1,., [J t A ..

'" IC Ft3 2. OETERMINE Max1Mu. Hydrogen voluMe that can be vented -B B -.\.(..t3SL-.=:........cCI<,lQa.nl..kt.2,a J..Ji

]OOS B .. _L.;.t..;;.;.'6*...:.7..1-1

......1 k <)_-__.... Ft3 3. DETERMINE Hydrogen flow rate 85 8 function of ReS pressure -C CHECK ReS pressure. DETfRM1NE Hydrogen flow rate using Attachment 5, HYDROGEN FLOW RATE VERSUS ReS PRESSURE.

Page 29. c -__1_C;..;i L;.,.*'_{!

____ SCFM 4. CALCULATE maxiMUM venting tiae: Maximum venting time -venting time --..>to"-.z'-l..:,..;...-

....l__ min ut e s r -END OF ATTACHMENT-Task Review a Safety Function Determination Page 1 of 13 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 2000451602-1.doc Difficulty:

4 Time: 30 Task Number: 2000450102 OAP-34 Review a Safety Function Page 2 of JPM Title: Review a Safety Function Determination JPM Number: SRO-A-2 KA Number and Importance:

1940012237 Equipment Control Ability to determine operability and/or availability of safety related equipment.

RO -3.6, SRO -4.6 Suggested Environment:

Classroom Actual Testing Environment:

Alternate Path: NO Time Critical:

NO Estimated Time: Actual Time:

References:

OAP -34 Safety Function Determination Process Technical Speci'fications Section 3.8 Technical Specifications Section 3.5 File: 2000451602-1.doc Difficulty:

4 Time: 30 Task Number: 2000450102 OAP-34 Review a Safety Function Determination Page 3 of 13 INITIAL CONDITIONS:

Unit 3 is operating at 100% Power 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . This was the only Active LCO at that time. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 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.S.1.

The ST A prepared a Safety Function Determination in accordance with OAP-34. The STA has determined that the minimum equipment to mitigate an accident is operable and that no loss of safety function exists. INITIATING CUES: You are the CRS and the Shift Manager has directed you to review the Safety Function Determination.

TASK STANDARD:

The Safety Function Determination is reviewed and errors identified.

File: 2000451602-1.doc Difficulty:

4 Time: 30 Task Number: 2000450102 OAP-34 I Review a Safety Function Page 4 of 13 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 Review Data Entered on Form Identify Tech Spec required Supported

2. Systems entered in D Identify Systems supported by the system 3. listed in D above entered in E Identify all systems supported by the systems 4. listed in Block E above Identify any systems redundant to those 5. systems identified in D, E, and F above that are tracked by active LCOs entered in G Identify systems supported by systems listed 6. in G above entered in H Identify the systems supported and affected by 7. the systems listed in H Entered in I Identify redundant systems listed between 8. blocks D, E, & F, and G, H, and I Review the minimum equipment required to jl8. mitigate an accident operable 49. Review Loss of Safety Function STANDARD StU Determine 3.5.2 and 3.8.9 are correct Determine 3.7.5, 3.7.8,3.7.9,3.7.11 , 3.7.13, 3.8.1, 3.8.4, 3.8.7 are correct Determines 3.4.4, 3.52.,3.7.8,3.7.12 ,

3.8.1, 3.8.9 are correct Determine 3.5.2 is correct Determine None is correct Determine None is correct Determine 3.5.2 is correct Determine Block K is NOT correct Determine Loss of Safety Function NOT correct File: 2000451602-1.doc Difficulty:

4 Time: 30 Task Number: 2000450102 OAP-34 Review a Safety Function Determination Page 5 of 13 S"rEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Do Not Sign Safety Function Determination 110. Does Not sign Form JPM is File: 2000451602-1.doc Difficulty:

4 Time: 30 Task Number: 2000450102 OAP-34

--Review a Safety Function Page 6 of \ No: OAP-034 Rev: 2 SAFETY FUNCTION PROCESS I Page 12 of AnACHMENT Safety Function (Page 1 of SAFETY FUNCTION DETERMINATION A. Inoperable system: S""e'" (.

f! It' ,

OR Number: Safety (S,C,H,P,Z,I).

ref. step 6.3. C \4-'Z. ; TS

/3,.8" \ Technical Speclflcation Related: Il?' Yea 0 No Support system: o;r" Yes el No List all systems supported by the Inoperable system Identified above: , .J!20tlist all systems supported by the systems listed In block 0 above: 3.j,,!) 3,1 3* 7, g 3 , <<, 3./*" 2*"7* /I 3 I j List all systems supported by the systems listed In block E above:

3.¥. 3 1 5 2-..... _.

__

317. Review the active LeO Log and list any systems redundant to those systems identified blocks D. E. & F that are tracked by active 3.15 ... ..----

_... ..... >'" --.-----,,,----.------._----,_._---.....-__.. w_.._._.. w ..... _.,

__"._.-,w Time: 30 minutes File:

Difficulty:

4 Administrative Task Number: 2000450102 OAP-34

Review a Safety Function Page 7 of I I No: OAP-034 Rev: 21\ SAFETY FUNCTION DETERMINATION I Page 13 of 37 L.__...ATTACHMENT Safety Function (Page 2 of SAFETY FUNCTION oeTERMINATION List the system. supported by the svstems listed In block G above: No Nt.: Lilt the systems $Upported .ffected by the systems listed In block H above: w/<wHl_--L../<

___jJ{N*)IJVV RS

< Identlfy redundant systems listed between blocks D, E, " F Af:!Q. G. H.a I above: 3,5 '2.. ------.---------'s the minimum equIpment requIred to mitigate an accident ut'Yys 0 No If the minimum equipment required to I. not 0 able the Lo.s of Safety FunctIon exists. / A< \ Doe** Lo** of Sarety i=unctlon exist? ( 0 Yes lntoflt' cIf a Losl of Safety Function eXists, then th tlons of the LeO in which the Lo ** < Safety Function Review/Approval: f 1 ,,"""'" \ '" t A \ .'I Prepared by: t_l ..... \ e (.\,\... 'e."" J4...1V"t.'V

$') ",-c!. <<i-]:J,\ kid ISTA) Nama 1;gnature ReViewed by:

! I <',-SRO (Current) Signature Date Time: 30 minutes Difficulty:

4 File: Administrative Task Number: 2000450102 Review a Safety Function Page 8 of Rev: 2 SAFETY FUNCTION DETERMINATION PROCESS 6.2 Minimum Equipment 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 I

'" ... __<-"",_... , ..",.,.., __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 Technical Specification Shutdown Sections.

The minimum equipment required is determined based on Technical Specifications.

plant status, and plant configuration.

63 Safety Function A function described or specified in the Technical Specification Bases Section "Applicable Safety Analysis", FSAR -Chapter 14, Design Basis Documents, or Accident 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,ReS integrity, containment integrity.

and ReS inventory.

File: 2000451602-1.doc Difficulty:

4 Time: 30 minutes Administrative Task Number: 2000450102 OAP-34 Review a Safety Function Determination Page 9 of 13 f SAFETY FUNCTION DETERMINATION I NO:'OAP-034 Rev: 2! PROCESS i Page 7 of 37 1 I L._____________. _ ..__________

....1._._.

___...._____._.___J 4.2.5 REVIEW the active LCOs, to identify any systems that are redundant to those entered in 0, 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 aU systems supported by systems entered in H. 4.2.7.1 RECORD these systems in "/" of Attachment

1. 4.2.8 ENTER any redundant systems identified during the evaluation in "J" 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 1he supported system(s).

Time: 30 minutes File: 2000451602-1.doc Difficulty:

4 Administrative OAP-34 Task Number: 2000450102 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 Task Number: 2000450102 OAP-34 Page 11 of 13 INITIAL CONDITIONS:

Unit 3 is operating at 100% Power 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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.B.1.

The pre-lube pump is expected back within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . This is the only Active LCO at time zero. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago 31 AFW pump was declared inoperable due to breaker control power fuses continuing to blow. The STA prepared a Loss of Safety Function Determination in accordance with OAP-34. INITIATING CUES: You are the CRS and the Shift Manager has directed you to review the Safety Function Determination. Task

Page 12 of 13 1 No: OAP.03_4__SAFETY FUNCTION I Page 12of37 -1..____ ATTACHMENT 1 Safety Function Determination (Page 1 of 2) SAFETY FUNCTION DETERMINATION A. Inoperable system: Reterence CR Number: Safety (S,C.H,P.Z.I).

ref. step TS Technical Specification Related: No Support system: No List all systems supported by the Inoperable system Identified above: .._.. _-_._...*._--_.. ---List all systems supported by the systems listed In block 0 above: ---""'--"'--'---'-----

---_.*... List all systems supported by the listed In block E above: Review the active LCO Log and list any systems redundant to those systems identified In blocks D. E, & F that are tracked by active lCOs: Task

Page 13 of 13 I* SAFETY FUNCTION DETERMINATION t No: OAP*034 !Page 13 of 37 ___1 ATTACHMENT Safety Function (Page 2 of SAFETY FUNCTION H. List the systems supported by the systems listed In block G above: List the systems supported M!Q affected by the systems listed In block H above: t-J e t>-.lf.. Identify redundant systems listed between blocks 0, E. & F AND G. H.a I above: 3,5 '2,., K. Is the minimum equipment required to mitigate an accident operable?

Yes 0 No I If the minimum equipment required to mitigate an accident Is not operable then a Loss 01 Safety Function exist *. l. Does It Los. of Safety Functlon exist? o Ves No If a Los. of Safety Function exists, then perform the Actions of the LeO in which the Loss of Safety Function exists. M. Review/Approval:

Prepared ReViewed by: SM/CRS/FSS SAO (Current)

Name--Signature Task Review a Manual Gaseous Rad Waste Release Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 2000181602-1 Difficulty:

3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 Review a Manual Gaseous Rad Waste Release Permit Page 2 of 8 JPM Title: Review a Manual Gaseous Rad Waste Release Permit JPM Number: SRO-A-3 KA Number and Importance:

1940012306 Ability to approve release permits. I SRO 3.8 Suggested Environment:

Classroom Actual Testing Environment:

Alternate Path: NO Time Critical:

NO Estimated Time: Actual Time:

References:

3-S0P-WDS-13 Gaseous Waste Releases File: 2000181602-1 Difficulty:

3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 Review a Manual Gaseous Rad Waste Release Page 3 of 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 !-Ici/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 TASK STANDARD:

Release Permit reviewed and errors found. File: 2000181602-1 Difficulty:

3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 Review a Manual Gaseous Rad Waste Release Permit Page 4 of 8 .. Denotes Critical Step DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Review Entered given data 13""'; . Calculate Total Activity 4. Calculate Available Release Rate 5. Determine Maximum Allowable Release Rate 6. Check Select Release Rate conservative Determine associated conservative percent lift 7. setting from Attachment 11 18. Determine calculated leakrate 9. Calculations are not correct JPM Complete STANDARD S/U Ensures given data properly entered Determine Total Activity Not Correct Correct Value 1.31 X 10 5 Determine Available Release Rate Correct Determines Maximum Allowable Release Rate is correct Selected release rate is conservative Selected percent lift setting is correct Determines Calculated Leakrate NOT correct Does Not sign the form File: 2000181602-1 Difficulty:

3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 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 GASEOUS WASTE RELEASE PERMIT (Page 1 of Current System (1) '3l L61)f OateITime (2) I DT)/:'l lL,PD Permit No. (3)_-,-I-e'

__Date Concentration I Volume (4) tt 3 Initial Pressure (5) I CD psig Tank! Noble Gas (C)(6),_..J.I Grab Date Tb'M Y Time I (,05 OR R-12 ",1,. Activity (A)(8): tf JlCI Noble Gas Iodine 131 Activity (Sa)-_..cYIIt.I%..-_--JI1CilCC

--1'5.l\ VC Purge Only Calculated Release Rate (R)(9 Ci/sec Available Release Rale (0)(10) uCilsec Discharge Monitor (11 ),__..IOdr:..l...L-

____ , Actual Alarm Set point (12) l>5);{O' I.lCi/sec Calculated alarm setpoint __---J1l Ci!t;ec Alert setpoint (14),______--IJlCVsec R-12 Auto Closure/Alarm Selpoints:

Calculated (15)__

Actual (16) J,>A JlCilcc IE discharge monitor is OOS, IHEN COMPLETE the following: Monitor (17) t,) b pieced out service CD _...-.J.J""-Z.).'-----_

__---JtJL:-.hc:..:!-Date Vent Sample:(18)

Sample # f.J A Date__

__ Time IJ A Results (19) N A. (NOble Gas) Vent flow rate (20) " etm Continuous Release Rate (CR)(21

__-IUCliSec Release Calculations verified by (22)____

______________

_ Release Path Valve Alignment Verified (23) ___________________

_ CRS/SM Discharge Authorized (24)_---:==:-:--

____ Release Start (25)_---:::--_

_---,.__ CRS/SM Date Time Final Pressure (26)______psig Release Stop (27)_---,,__

_ ___ Date Time Calculations Results: S (28)_____ Emax (29) 'DD E(30)_-:J..={,___ft 3 imin ACV-014 Set1mg (31)__

__% open Comments;(32),______________________________

_ File: 2000181602-1 Difficulty:

3 Time: 15 minutes Task Number: 2000180102 3-S0P-WDS-13 Administrative Review a Manual Gaseous Rad Waste Release Page 6 of Any area of weakness observed?

YES DNoD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information:

File: 2000181602-1 Difficulty:

3 Time: 15 Task Number: 2000180102 3-S0P-WDS-13 Page 7 of 8 INITIAL CONDITIONS:

Preparations are in progress to release 31 Large Gas Decay Tank The Tank is currently at 100 psig Gas Decay Tank Unpressurized Volume 525 Fe Grab Sample Number 35610 Concentration of Noble Gases 1.3 X 10-3 Current Radiation Monitor 27 Reading is 1 0 The BOP calculated a manual Release Permit INITIATING CUES: You are the eRS and the SM has directed you to review the Gaseous Waste Release Permit Task Page 8 of 8 -No: 3-S0P-WDS-013 Rev: 26 GASEOUS WASTE RELEASES Page 36 of 55 ATTACHMENT GASEOUS WASTE RELEASE PERMIT (Page 1 of 1) Current _Tank! System (1) 51 L6j)[ OatelTime (2) j OWN Permit No. (3) ___1_'___ Date Time Concentration of I .. Volume (4) 5J*f If Initial Pressure (5) 100 psig Noble Gas (C)(6) I * '3 KID-J,1Cllcc Grab Sample:(7)

Sample II 3:51.1O Date Tb'M V Time I kp"'f Q.B R-12 Monitor Activity (A)l8) ( .1 leX! () ., uCi Noble Gas Iodine 131 Activity VC Purge Only Calculated Release Rate (R)(9) '3 ,.Cilsec Available Release Rate (D){10) uCilsec Discharge Monitor {11 ) __....dL.,J....i-.

____ Actual Alarm Setpoint (12) 3.l>Z$)\{Q J,1Cilsec Calculated alarm selpolnt (13)_...:tJ-=-A

__-->IlCilsec Alert setpoln1 (14)______--'IlCVsec R*12 Auto Closure/Alarm Setpoints:

Calculated (15)__

Actual (16) f.l A IlCVce.... _____--JIlCilcc .I.E discharge monitor is OOS, I.t:i!ili COMPLETE the following: Monitor (17) tJ J',. placed out service 0 Date Vent Sample:(18)

Sample # t.J A Date__

__ Time bl A Results (19) N A !-lCVee {Noble Gas) Vent flow rate (20) N 1>.. elm Continuous Release Rate (CR)(21 )_--'-'l-d--'-/\

___-Illcllsec Release Calculations verified by (22),____....tJ.lI<-'"t.."'--

_______________

_ Release Path Valve Alignment Verified (23),______________________

_ CRSISM Discharge Authorized Release Start (25)_---:::,..-,-_

CRS/SM Dale Time Final Pressure (26) ______iPSlg Release SlOP (27)_--=:--_

Date Time Calculations Results: S (28) __,____ Emax (29) j 00 ? E(30) RCV*014 Setting (31)_---'4

......)(.....___% open Commen Is: (32) ______________________________

_ Task Classify E-Plan Event and Complete Part 1 Form Page 1 of 7 ENTERGY (IP2) JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 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 File: Difficulty:

Time: minutes Task Number: Procedure Ref category Classify E-Plan Event and Complete Part 1 Form Page 3 of7 This is a TIME CRITICAL JOB PERFORMANCE MEASURE. YOU HAVE 15 MINUTES FROM THE TIME YOU ARE TOLD TO BEGIN UNTIL YOU CLASSIFY THE EVENT YOU HAVE 15 MINUTES FROM THE TIME YOU CLASSIFY THE EVENT UNTIL YOU COMPLETE THE RADIOLOGICAL EMERGENCY DATA FORM. INITIAL CONDITIONS:

The Reactor and Turbine have tripped. Safety Injection automatically initiated due to a large break LOCA inside containment.

The following plant conditions exist: The team is responding in E-O, Reactor Trip or Safety Injection. Containment Isolation Phase A and B have been confirmed. 31 and 32 Containment Spray Pumps failed to start and attempts to start pumps was unsuccessful. 34 Containment Fan Cooler Unit was inoperable prior to the event due to circuit breaker maintenance Containment Pressure is 38 psig and stable R-25 reading 19 R/hr and R-26 reading 21 R/hr RVLlS, Natural Circ Range reading 44% METEOROLOGICAL CONDITIONS:

Wind Speed: 3.5 Wind Direction:

120 degrees @ 10 Stability Class: The Shift Manager is unable to get back to the control room. The MIDAS Computer is out of service for maintenance.

INITIATING CUES: You are the CRS and you must classify the event and complete the required Radiological Emergency Data Form as required by the Emergency Plan. TASK STANDARD:

Emergency Event properly classified and Emergency Data Form Part 1 properly completed.

File: Difficulty:

Time: minutes Task Number: Procedure Ref category I Classify E-Plan Event and Complete Part 1 Page 4 of 7 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U Inform operator to BEGIN after completion of review of the Initiating and log time 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" Complete IP-EP-115 Note: MUST BE COMPLETED WITHIN 15 Form 1 MINUTES OF DECLARATION Verify Data using Obtain filled out Radiological Emergency Data Radiological Form, Part "1" from MEANS and retain as part Emergency Data of JPM package. Form Information, Time IP-EP-115 Form 1 completed:

item #s 4, 5, 7, 8 11, 12 &13 Refer to procedure IP-EP-210, Attachment Attach 9.1 9.1 (SM I POM I ED Checklist)

Initiate County, State and NRC notification IP-EP-115, Form EP-4, 5 or 6 as Request for CCR 5. comunicator CUE: Acknowledge as communicator requested to commence File: Difficulty:

Time: minutes Task Number: Procedure Ref category Classify E-Plan Event and Complete Part 1 Page 5 New York State Indian Point Energy Center RADIOLOGICAL EMERGENCY DATA FOAM* PART 1 Notificatic ) This is the Indian Point Energy Center with a Part 1 Nottfication on: 1. Reactor StatUSj /' This is an: lEXERCISV ACTUAL EMERGENCY at: UNIT 2 BOTH Uti Unit 2 IUperatlOO8IJ" /{Date)_______ (Time) _______ (24 hr cloc Shutdown .!.!!:!.tt..a

.... \ '--"""\ (Date) ---1TJ,<:b.=.1)L,..i'Y..l--

___ (Time) Cue£tN TIMf (24 hr

2. The Emeroeocy 7'\ A. Unusual Event B. C. Site Area Emer Classificallon V r.::--:::=

E. Emergency This Emergency Classification declared on:

__-=_. at C y <<*Of 1) LiE (Dale) (Time 24 hr clock) Release of Radioactive Materials due to the Classified Event: No B. Release BELOW Federal limits To Atmosphere To Release ABOVE Federal limits To Atmosphere To Water D. Unmonitored release requiring evalue Wind Speed: '5 Meters/Sec at elevation 10 meters Wind Direction: Degrees at elevatlon 10 meters 1. Stability Class; A B @ D E F G 8. Answer Key The following Prolective Actions are recommended to be 1m plein anted as soon at practicable:

A. NO NEED for PROTECTIVE ACTIONS outside the site *" (y.VACUATE and IMPLEMENT the KI PLAN for the following C, SHEL TER*IN-PLACE and IMPLEMENT the KI PLAN for the following All remaining Areas MONITOR ttle EMERGENCY ALERT 5 miles around 1 ().miles downwind Entire EPZ ¥lnlhefollowin g Seclors:C7G)@

456789101112131415

@ NOTE' QFFSITE AUTHORITIES SHOULD CONSIDER SHELTER*IN*FLACE

+ TAKE KIIE EVACUATION IS NOT FEASIBLE 9. Reported by -Communicator:

_______________

Telephone 11 ________-1 (Communicator's Name) 1Emergency Director Approval:

fL""....i"":M-..,_________

DateITime: -rOOJ.1/

n .. (Oil'BCtor's Name) Page 1 of Form EP-1. Re Difficulty:

Time: minutes File: category Procedure Ref Task Number:

Classify E-Plan Event and Complete Part 1 Form Page 6 of7 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 7of7 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 Rlhr RVLlS, Natural Circ Range reading 44% METEOROLOGICAL CONDITIONS:

Wind Speed: 3.5 Wind Direction:

120 degrees @ 10 Stability Class: The Shift Manager is unable to get back to the control room. The MIDAS Computer is out of service for maintenance.

INITIATING CUES: You are the CRS and you must classify the event and complete the required Radiological Emergency Data Form as required by the Emergency Plan. Task Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 1 of 15 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 2000771601-1.doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 2 of 15 JPM Title: Calculate a Power Reduction Reactivity Plan per POP-2.1 JPM Number: RO A-1-1 KA Number and Importance:

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. I RO 3.9 Suggested Environment:

Actual Testing Alternate Path: Time Critical: Estimated Time: Actual Time: __

2-POP-2.1 Operations at Greater than 450/0 Power File: 2000771601-1.doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per Page 3 of 15 INITIAL CONDITIONS: The Beacon Computer is out of service for maintenance. The plant has been operating at 100% power (1080 MWe) for 175 days following a refueling outage. 32 Heater Drain Pump must be removed from service to repair a valve packing leak. The SM has directed a power reduction to 700 MWe in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to remove the heater drain pump. Current RCS Boron Concentration is 1200 ppm Current Control Bank D position 230 Steps INITIATING CUES: You are the ATC and the CRS has directed you to perform a Power Reduction Reactivity calculation using Attachment 5 of 3-POP-2.1.

TASK STANDARD:

Attachment 5 of POP-2.1 complete.

File: 2000771601-1.doc Difficulty:

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

2. Obtain current copy of 3-POP-2.1

13. Enter Total MW change 14. Enter Rate of Shutdown 5. Enter Start Time 6. Enter End Time

7. Determine Power Defect from Graph RV-1 18. Determine Xenon Worth from Graph 3D 19. Calculate total of steps 2 & 3 110. Enter Target Rod Position 111. Enter Integral Rod Worth at 186 steps 112. Enter Current Rod Position ,13. Enter Integral Rod Worth at 230 Steps .14. Calculate Reactivity due to rods STANDARD I S/U Candidate will be given the procedure Enters 380 MW Enters approx 127 (+/- 1) Enters Current Time Enters Start Time + 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Enter 400 (+/- 5) pcm Enter 22 (+/- 3) pcm Enter 378 (+/- 8) pcm Enter 186 (+/- 1) steps Enter 91 (+/- 3.5) pcm Enter 230 Steps Enter 0 pcm Enter 91 (note this is a negative number) File: 2000771601-1.doc Difficulty: 3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per Page 5 of 15 ESCRIPTIONS I CUES & NOTES STANDARD S/U 115. Calculate Reactivity needed from Boric Acid Sum Steps 4 &5 Enter 287 (+/- 10) pcm 116. Enter 141 (+/- 10) File: 2000771601-1.doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 6 of 15 OPERATION AT No; 3-POP-2.1 Rev: 53 ----GREATER THAN 45% POWER Page 35 of 40 ATTACHMENT POWER REDUCTION REACTIVITY (Page 1 of NOTE 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

RECORD the following:

ANSWER Total MW Change Rate of SID I rt\/.0/'flf" Stan Time IItV\.t End Time ClArYenf t DETERMINE Power Defect from 3-GRAPH-RV-1 OR the daily reactivity sheet. (+) tiOD pem DETERMINE Xenon worth as follows: IF Xenon equilibrium is established ANO 3-GRAPH-RV-30 has current cycle data. THEN USE 3-GRAPH-RV-3D. IF Xenon equilibrium is NOT established, OR 3-GRAPH-RV-3D does NOT have current cycle data, REQUEST Xenon worth from Reactor Engineering

(-)

pem 4.0 CALCULATE the total of Steps 2 and 3. .:..{OO Step 2 + Step 3 = (+) 31&'0: g J pem I I I File: 2000771601-1.doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1

--Calculate a Power Reduction Reactivity Plan per Page 7 of OPERATION AT No: 3-POP-2.1 Rev: 53 -URE ATE R TffAN45%>

POWER -Page 36 of 40 ATTACHMENT POWER REDUCTION REACTIVITY (Page 2 of DETERMINE Reactivity due to control rods using 3-GRAPH-RV-13 ANO 3-GRAPH-RV-7B.

Control Rog PositigO Integr§1 Rod WQrth Target Rod Position let.e: \ ) Steps q 1 (;

pcm Current Rod

.;2 Steps -0 pcm H '\1 pcm CALCULATE the Reactivity needed from Boric Acid by summing Steps 4 and 5. + (--) '11 = (+) .;2 pcm Step 4 StepS CALCULATE the total amount of Boric Acid needed. _J._l_l___pcm I .2.0.; pcm/gal = \q I /;. 10) gal Step (from 3-GRAPH-RV-14, Reactivity Control Parameters, OR Reactor Engineering)

!ANSWER KEY File: 2000771601-1.doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1 Calculate a Power Reduction Reactivity Plan per Page 8 of 3-GRAPH-RV-1 Rev 20 I ANSWER KEY TOTAL POWER DEFECT (for use with 3-S0P-RPC-003)

'---------------'

CYCLE 16 (Page' of 2) 0.0 -200.0 SOL

-400.0 dre bff'U'1-.

-_.._-_.-i C;M.da4t'

-600.0 +--------,,-...IA ..rfV l'Of tee.bM or

-800.0

.-----.--l fypJl\ .;t e !-10oo.0 g --1U *1200.0 Q a.: w -1400.0 g'1600.0 ..*1732.S

-1881.2 pcm -2000.0 -2200.0 *2.299.8 pcm *2349.7pem

-2400.0 , *2401.9 pcm -2600.0 o 10 20 30 40 50 60 70 80 90 100 POWER LEVEL SOl BORON =1600 ppm 10 1000 ppm MOL BORON =800 ppm to 400 ppm EOL BORON" 200 ppm 10 (; ppm File: 2000771601-1.doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1

-/" m=(J) (J) A" 3-GRAPH-RV-1 RJ 20 ZN cO TOTAL POWER S>> 0 38 (for use with 3-S0P-R.C-0(3) n 0" -.I C CYCLE 16 (Page 2 df .. 0') i>>.....NO 0 ...... (I) 0' BOL I Mal I EOi.S>> -.I 0-r-----Res BORON CONCENTRATION (1lPl\! -.10 POWER("!.)

1400 1&00 1800 400 600 800 0 100 2QO "tJ ..... 0 o o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 5 -106.6 *100.2 -95.0 -90.7 -37.1 -108.6 .0 -101.8 -159.9 -157.0 -154.4 (I) 10 -207.3 *195.5 -185.7 -177.1 -170.9 -214.2 *20.2 -20D.9 *310.1 -305.3 -300.2 .. 15 *302.9 *2864 -272.7 -261.2 -251.5 -317.1 -.8 *291.4 -453.6 -445.8 -438.4 ::u 20 -394.0 *373.4 -356.2 -341.7 -329.3 -411.6 .2 -391.8 -589.6 -519.5 -569.9 (I)25 -481.4 -457.2 -436.8 ....,9.5 -404.6 -516_2 .... .5 ....M.l -719.1 -707.4 -695.7 Q.30 -565.6 -538.1 -514.8 ....94.9 ....17.6 -613_0 -593.1 -574.6 -844.1 -sao.2 -816.5 -oC 35 -647.2 -61S.6 -590.5 -568.1 -548.6 -708.4 *.2 -663.S -965.5 -948.9 *933.0 40 -726.5 -693.0

-664.3 -639.5 -6177 -B02.5 -nib -751.1 '1082.8 '1064.0 -1046.1 ma (C -"-u _. 45 -304.0 *761.7 -736.3 -709.1 -685.1 -895.5 -865.4 -837.4

-1197.3 *11762 -1156.2 ('!) 0 031 SO -880.1 -840.9 -807.0 *177.3 -7SUl -987.7 -954.0 -922.6 *1309.6 '1286.3 -12&4.0 c.o:::S -u 0 55 -955.0 *912.9 -876.3 -844.2

-615.6 *1079.2 -104i.7 *1006.8 -'420.3 -1394.6 -1370.0 .£ 60 -1028.9 -983.9 *944.5 -909.9 -878.9 -117M *1128.7 -1090.1 -1529.9 -1501.7 a::u!'J.:it ........ . .

11022 -1054.0 -1011.8 -974.5 -941.1 -121$.0 -1172.7

-1638.8 -1607.9 -1578.5 c.nS>>70 -1174.7 -1078.2 -1038.1 -1002.1 -1350.3 .1300.1 *1254.5 -1747.3 -1713.7 .1881.6 n z 75 *124tH* .0 *1'.3.7 -1100.8 -1062.2 -1439.8 -1385.9 -1335.7 -1855.8 *1819.3 -17M .* ..... 80 -1318.1 -1259.9 -1208.5 *1162.6 -1121.3 -1529.0 *1470.6 -1416.3 -1964.4 -192-'.9 -1887.2 >> 85 *1388.9 *13272 -1272.4 *1223.5 -1179.4 -1617.7 -1554.9 -1496.2 -2073.2

-2030.7 -1990.0 >> <" 110 *1458.9 '1393.6 -1335.5 *1283.5 -1236.6 -1706.1 '1638.6 -1575.6 -2182.<1 -2136.7 -2093.0 Z 95 -15280 -.lJ5a.l -1397.6 -1342.5 -1292.7 -1793.9

1721.7 -1654.4 *2292.0 -2243.0 -2196.3 100 '1595.9 (1523.S) -1458.7 -1400.5 -1347.8 -1881.2

-1804.3 -1732.5 -2401.9 -2349.7 -2299.8 (fJ "tJ L-S>> :::s "0 (I)m .. "tJ -/ ::u 0 l:Io 3' :::0 A . "tJ I N /\ ...I.iii" .... m -. m IU ::l .... c -< ;. .. ..." ...-..." ',*u*-,foI,"l'j

,<r..... ....-<

Calculate a Power Reduction Reactivity Plan per Page 10 of 15 -._.... -_..-.... -'---.--*-*-**--+----f--Written by: CA.. '7:../1" '

.-.-Reviewed by:

,!/"74-:::::;:;::r--, ___._.._ .. 1--__ .._. **__._...*__-...__ _ Approved by:

i Effective Date: 0 ..£ "AI , -Reaeto' at Hot Full Power ---'---, , "' \ \ .

.--. ......f----.---_-I-----it--tI

\, _\......._-._.,1-11.\..-.

-,'__. "'"",' File: 2000771601-1.doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1

-I"Tl ru=(/)" . 111 . (ZI\.)c:;0 0 38 3-GRAPH-RV-7lev.l1

0" -.J 11I-.J AT POWER CONTROL BANK WORTH AS FUNCTION OF BANK POSITION n C CYCLE 16 (For Use w1h POP-2.1)OJ 1\.)0 EQUIUBRIUM XENON CcPNDITIONS

,...0 .....

0' *0:-" (Page 1 CD -.J c. -.Jo 00 BANK POSITION BOL BOUMOl MOlJEOl EOL ..... ,J, MOL ." o SI"". Withdrawn 150 MWDIMTU 6000 MWDIMTU 1 000 MWDIMTU 18000 MWDIMTU 25017 MWDlMTU 0..... IlII1....nllll lmgql DII_1Iat InIe\ItIII DiIonnIlll InItIgnIl OI!Ierentli Inltlgnll am.onIIII In...., BANKe WINK 0 RodWor1h RodWor1h RodW"rtIl Rod Wor1h RodWor1h RodWor1h RodW_ Rod worm RodWorIh RodWor1h CD (pcml**epl fpcm) (pC!n/olop) lpc:ml (pc:mfolop)

",em) (pcmlolop) (pcmlllop) (porn) .. 230 2J() 0.00 0.00 0.00 0.00 GOO 0..00 0.00 Q.OO 0.00 0.28 ::0 230 227 052 311 0.28 \43 0.32 1.58 0.51 254 tOO 41\6 CD 2.iO 224 1.24 6.22 0.57 2.85 0.63 316 102 5.08 181 9.33 Q. 230 220 201 1fl.37 0.95 4.75 \,il5 528 1.69 8.46 2l1J 15.5< -oC 230 218 2.36 1597 1.20 7.91 1.36 8.92 2.15 14.14 343 2422 DJ n 230 215 2.11(1 2436 1.5& 12.1>4 1.83 1440 2.84 22.66 *.34 37.23co!:!.1:::1 _. 230 212 3.24 3216 1.95 17.37 2.29 19.89 3.53 31.18 5.24 50.24 CD 0 og 230 210 3.53 36.36 2.20 20.52 2.60 23.51; 3.99 36.86 585 58.91 ..... :::s Ilc:; 230 206 3.56 52.62 2.47 30.86 3.0.1 35.98 *.S:? 51;,48 6.35 84.80 N 230 20(! 3.56 6331 2.86 38.25 3.al 45.31 *.92 00.45 6.72 104.22 0::0 ..... 230 200 3.110 74.00 2.86 45.84 3.62 54.64 S.33 63.42 710 123.63 -CD w ......230 1117 3110 &1.78 3.01 551S 3.79 86.38 5.46 100.00 710. '4495 U1n 230 194 3.59 9556 3.16 84.51 3.97 78.11 5.5& 11671 711 168.21 ,...230 190 359 111994 3.36 78.96 4.21 93.76 5.77 13890 7.12 111<1.10 230 3.57 117.02 3.42 4.26 102.42 S.75 150.34 1.02 206.45 <' 23(1 II 3.54 121.63 3.51 4.33 115.39 512 161.49 8M 229.06-.----230 182 3.51 13824 3.59 105.00 *.40 128.37 5.69 18<1.85 6.73 249.71 230 lao 3.49 145.31 3 liS 112.02' 4.44 137.03 5.67 196.09 6.64 263.47 >>1 ." 230 1'16 3.46 15913 3.73 127.04 <46 151;.00 5.5& 218.32 8A7 289.19 iii'230 173 3.44 169.49 3.80 138.30 4.51 168.46 5.51 234.99 6.35 308.48 :::s 230 170 342 11984 3.86 146.&7 *. 54 181.96 S.45 251.66 6.22 321.78 230 167 3.* ' 100.00 3.92 16143 4.56 195.66 5.38 287.68 6.13 346.00 "C 2J() 164 340 200.27 3.97 113.29 451 209.35 532 2a3.70 605 36423 CD Z ..,:10 160 339 213.118 4.05 189.11 459 22762 5.23 JQ5.07 5.93 38853 (f) "'0-I WriltenS r ..__Total Control Bank Worth):a. 3' Reviewed By:.__ . ___ 0 SOL = 3635pcm EOl= 3996pcm Approved "'0Total Shutdown Bank WoI1h -,I\.) Effective

!te: 3:: 11£< I I SOL; 4000pcm EOl" 4485pcm N ,:::So (jj'3 m ....It. ;t -. Qj ::J ;0-"'--.

A m -<

Calculate a Power Reduction Reactivity Plan per POP-2.1 Page 13 of 15 3*GRAPH*RV-14 Rev. 3 NSWER KEY REACTIVITY CONTROL PARAMETERS IP3 Cycle 16 \IIc l!2I. 2QQl! MWO/MTIl MS& SQI. Cycl. SlKnup (MWO/MTU)

150 6000 12000 25017 Specified Boron Concentration (ppm)

974 1194 1001 100 Aelatln Power (%) :: 100 100 100 100 Mo<IerotOl' TemperatuteCOefflclent (pelTlll"I

.. '12.11 -10,9 *15.1 *29.8 Isothermal Temperature Coefllclent (pem/F) .. *14.6 *12.7 '17.2 *33,1 Moderator Temperatur.

Defect (pem) .. *221.9 *173.9 *252.8 *551.6 Doppl.r Pow., Coefficient (pcm/% power) .. *8.9 *a.6 *8.1:1 *8.9 Doppler Temperature Coefficient (pc:m/F) .. *1.3 *1,3 *1.4 -1.4 Doppler Power Defec:1 (pcm) :: -"77.2 '1177.3 *1221.0 -1113,$ Total Power Coefficient (pcm/% power) * -13.8 *11!.6 -14,7 *21.3 Total Power o.fec:1 (pemj .. '1606.0 '1440.3 *HJ63.8 '2349,7 Axial Reactivity RedIstribution Oefec:1Jpcm)

'206.1:1 *89.1 '190.0 *618,3 control "'anka uinerantlel Rod Worth

C ban" and 0 bank (pc:m/lltep)

.. 4,7 5.0 5.2 6.6 Control Bank 0 Average Differential Rod Worth 100 to 223 at..,. (pern/step)

.. 3.1 3.4 3,1 5.4 Control Bank 0 Power Worth (step&l%)

.. *4 4 -4 Highest Worth Stuck Rod (pcm) " 948 (N*ll) 762 (K'10) Dropped Flod Worth (pcm) '" 100.0 100.0 100.0 100.0 Om**entia' _ron Worth (pcmlppm)

'" -6.31ti -6.289 -6.667 -8,lW Boratlon (ueing 12.1 % Boric Acid) (gal/ppm)

.. 3.1 3.1 3.1 3.0 Dilution (Pure Makeup Water) (gallppm)

.. 66 &4 84 645 Boron Dilution Wol1h (pcrn/gal)" '0,096 -0.104 -0,013) aoeaaloA Wonb ,pcmlgell=

2.04 @ -2.'6 *2.73 Dilution DlfferenUal Power Worth (No Rod Motion) (9all%) = 144 108 141 1675 Boration Diff.rential Power Woith (No Rod Motion) (9811%) => 6.a 5.2 6.8 7,9 Other Parametera Pressurizer Hal -75 gaII% Cold -125 gaV% 1"f 1% Level Pressurizer 1 % pzr Levit! 1 0/1 Press ,'F 6. Tavg '" looll 6. Press when solid Steam Dump Steam .. 3. Steam FIOwI"F Temp. Error Above 5'F Dead Sand Using the above information, olher contrOl parameters can easily be derived rt Il'le desired units are known, linear Interpolation of the aboVe dalll for other tnnes in core life (a particular core bumup) can be PQriormea and obls'n gOOd accuracy.

Reference:

Cycte 16 NuPOP Rell. 0 (WCAP*17050*P), Hot lull power, all rods out conditions are assumed in the above. Time: 20 minutes File:

Difficulty:

3 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?

YEsDNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information:

File: 2000771601-1 ,doc Difficulty:

3 Time: 20 Task Number: 2000770101 2-POP-2.1 Page 15 of 15 INITIAL CONDITIONS: The Beacon Computer is out of service for maintenance. The plant has been operating at 100% power (1080 MWe) for 175 days following a refueling outage. 32 Heater Drain Pump must be removed from service to repair a valve packing leak. The SM has directed a power reduction to 700 MWe in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to remove the heater drain pump. 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

---I" III = " en . (I) . Written By:_C 7;. ..,. --/ o ZN

Reviewed cO Approved By: -; ___________ 38 n tT ---.I ?10

Eflectiv8 Date: , . .2 -/6 -

(1)---.1 C (J) D) r-'" NO 0-' o' , f,....0:-" D)---.I Cl. 190 It .... ,....,......

---.10 00 "" .... .. .....

0 160 -" . .. -,...".. 70 "JMOL __ -.. -.,., -.. . --,...,. ;0 60 ... CD ::LI: .-* "C Q. 50 B) (') *I cae!:.J (33; 40 CD 0 "g ,

30 J 0;0/' -CD-' V> , ...:Io.D) 20 BANK D POSTtON (Steps Withdrawn) 01(')....I ;r 10 Power % SOL MOl EOL I , 30 156 160 45 -0>> >>.' 40 164 166 101 iii'z f Z ::s 50 172 172 157 .. 60 181 179 169 "t'J (J) (J) CD EOl 70 190 186 181 ..I 80 201 195 193 -0 :t. -I_. , 90 211 205 204 o I -0m , 100 m 230 230 230 t a" N:i' :::0 , :::0 . ......iii'... 3 _. I... I-. c--A A m m -< -<

Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 1 of 7 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0001251601-1 ,doc Difficulty:

2 Time: 15 Task Number: 0001250501 3-FR-1.3 Perform Reactor Vessel Venting Time Calculation per Page 2 of7 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: Actual Time:

References:

3-FR-I.3 Response to Voids in Reactor Vessel File: 0001251601-1.doc Difficulty:

2 Time: 15 Task Number: 0001250501 3-FR-1.3 Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 3 of 7 INITIAL CONDITIONS: An event occurred 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. Containment pressure 2.5 psig Containment temperature 160°F Containment hydrogen conc 1.0% RCS 1000 psig INITIATING CUES: You are the ATC and the CRS has directed you to perfom the Reactor Vessel Venting Time calculation in accordance with FR-1.3 Attachments 4 & 5. TASK STANDARD:

Calculation reviewed and errors identified.

File: 0001251601-1.doc Difficulty:

2 Time: 15 Task Number: 0001250501 3-FR-1.3 Perform Reactor Vessel Venting Time Calculation per FR-1.3 Page 4 of 7

Denotes Critical Step STEP DESCRIPTIONS I CUES &NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Obtain Current Rev of Procedure 13 Determine Containment Volume at STP (A) Determine Maximum Hydrogen volume that can be vented (8) Determine Hydrogen flow rate as a function of 15 RCS pressure (C) Calculate maximum venting time 16 JPM Complete STANDARD S/U Candidate will be given procedure Calculates 2.40E6 to 2.45E6 Calculate 4.845E4 to 5.0E4 2800 to 2950 Calculate 15 to 18 minutes File: 0001251601-1.doc Difficulty:

2 Time: 15 Task Number: 0001250501 3-FR-1.3 Perform Reactor Vessel Venting Time Calculation per FR-I.3 Page 5 of 7 Nueer: I Revision 3-fR-1.3 RESPONSE TO VOIDS IN REACTOR o Attlch!llent 4 (Attachmem:

page 1 of 1) lNSTRUCTJQNS FOR DETERMINING VENTING TIME 1. DETERMINE ContainMent Volu-e It STP -A A -( 2. 61x 1 06 Ft3 ) x __

__ x __

14.7 psi T P (psig) -Containment pressure (psig) + 14.7 T(OR) -Containment temperature(*F}

+ 460 A -( 2. 6lxl 06 F t 3 ) )( __

__ Jt __..;.>4....92..* ... R'--_ 14 . 7 ps ia ('eJ () 2. DET[RMJN[

Maximu. Hydrogen volu.a that can be vented -B B -.l.(

.....c....e.u..nt"",r-"a

...t-",i o""'n....)--'x"--... 3. DETERMINE Hydrogen flow rate as a function of ReS pressure -C CHECK ReS pressure. DETERMINE Hydrogen flow rate using Attachment S. HYDROGEN FLOW RATE VERSUS ReS PRESSURE, Page 29. c"' q1'ioo SUM Maximum venting Answer Keyventing time .. 1ft.£.. minutes *END OF ATTACHMENT-File: 0001251S01-1.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 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: 0001251601-1.doc Difficulty:

2 Time: 15 Task Number: 0001250501 3-FR-1.3 Page 7 of 7 INITIAL CONDITIONS: An event occurred 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, 1.3. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. Containment pressure 2.5 psig Containment temperature 160°F Containment hydrogen conc 1.0% RCS 1000 psig INITIATING CUES: You are the ATC and the CRS has directed you to perfom the Reactor Vessel Venting Time calculation in accordance with FR-1.3 Attachments 4 & 5. Task Perform a Peer Review of a Surveillance Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 2000701602-1.doc Difficulty:

2 Time: 15 Task Number: 2000700102 IP-SMM-DC-904 Perform a Peer Review of a Surveillance Page 2 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: Estimated Time: Actual Time: __

References:

3-PT -Q0928 32 Service Water Pump IP-SMM-DC-904 Surveillance Test Program File: 2000701602-1.doc Difficulty:

2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 Perform a Peer Review of a Surveillance Test Page 30f7 INITIAL CONDITIONS It is 0200 3-PT-Q092B 32 Service Water Pump Quarterly Test was INITIATING CUES: You are the Spare RO and the CRS has directed you to perform a Peer Review of the Surveillance Test in accordance with IP-SMM-OC-904.

TASK STANDARD:

Surveillance Test Reviewed and Errors Identified.

File: 2000701602-1.doc Difficulty:

2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 I Perform a Peer Review of a Surveillance Page 4 of 7 Denotes Critical Step DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Commence evaluation Obtain current copy of IP-SMM-904

2. CUE: Candidate given procedure Document Review on Attachment 10.2 Calibration due dates recorded Instruments within calibration Changes documented by TPC All required procedural steps completed All steps NOT completed noted & explained in 7. Comments Section 8. All corrections lined out, dated and initialed All Calculations Correct NOTE: On page 14 data is incorrectly transcribed.

The calculation is correct; however it is OOS 10. All data properly transcribed Required CRs, WOs, PFs, or CTSs etc 11. initiated STANDARD Identifies dates recorded Identifies dates within calibration Identifies NA Identifies step 4.2.7 NOT signed off Identifies step 4.2.7 not signed off Identifies correction on page 12 is correctly lined out, dated and initialed Identifies calculations correct Identifies pump discharge pressure not properly transcribed from page 12 to page 14 Identifies NA File: 2000701602-1.doc Difficulty:

2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 Perform a Peer Review of a Surveillance Test Page 5 of 7 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 Task Number: 2000700102 I P-SMM-DC-904 Perform a Peer Review of a Surveillance Test Page 6 of7 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: 2000701602-1.doc Difficulty:

2 Time: 15 Task Number: 2000700102 I P-SMM-DC-904 Page 7 of 7 INITIAL CONDITIONS It is 0200 3-PT-Q092B 32 Service Water Pump Quarterly Test was INITIATING CUES: You are the Spare RO and the CRS has directed you to perform a Peer Review of the Surveillance Test in accordance with IP-SMM-OC-904. Task Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 1 of 7 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0350041602-1 Difficulty:

2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using Page 2 of 7 JPM Title: Perform a SG Tube Leak Determination using SG-1 JPM Number: RO -A-3 KA Number and Importance:

2.3.14 Radiological Controls Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

RO -3.4 Suggested Environment:

Classroom Actual Testing Environment:

Alternate Path: NO Time Critical:

NO Estimated Time: Actual Time:

References:

3-AOP-SG-1 Steam Generator Tube Leak File: 0350041602-1 Difficulty:

2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 3 of 7 INITIAL CONDITIONS:

Radiation Monitor 15 is in The operating crew is responding in accordance with 3-AOP-SG-1 Generator Tube Given the attached Leakrate INITIATING CUES: You are the BOP and the CRS has directed you to estimate the SG Tube Leakage. TASK STANDARD:

SG Tube Leakage calculated using 3-AOP-SG-1 Attachment

1. File: 0350041602-1 Difficulty:

2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 4 of 7

Denotes Critical Step DESCRIPTIONS I CUES &NOTES STANDARD S/U Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation Candidate may use .2. Enter data ! Attachment 1 or separate paper Determines

.3. Calculate average R-63 R-63 is 1.49 X 10*

Determines SG Tube .4. Calculate SG Tube Leakage Leakage is 15.36 +/-O.3 GPD JPM Complete File: 0350041602*1 Difficulty:

2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Perform a SG tube Leakrate Determination using 3-AOP-SG-1 Page 5 of7 Any area of weakness observed?

YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information:

File: 0350041602-1 Difficulty:

2 Time: 15 Task Number: 0350040502 3-AOP-SG-1 Page 6 of 7 INITIAL CONDITIONS:

Radiation Monitor 15 is in The operating crew is responding in accordance with 3-AOP-SG-1 Generator Tube Given the attached Leakrate INITIATING CUES: You are the BOP and the eRS has directed you to estimate the SG Tube Leakage. Task Page 7 of7 Steam Generator Tube Leak 3-AOP-SG-1 Rev. 06 Attachment 2 Page 21 of 41 Leak Rate Log 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months {s 10% increase in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ). take data every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . If leak < 30 gpd, take data once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . R-15 Time *Date (J,lCilcc) j:;) ;t, ;-Ot)fH./

iJ &'(..(6 t /.)u'*; r{5tJA. 'I Il..d'll ,et 13D[.i It")O,!\'1 74'1.1I"{;

I'>,S' TOiJA*(j !'J ...*Nf{jl.. , rBl) '-il,)v,/;-t '4, 'f\(( D-i., i1JiI <" 'TbHAt! 14CO TN1M K. \ '{'(v " R-6S Current **OELTA Method Used To (J.lCilcc)

Leakrate LEAKRATE Determine A B gpm (gpd) gpm (gpd)/hr Leakrate /. tX1-,1 iJi;lfl..i J.9vJI;)..

I )laD J l,c/'/. (c I. (J-i't.I(/

I/Jt!IO J.. llfiilijl.

1.'11/.JO i.rRVIl':'" 1.<:/

j (11",/ j Afro} 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 LEAK RATE (extrapolate r.esult out to one hour). Use a minus (-) to indicate decr*asing feakrate.

File: Task Number:

Emergency Borate Page 1 of 9 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0040421601-5.doc Difficulty:

2 Time: Task Number: 0040420501 ONOP-CVCS-3 Emergency Page 2 of {

JPM Title: Emergency Borate JPM Number: S-1 (a) KA Number and Importance:

000024A120 RO 3.2, SRO -3.3 Suggested Environment:

Simulator Actual Testing Environment:

Alternate Path: YES Time Critical:

NO Estimated Time: Actual Time: ___

References:

ONOP-CVCS-3 File: 0040421601-5.doc Difficulty:

2 Time: Task Number: 0040420501 ONOP-CVCS-3 Emergency Page 3 of INITIAL CONDITIONS: The reactor has just tripped. 31 BATP is aligned to the blender. All actions in E-O, Steps 1-4 and ES-O.1, Steps 1 through 3 have been completed.

INITIATING CUES: You are the ATC and the CRS has directed to emergency borate per CVCS-3 up to and including the completion of Step 17.a due to multiple stuck rods. TASK STANDARD:

The RCS has been Emergency Borated per ONOP-CVCS-3 up to and including the completion of step 17.a. File: 0040421601-5.doc Difficulty:

2 Time: Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 4 of 9 Denotes Critical Step STANDARD S/U STEP DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after completion of review of the Initiating Cues log time 1 Obtain correct ONOP-CVCS-3 Observe Charging 2 Check Charging Pump running Pump RUNNING 3 Check MCC-36A and 368 Verify and 368 Time: minutes File: 0040421601-5

.doc Difficulty: Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 5 of 9 Verify PressurizerCheck Pressurizer pressure LESS THAN 2335 pressure < 2335 psig psig 17 Check status of Verify 11 Check RCS temperature Verify RCS >500°F 12 Check RCS temperature Observe 230°F If any rod is greater than or equal to 20 steps Observes 2 emergency bora t e per attachment 4 fu lIy withdDeterminesDetermine boration time minimum of 142 NOTE: Minimum Boration Time 142 seconds seconds Candidate may calculate up to 284 (Time Compression)

Inform candidate that the calculated time has Determine 2 RodsDetermine status of Control Rods > 20 Steps 14 Determine amount of boron Calculate 212 ppm boron concentration increase requi r ed increase required NOTE: 212 ppm for each additional rod greater than one Time: minutes File: 0040421601-5

.Difficulty

2 ONOP-Simulator Task Number: 0040420501 II 16 17 18 19 20 Emergency Borate Page 6 of9 DESCRIPTIONS I CUES & NOTES Determine boration time required NOTE: 34 min for each additional rod greater than one If candidate stops and is waiting for time to elapse, CUE: (Time Compression)

Inform candidate that additional 34 minutes has passed Direct Watch Chemist to sample RCS boron concentration CUE: Acknowledge as Watch Chemist Determine if boration completed CUE: (Time Compression)

Inform candidate that additional 34 minutes has passed Place boric acid transfer pumps to SLOW Turn Makeup Control Switch to Stop Open Boric Acid Storage Tank Recirculation Valves to approximately 25% JPM Complete DARD S/U Determine 34 minutes required Direct Watch Chemist to sample RCS for boron concentration Determine expected boration time completed OR required boron concentration achieved Rotate speed switch to slow position Rotate Makeup Control Switch to Stop Rotate valve potentiometer to 25% File: 0040421601-S.doc Difficulty:

2 Time: Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 7 of9 ff Any area of weakness observed?

YEsDNODExaminee Signature All areas of observed Evaluator Description of problem area: Description of reviewed information:

File: 0040421601-5.doc Difficulty:

2 Time: Task Number: 0040420501 ONOP-CVCS-3 Emergency Borate Page 8 of9 Simulator Setup Reset to any 100% IC Insert Malfunctions for Stuck Rods MAL-CRF004AJ (CBB -Rod H12) -UNTRIPPABLE MAL CRF004AZ (CBD -Rod K2) -UNTRIPPABLE Manually trip the reactor. Open Atmospheric Steam Dumps to cooldown to approximately 530°F File: 0040421601-S.doc Difficulty:

2 Time: Task Number: 0040420S01 ONOP-CVCS-3 Page 9 of 9 INITIAL

1. The reactor has just tripped. 2. 31 BATP is aligned to the blender. 3. All actions in E-O, Steps 1-4 and ES-O.1, Steps 1 through 3 have been completed.

INITIA'"ING CUES: You are the ATC and the CRS has directed to emergency borate per CVCS-3 up to and including the completion of Step 17.a due to multiple stuck rods. File: 0040421601-5.doc Task Number: 0040420501 Transfer to Cold Leg Recirculation Page 1 of 9 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

UNSAT This ..IPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0130151601-1.doc Difficulty:

4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Recirculation Page 3 of9 l__ INITIAL CONDITIONS: A Large Break LOCA occurred approximately 25 minutes ago. The RWST LOW LOW Level alarm has just illuminated. SI has been RESET per RO-1 and procedure E-1, Steps 1 through 19 actions have been completed with Containment Spray reset. INITIATING CUES: You are the ATC and the CRS has directed you to transfer to Cold Leg Recirculation per ES-1.3, steps 1 through 12. TASK STANDARD:

Cold Leg Recirculation established prior to RWST level lowering below 1.5 feet with recirculation flow to the core approximately 360 gpm. File: 0130151601-1.doc Difficulty:

4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Page 4 of 9 I Denotes Critical Step DESCRIPTIONS t CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1 Obtain correct procedure 2 Review Caution and Note prior to Step 1 Determine if transfer to Cold Leg Recirc is 3 required i 4 RESET SI 5 Check SI RESET 6 RESET Containment Spray 17 Align SI Recirc Switches #1 and #3 Energize the following valves on MCC-36A and MCCC-36B: . AC-MOV-743, 744 and SI-MOV-894A eAC-MOV-1870, SI-MOV-882 and 8 894B,894D CUE: Acknowledge as NPO Booth Operator:

Energize valves Establish communications with PAB 73 ft. and prepare for operation of SWN-35-1 and 35-2 9 CUE: Acknowledge as NPO 10 Check status of Recirc Switch #1 STANDARD StU ES-1.3, Step 1 Caution and Note reviewed Verify both RWST Low-Low Level alarms LIT and VC Sump trending up Verfy reset Verify SI Actuated light extinguished VC Spray reset per initiating cue Place Recirc Sw #1 and #3 to ON Dispatch NPO to energize valves on MCC 36A and 36B Dispatch NPO to PAB. 73 ft. Verify Recirc Switch #1 function complete light LIT File: 01301S1601-1.doc Difficulty:

4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Recirculation Page 5 of 9 STANDARD StU Verify Recirc Switch #3 function complete 11 Check status of Recirc Switch #3 ht LIT Verify RCS pressure Check RCS pressure less than intact SG less than intact SG 12 pressure Place 31 t 33 13 Stop both Motor Driven Auxiliary Feed pumps in Initiate performance of Attachment 1 CUE: Additional Team operator will parallel actions of Attachment Direct 14 BOOTH OPERATOR:

Verify 459,460,200 of Attachment A,B, C closed, stop running pump(s), place all Pressurizer heaters OFF. Notify operator that Attachment Dispatch NPO Check status of SWN-FCV-1111 and 1112 verify 15 1111 and CUE: FCV-1111 and 1112 are CLOSED Place Recirc Sw #2 16 Align SI Recirc Switch #2 to ON Verify Recirc Switch #2 function complete 17 Check status of Recirc Switch #2 LIT Establish communications with PAB 73 ft. Request NPO 18 standby CCW CUE: Acknowledge as Check RHR Hx CCW Shutoff Valves OPEN. Verify 822 A 19 8228 CUE: Ack as Observes 32 20 Manually START 32 Recirc pump pump NOT Observes 31 Recirc 21 Manually START 31 Recirc pump pump NOT running Time: 20 minutes File: 0130151601-1.doc Difficulty

4 Simulator Task Number: 0130150501 ES-1 .3 Transfer to Cold Leg Recirculation Page 6 of 9 Verify Recirculation Trains not affected by sump blockage 31 -Low Head Injection Line Low Flow alarm -SI Pump Suction Low Pressure alarm -Indications of erratic I reduced flow 32 -Abnormal su level indication Determine Minimum Core Recirculation Flowrate File: 0130151601-1

.doc Difficulty

4 Task Number: 0130150501 ES-1 .3 Verify indications of sump blockage do NOT exist Throttle to maintain 360 gpm on lowest available indicator Time: 20 minutes Simulator Transfer to Cold Leg Recirculation Page 7 of9 Any area of weakness observed?

YES DNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information:

File: 0130151601-1.doc Difficulty:

4 Time: 20 Task Number: 0130150501 ES-1.3 Transfer to Cold Leg Recirculation Page 8 of 9 Simulator Setup Initiate Simulator to any 100% power IC Insert Malfunctions:

MAL-RCS001A

-100%

MAL-CNS003A

-Trip -Recirculation Pump 31 Trip

MAL-CNS003B

-Trip -Recirculation Pump 32 Trip Run Simulator Perform all actions of E-O, RO-1, E-1 Wait until RWST Low Low level alarms annunciate.

Freeze the Simulator Take a Snapshot if JPM is to be used more than once. File: 0130151601-1.doc Difficulty:

4 Time: 20 Task Number: 0130150501 ES-1.3 Page 9 of 9 INITIAL

1. A Large Break LOCA occurred approximately 25 minutes ago. 2. The RWST LOW LOW Level alarm has just illuminated.

3. SI has been RESET per RO-1 and procedure E-1 J Steps 1 through 19 actions have been completed with Containment Spray reset. INITIATING CUES: You are the ATC and the CRS has directed you to transfer to Cold Leg Recirculation per ES-1.3, steps 1 through 12. Task Respond to Pressurizer Controlling Pressure Channel Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

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: 0100081601-1 Difficulty:

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel Page 2 l"" 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 I- Time Critical:

NO Estimated Time: Actual Time:

References:

3-AOP-INST

-1 Instrument or Controller Failures File: 0100081601-1 Difficulty:

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel Failure High Page 3 of9 INITIAL CONDITIONS:

The plant is at 1 00% Power INITIATING You are the TASK STANDARD:

File: 0100081601-1 Difficulty:

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 I Respond to Pressurizer Controlling Pressure Channel High Page 4 of 9 Denotes Critical Step DESCRIPTIONS I CUES &NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below CUE: Evaluator, inform operator as the CRS to implement immediate actions of INST-1, Instrument/Controller Failures Commence evaluation Identify Failure/Stabilize Plant 12. Check All Control Systems Rod Control -Not Affected PRZR Level Control -Not Affected 3.

MBFP Speed Control -Not Affected SG Level Control -Not Affected SG Pressure Control -Not Affected PRZR Pressure Control -IS AFFECTED 4. Determine an Instrument Failure has occurred Transition to procedure section for PRZR 15. Pressure Failure Manually operate Heaters and Sprays as 16 necessary to maintain desired pressure Determine PI-457 has not failed STANDARD Determine PRZR pressure not NORMAL Place PRZR pressure control in MANUAL Check indications for all control systems Determines an instrument failure has occurred; redundant indications and controller response Selects proper procedure step from table Adjust Master Pressure controller to close spray valves and energize heaters Observes Indication File: 0100081601-1 Difficulty:

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel P age 5 0 IL!TEP DESCRIPTIONS I CUES & NOTES 8 Determine PI-474 has not failed Place Pressurizer Pressure Defeat Switch in 19 ' DEFEAT 1 & 4 (Rack B-6) CUE: A spare operator will monitor the flight panel Place Delta T Defeat Switch T/411A in Defeat 110 Loop 1 (Rack B-8) Place Pressurizer Pressure Recorder to 11 channel 2 or 3 12 Return Heaters and Sprays to Auto Refer to Technical Specifications.

13 CUE: The CRS is reviewing Tech Specs 14 Observes Note before step Check Redundant Bistables for failed channel 15 NOT tripped 16 Observe NOTE before step Place the bistables to trip for failed channel in Rack Red A-4

Loop 1 Overtemp Trip

Loop 1 Hi Press Trip 117

Loop 1 Lo Press Trip

Loop 1 Unblock SI

Loop 1 SI Check all bistable status lights for failed 18 instrument listed in Attachment 6 Table 3 illuminated STANDARD S Observes Indication Rotates Switch to DEFEAT 1 &4 position Rotates Switch to Loop 1 position Rotates Switch to channel 2 or 3 position Place Master Pressure Controller to auto Reviews Note Using Attachment 6 Table 1 Check Bistable Status lights extinguished (Panel SOF) Reviews Note Places bistable trip switches in the UP position Observes all status lights illuminated File: 0100081601-1 Difficulty:

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel P age 6 0 f9 STEP DESCRIPTIONS I CUES & NOTES STANDARD S/U JPM Complete File: 0100081601-1 Difficulty:

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Respond to Pressurizer Controlling Pressure Channel Failure High Page 8 of9 Simulator Setup Initialize Simulator to any 100% power Ie Insert Malfunction MAL-PRS005A Final Value 2500 psig Ramp -15 seconds Take a snapshot if JPM is to be used more than once. File: 0100081601-1 Difficulty:

3 Time: 20 Task Number: 0100080501 3-AOP-INST-1 Page 9 of 9 INITIAL CONDITIONS:

The plant is at 100% Power INITIATING CUES: You are the ATC. Task Respond to Loss of Main Boiler Feed Pump Speed Control Page 1 of 8 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0590141601-1.doc Difficulty:

3 Time: 20 Task Number: 0590140501 3-AOP-FW-1

---Respond to Loss of Main Boiler Feed Pump Speed Page 2 of 8 JPM Title: Respond to a Loss of Main Boiler Feed Pump Speed Control JPM Number: S-4(j) KA Number and Importance:

OOOOS4A20S Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): -Status of MFW pumps, regulating and stop valves RO -3.S SRO -3.7 Suggested Environment:

Actual Testing Alternate Path: Time Critical: Estimated Time: Actual 3-AOP-FW-1 Loss of Feedwater File: 0590141601-1.doc Difficulty:

3 Time: 20 Task Number: 0590140501 3-AOP-FW-1 Respond to Loss of Main Boiler Feed Pump Speed Control Page 3 of 8 INITIAL CONDITIONS:

The plant was operating at 100% 31 Main Boiler Feed Pump Trouble Alarm 31 Main Boiler Feed Pump is in Track and All actions up to step 4.22 of 3-AOP-FW-1, Loss of Feedwater have INITIATING CUES: You are the Spare RO on shift. The CRS has directed you to perform . Attachment 3 of 3-AOP-FW-1 for 31 MBFP in Track & Hold. TASK STANDARD:

Track and Hold is reset and 31 MBFP is being controlled using the Startup Signal. File: 0590141601-1.doc Difficulty:

3 Time: 20 Task Number: 0590140501 3-AOP-FW-1 II Respond to Loss of Main Boiler Feed Pump Speed Page 4 of 8

Denotes Critical Step DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Commence evaluation Dispatch NPO to the Lovejoy Control Cabinet NOTE: The candidate will perform actions at the Lovejoy Control Cabinet. CUE: NPO Acknowledges Is in service FEEDBACK 0 LED lit or flashing 3. CUE: NPO Reports Feedpump D LED is not lit or flashing Is PI-404 Failed High Is Track and Hold LED lit or % Track and Hold 5. signal displayed Is continued Operation of the affected Main Boiler Feedpump desired? 6. CUE: The CRS has determined that continued operation is desired Are Percent FW and Percent Hold within 4% 7. of each other? Adjust Percent Feedwater Controller to 8. attempt to reduce difference to within 4% 19. Select desired rate Lower Percent Startup Signal below Percent 110. Hold Signal using raisellower switch File: 0590141601-1.doc Difficulty:

3 Task Number: 0590140501 3-AOP-FW-1 STANDARD S/U Contact NPO and dispatch to Lovejoy Control Cabinet Contacts NPO and asks question.

Observes Meter Not Failed Observes both Track & Hold LED is lit and % Track and Hold signal is displayed Observes % FW and % Hold signals are .NOT within 4% of each other Attempts to adjust 31 Main Boiler Feed Pump controller.

Observes no change in %FW signal Selects either 2 or 3 Rotates switch to lower position Time: 20 minutes Simulator Respond to Loss of Main Boiler Feed Pump Speed Control Page 5 of 8 ....

I CUES & NOTES When Startup In Service LED is illuminated

11. Notify I&C to perform the following Adjust OVD POS knob until green LED is as 112. bright as possible Place OVD SYS Enable/Off switch to Enable Adjust FW OVD POS knob until FEEDWATER 114. is 95% Press Track & Hold Reset Did Failure Hold light extinguish Direct NPO to press signal processor RESET 17. pushbutton Did signal processor alarms extinguish Is affected MBFP speed under control? JPM is complete STANDARD Contact I&C Observes green LED is illuminated Move Toggle Switch to Enable Rotate knob clockwise until %FW is 95% Depresses button Observes LED is extinguished Depresses correct pushbutton Observes alarms clear Determines MBFP is under control File: 0590141601-1.doc Difficulty:

3 Time: 20 Task Number: 0590140501 3-AOP-FW-1 Respond to Loss of Main Boiler Feed Pump Speed Control 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: 0590141601-1.doc Difficulty:

3 Time: 20 Task Number: 0590140501 3-AOP-FW-1 Respond to Loss of Main Boiler Feed Pump Speed Control Page 7 of 8 Simulator Setup Reset simulator to any 100% power Ie Insert malfunction:

MAL-ATSOOSA Run the simulator.

Take a snapshot if this JPM is to be used more than once. File: 0590141601-1.doc Difficulty:

3 Time: 20 Task Number: 0590140501 3-AOP-FW-1 Page 8 of 8 INITIAL CONDITIONS:

The plant was operating at 100% 31 Main Boiler Feed Pump Speed Control Trouble Alarm 31 Main Boiler Feed Pump is in Track and All actions up to step 4.22 of 3-AOP-FW-1, Loss of Feedwater have INITIATING CUES: You are the Spare RO on shift. The CRS has directed you to perform Attachment 3 of 3-AOP-FW-1 for 31 MBFP in Track & Hold. Task Start a Hyd rogen Recom bi ner Page 1 of 8 ENTERGY (IP3) JOB PERFORMANCE MEASURE Operator Employee ID 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: Task Number: 0280010501 3 SOP-CB-7 Start a Hydrogen Recombiner Page 2 of 8 JPM Title: Start a Hydrogen Recombiner JPM Number: S-5(e) KA Number and Importance:

028000A401 Ability to manually operate and/or monitor in the control room: -HRPS controls RO -4.0 SRO -4.0 Suggested Environment:

Simulator Actual Testing Environment:

Alternate Path: NO Time Critical:

NO Estimated Time: Actual Time:

References:

3-S0P-CB-007 H2 Recombiner Operation File: 0280011601*1.doc Difficulty:

3 Time: Task Number: 0280010501 3 SOp*CB*?

Start a Hydrogen Recombiner Page 3 of 8 INITIAL CONDITIONS:

A Large Break LOCA occurred 2 days All actions of ES-1.4 Transfer to Hot Leg Recirculation have been The Operating Crew Transitioned back to ES-1.3, Transfer to Cold Containment Hydrogen has slowly risen to Current VC Pressure -2 Pre-LOCA VC Pressure -0 Pre-LOCA VC Temperature

-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: Task Number: 0280010501 3 SOP-CB-7 I Start a Hydrogen Page 4 Denotes Critical Step STEP DESCRIPTIONS I CUES &NOTES Inform operator to BEGIN after his . completion of review of the Initiating Cues and log time below 1. Commence evaluation Energize 31 H2 Recombiner by placing breaker in ON 2. CUE: NPO reports breaker closed Verify Control Power Available light is lit on Hydrogen Recombiner Panel 3. CUE: Control Power White Light is Lit Verify Manual Heater Power Adjust 4. potentiometer is set to 000 Verify Heater Mode Selector Switch is in 5. Manual Note the following Current VC Pressure *

Pre-LOCA VC Pressure

Pre-LOCA VC Temperature

6. CUE: If Simulating this JPM

Current VC Pressure -2 psig

Pre-LOCA VC Pressure -0 psig

Pre-LOCA VC Temperature

-9soF Determine Pressure Correction Factor (Cp) 17. using Attachment 2 S. Record Cp on Attachment 4 Determine Required Heater Power on 19. Attachment 4 (Cp X 42.3 KW) STANDARD Directs NPO to close the breaker for 31 H2 Recombiner on MCC-36C Observes Control Power Light Rotate potentiometer fully counterclockwise Observes Switch in Manual Record parameters Determine Cp 1 .165 +/-.005 Enters 1.165 on Attachment 4 Determine approximately 49.3 KW File: 0280011601-1.doc Difficulty:

3 Time: Task Number: 0280010501 3 SOP-CB-7 Start a Hydrogen Recombiner Page 5 of 8 STEP 110. DESCRIPTIONS t CUES & NOTES Place Recombiner Control Switch in Start and Release 111. CUE: Green Light OFF Red Light ON Slowly Adjust Manual Heater Power until 5 KW is indicated on Heater Power Meter and Hold for 10 minutes 112 CUE: Meter indicates 5 KW Slowly Adjust Manual Heater Power until 10 KW is indicated on Heater Power Meter and Hold for 10 minutes 113. CUE: Meter indicates 10 KW Slowly Adjust Manual Heater Power until 20 KW is indicated on Heater Power Meter and Hold for 5 0 minutes 114 CUE: Meter indicates 20 KW Adjust Manual Heater Power as required to maintain Required Heater Power per Attachment 4 CUE: Meter indicates 49.3 KW JPM Complete STANDARD Rotate Switch to Start and spring return to neutral Rotate potentiometer clockwise observe heater power meter Rotate potentiometer clockwise observe heater power meter Rotate potentiometer clockwise observe heater power meter Rotate potentiometer clockwise observe heater power meter StU File: 0280011601-1.doc Difficulty:

3 Time: Task Number: 0280010501 3 SOP-C8-7 Start a Hydrogen Recombiner Page 6 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:

File: 0280011601-1.doc Difficulty:

3 Time: Task Number: 0280010501 3 SOP-CB-7 Start a Hydrogen Recombiner Page 7 of 8 Reset the Simulator to any IC. It is not necessary to establish Post LOCA conditions.

File: 0280011601-1.doc Difficulty:

3 Time: Task Number: 0280010501 3 SOP-CB-7 Page 8 of8 INITIAL CONDITIONS:

A Large Break LOCA occurred 2 days All actions of ES-1.4 Transfer to Hot Leg Recirculation have been The Operating Crew Transitioned back to ES-1.3, Transfer to Cold Containment Hydrogen has slowly risen to Current VC Pressure -2 Pre-LOCA VC Pressure -0 Pre-LOCA VC Temperature

-INrnATING CUES: You are the BOP and the CRS has directed you to place the 31 Hydrogen Recombiner in service. I Task Remove a Power Range Nuclear Instrument From Page 1 of 9 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0150021601-1.doc Difficulty:

2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 2 of 9 (-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: Actual Time: ___

References:

3-S0P-NI-001 Excore Nuclear Instrumentation System Operation File: 0150021601-1.doc Difficulty:

2 Time: 25 Task Number: 0150020501 3-S0P-N 1-00 1 Remove a Power Range Nuclear Instrument From Page 30f9 INITIAL CONDITIONS The plant is operating at 100% Power Range Channel N41 is operating The Shift Manager has declared N41 INITIATING You are the BOP and the CRS has directed you to remove channel N41 TASK Channel N41 removed from File: 0150021601-1.doc Difficulty:

2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Page 4 of 9 Denotes Critical Step DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Commence evaluation Circle selected channel If removing channel from service due to partial failure obtain guidance from I&C and Reactor Engineering.

3. CUE: Channel is NOT being removed from service due to partial failure Place Dropped Rod Mode Selector Switch in 14. BYPASS If Control Power is available check Dropped Rod Bypass lamp illuminated NIS Rod Dropp Bypass PR 41 lamp on 5. '. Panel FBF is illuminated NIS Trip Bypass alarm on Panel SBF-1 is annunciated Place applicable Rod Stop Bypass switch in 16. BYPASS PR N41 Place applicable Power Range Channel Percent Power Computer Input Out of Limit Check CUE: The STA will remove channel from limit check Observe Warning Caution and Notes Block the dropped rod protection bypass relays for the selected channel by placing the 19, blocking strip across the back of the relay NOTE Blocking strips are installed STANDARD Circles N41 Switch rotated to BYPASS Checks lamps illuminated Rotate Switch to N41 Position Reviews Warning Caution and Notes Screw bolt in to engage relay File: 0150021601-1,doc Difficulty:

2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 50f9 DESCRIPTIONS I CUES & NOTES Defeat selected channel AT signal by placing the delta T Defeat Switch in Defeat Channel 1 110. Rack B-8 Verify AT Recorder selected to unselected

11. channel Observe caution Check the Overtemperature AT bistables for the unselected channels are extinguished on panel SOF Observe Note Place the Overtemperature AT bistable for Loop 1 Over Temp Trip in the tripped position RackA-4 Check Overtemperature AT bistable for Loop 1 Over Temp Trip is . Panel Check Overtemp AT Channel Trip or Rod Stop 17. alarm lit on panel SAF Verify Rod Control Mode Selector Switch is in 18. Manual Place Power Mismatch Bypass Switch in 119. PYBASS PR N41 When a minimum of two minutes has elapsed, 20. Return Rod Control to Automatiic Place Detector Current Comparator Upper 121. Section Switch in PR N41 Place Detector Current Comparator Lower 122. Section Switch in PR N41 STANDARD S/U Rotate Switch to Defeat Ch 1 Rotate recorder switch to channel 2, 3,or4 Review Caution NA the Selected Channel and Checks the remaining channels extinguished Reviews Note Places trip switch in the up position Observes light illuminated Observes annunciator lit Observes Switch is in Manual Rotates Switch to position Rotates Rod Control Mode Selector Switch to Automatic Rotates switch to PR position Rotates switch to PR position File: 0150021601 Difficulty:

2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 6 of9 STEP 123. 24. 25. 26. 27. .28. 29. 30. 31. DESCRIPTIONS I CUES &NOTES Place Comparator Channel Defeat Switch to N41 position Check Comparator Defeat light is lit Check no other overpower high range hi flux trip bistables are tripped on Bistable Status Panel Panel SOF Check if overpower low range high flux trips are NOT Blocked Observe NOTES Trip all NIS bistables associated with the selecte channel by removing both instrument and control power fuses Check alarms on Panel SBF-1 NIS Power Range Loss of Detector Voltage NIS Poser Range Single Channel High Range Trip Check Overpower High Range Hi Flux Trip bistable for N41 is lit Panel SOF Verify NR-45 Recorder selected to an unselected channel JPM Complete STANDARD S/U Rotates switch to N41 position Observes light lit Observes no other light lit Observes Overpower Low range high flux trip are blocked Reviews Notes Removes fuses Observes alarms lit Observes light lit Rotate switch to ChanneI2,3,or4if necessary File: 01S0021601-1.doc Difficulty:

2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Remove a Power Range Nuclear Instrument From Service Page 8of9 Reset Simulator to any 100% Power IC. File: 0150021601-1.doc Difficulty:

2 Time: 25 Task Number: 0150020501 3-S0P-NI-001 Page 9 of 9 INITIAL CONDITIONS The plant is operating at 100% Power Range Channel N41 is operating The Shift Manager has declared N41 INITIATING CUES: You are the BOP and the CRS has directed you to remove channel N41 from sevice Task Reset R-18 Alarm Setpoint using the RM-23A Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0730161601"1.doc Difficulty:

3 Time: 10 Task Number: 0730160101 3"SOP"RM"008 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 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 3 of8 INITIAL CONDITIONS Preparations are underway to release 31 Waste Holdup Tank The current alarm setpoint for R-18 is 4.0 X 10-4jJCi/ml The calculated alarm setpoint for the release is 1.25 X 10.3 jJCi/ml The Bantam 11 Control Cabinet is OOS for maintenance.

INITIATING CUES: You are the BOP and the CRS has directed you to reset the Alarm setpoint for 18 to 1.25 X 10.3 jJCi/ml using the RM-23A in accordance with 3-S0P-RM-008 Step 4.3.5.3. TASK STANDARD:

R-18 Alarm setpoint is reset using the RM-23A controller.

File: 0730161601-1.doc Difficulty:

3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Page 4 of 8 { Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Commence evaluation Determine NOT changing R-1 or R-33 2. Setpoint Depress Channel Insert key and tum Norm Supervisor switch to 14. Supervisor

5. Verify SUPV Mode LED is ON If changing High Alarm set point ENTER 009 Determine NOT changing Alert set point at this 7. time Depress ITEM and verify current setpoint is 18. displays Enter new set pOint using the following format 19. [1] [2] [5] [-] [0] Verify desired value is displayed then 110. ENTER key Tum Normal Supervisory Key Switch to 111. NORMAL and remove key Depress desired channel button to return 12 display to normal STANDARD Given in initial conditions Depresses R 18 LlQ button on RM-23A Insert Key and rotate switch to Supervisor Observes SUPV Mode LED ON Enter 0 0 9 using keypad Depresses ITEM button and observes digital display Enters data in stated format Observes digital display correct then presses ENTER key Rotate key to NORM and remove Depress R 18 LlQ button File: 0730161601-1.doc Difficulty:

3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Page 5 of DESCRIPTIONS I CUES & NO"rES STANDARD S/U IF RM-23A alarm set point was changed Verify Observes LED is 13 Supv Mode LED is OFF JPM is File: 0730161601-1.doc Difficulty:

3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 6 of 8 Any area of weakness observed?

YEsDNOD Examinee Signature All areas of observed weakness discussed Evaluator Initials Description of problem area: Description of reviewed information:

File: 0730161601-1.doc Difficulty:

3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Reset R-18 Alarm Setpoint using the RM-23A Module Page 7 of 8 This JPM can be run from any IC . .. 'il;.. File: 0730161601-1.doc Difficulty:

3 Time: 10 Task Number: 0730160101 3-S0P-RM-008 Page 8 of 8 INITIAL CONDITIONS INITIATING CUES: Task Transfer Buses 1 -4 to the Station Aux Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0800031601-1.doc Difficulty: 2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 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: Actual Time: ___ .l***/

References:

3-S0P-EL-005 Operation of On-Site Power Sources File: 0800031601-1.doc Difficulty:

2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 30f9 (':i,;# 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 eRS has directed you to Transfer Buses 1 -4 to the Station Aux Transformer in accordance with 3 SOP-EL-005 section 4.4. TASK STANDARD:

Buses 1 -4 are energized from the Station Aux Transformer and Unit Aux Transformer breakers are open. File: 0800031601-1.doc Difficulty:

2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 4 of9 ! I Denotes Critical Step DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below Commence evaluation Observe NOTES before step 4.4.1 Ensure less than 100 volts difference between 3. Station and Unit Auxiliary Transformers If desired to transfer 6.9 KV Bus 1 to the Station Aux Transformer Perform Voltage Check per step 4.4.1 Place 6900 Bus 1 Synchroscope in Bus 1 Bus 15. 5 position If Synchroscope is at 12 o'clock then Close the .6. Bus No. 1-5 Tie Breaker 17. Open 6900 Bus 2 Normal Feed Breaker Place 6900 Bus No. 1 Synchroscope in Off Ensure less than 2000 amps on 6900 KV bus 9. 5 If desired to transfer 6.9 KV Bus 2 to the Station Aux Transformer File: 0800031601-1.doc Difficulty:

2 Task Number: 0800020201 3-S0P-EL-005 STANDARD Reviews Notes Observe Meters; Adjusts Unit Aux Transformer Tap Changer if necessary Determine transfer is desired Observe Station Aux and UnitAux transformer voltage meters Places handle in switch location and rotate switch to bus 1 bus 5 position Rotate Switch to Close then release to auto Rotate Switch to Open the release to auto Rotate switch to Off Observe meter determines

< 2000 amps Determine transfer is desired Time: 15 minutes Simulator Transfer Buses 1 -4 to the Station Aux Transformer Page 50f9 DESCRIPTIONS I CUES &NOTES Ensure both 2A-3A Tie breaker is Open Perform Voltage Check per step 4.4.1 Place 6900 Bus 2 Synchroscope in Bus 2 Bus 112. 5 position If Synchroscope is at 12 o'clock then Close the 113. Bus No. 2-5 Tie Breaker 114. Open 6900 Bus 2 Normal Feed Breaker Place 6900 Bus No.2 Synchroscope in Off Ensure less than 2000 amps on 6900 KV bus 16. 5 If desired to transfer 6.9 KV Bus 3 to the Station Aux Transformer Ensure both 2A-3A Tie breaker is Open Perform Voltage Check per step 4.4.1 Place 6900 Bus 3 Synchroscope in Bus 3 Bus 119. 6 position If Synchroscope is at 12 o'clock then Close the .20. Bus No. 3-6 Tie Breaker 121. Open 6900 Bus 3 Normal Feed Breaker STANDARD S/U Observes breaker Open Observe Station Aux and UnitAux transformer voltage meters Places handle in switch location and rotate switch to bus 1 bus 5 position Rotate Switch to Close then release to auto Rotate Switch to Open the release to auto Rotate switch to Off Observe meter determines

< 2000 amps Determine transfer is desired Observes breaker Open Observe Station Aux and UnitAux transformer voltage meters Places handle in switch location and rotate switch to bus 1 bus 5 position Rotate Switch to Close then release to auto Rotate Switch to Open the release to auto File: 0800031601-1.doc Difficulty:

2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 6 of 9 STEP DESCRIPTIONS I CUES &NOTES Place 6900 Bus NO.3 Synchroscope in Off Ensure less than 2000 amps on 6900 KV bus 23. 6 If desired to transfer 6.9 KV Bus 4 to the Station Aux Transformer Perform Voltage Check per step 4.4.1 Place 6900 Bus 4 Synchroscope in Bus 4 Bus 125. 6 position If Synchroscope is at 12 o'clock then Close the 126. Bus No. 4-6 Tie Breaker 127. Open 6900 Bus 4 Normal Feed Breaker Place 6900 Bus No.4 Synchroscope in Off Ensure less than 2000 amps on 6900 KV bus 29. 6 When transfer complete, ensure Unit Aux and 30. Station Aux Tap Changers are in automatic JPM is complete STANDARD SJU Rotate switch to Off Observe meter determines

< 2000 amps Determine transfer is desired Observe Station Aux and UnitAux transformer voltage meters Places handle in switch location and rotate switch to bus 1 bus 5 position Rotate Switch to Close then release to auto Rotate Switch to Open the release to auto Rotate switch to Off Observe meter determines

< 2000 amps Ensure both tap changer switches are pulled out File: 0800031601-1.doc Difficulty:

2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 7 of 9 ,>' Any area of weakness observed?

YES DNOD;i:1iJ' Examinee Signature All areas of observed Evaluator Description of problem area: Description of reviewed information:

File: 0800031601-1,doc Difficulty:

2 Time: 15 Task Number: 0800020201 3-S0P-El-005 Transfer Buses 1 -4 to the Station Aux Transformer Page 8 of 9 Simulator Setup Reset Simulator to Ie -9 Reduce Load to < 40 MWe Take a snapshot if JPM is to be used more than once. File: 0800031601-1.doc Difficulty:

2 Time: 15 Task Number: 0800020201 3-S0P-EL-005 Page 90f9 ,

.._( 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 Locally Start 32 Aux Boiler Page 1 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0610011604-1.doc Difficulty:

3 Time: 20 Task Number: 0610010404 3-S0P-ESP-1 In

" Locally Start 32 Aux Boiler Page 2 of JPM Title: Locally Start 32 Aux Boiler Feedpump JPM Number: In Plant 1 (j) KA Number and Importance:

2.1.30 Ability to locate and operate components, including local controls.

RO 4.4 SRO 4.0 Suggested Environment:

In Plant Actual Testing Environment:

Alternate Path: YES Time Critical:

NO Estimated Time: Actual Time:

References:

3-S0P-ESP-001 Local Equipment Operation and Contingency Actions File: 0610011604-1.doc Difficulty:

3 Time: 20 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump Page 30f7 INITIAL CONDITIONS:

1. The Control Room has been evacuated due to a fire. 2. No ABFPs started. 3. An NPO is available to control feedwater flow to the individual SGs. INITIATING CUES: You are the RO in the ABFP Building and the eRS has directed you to locally start 32 ABFPper 3-S0P-ESP-001, section 4.1.8 up to and including section 4.1.8.11 Inform the RO when 32 ABFP discharge pressure is 600 psig. TASK STANDARD:

32 ABFP running with approximately 600 psig discharge pressure File: 0610011604-1.doc Difficulty:

3 Time: 20 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Page 4 of7

Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES I NOTE: Remind operator to NOT change any switch or valve positions 1 Obtain correct procedure Determine if MS-PCV-1310A, 32 ABFP Steam Supply Isolation valve, is OPEN 2 CUE: Valve is OPEN Determine if MS-PCV-1310B, 32 ABFP steam Supply Isolation valve, is OPEN 3 CUE: Valve is OPEN If directed to use handwheels to control FCVs then rotate applicable FCV handwheels in the 4. closed direction CUE: The NPO will control individual FCVs ADJUST HCV-1118 32 ABFP Turbine Speed Control manual handwheel for idle speed CUE: Handwheel in close CLOSE IA-865 32 ABFP MS-HCV-1118 Instrument Air Isolation valve *16 CUE: Valve closed BLEED off air from 32 ABFP MS-HCV-1118 by removing cap and opening MS-456 CUE: Cap removed and valve OPEN HCV-1118, 32 ABFP Turbine Speed Control valve approximately 1/8" 18 CUE: Valve open 1/8" STANDARD StU 3-S0P-ESP-001, section 4.1.8 Observes valve stem limit switch position Observes valve stem limit switch position Direct the NPO to perform steps 4.1.8.7 a through e CLOSE 1118 using manual handwheel CLOSE IA-865 Remove cap and OPEN MS-456 Manual handwheel adjusted until valve stem -1/8" OPEN File: 0610011604-1.doc Difficulty:

3 Time: 20 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump Page 5 of7 STEP DESCRIPTIONS

/ CUES & NOTES Start 32 CUE: Turbine heard increasing speed of pump 10 Review notes prior to step 4.1.8.10 Verify correct discharge pressure for 32 CUE: Discharge pressure indicated 250 Adjust PCV-1139 AIM station manual loading pressure to match the instrument loading pressure 112 (do not exceed 13 psig) CUE: Pressure indicates 12.5 psig Turn the Auto/Manual switch on the PCV-1139 113 AIM station to MANUAL Slowly adjust PC-1139 AM Station Manual loading pressure to approximately 12 psig 114 CUE: Indicator reads 12 psig Adjust PC-1139 AIM station Manual Loading pressure to maintain steam inlet pressure to 32 115 Aux Boiler Feed Pump turbine at approximately 600 psig Adjust turbine speed using HCV-1118 until discharge pressure is 600 psig ,116 CUE: Discharge pressure indicates 600 psig Inform CCR 32 ABFP discharge pressure is 600 psig CUE: CCR acknowledges STANDARD StU Place 32 ABFP Trip/Auto/On local control switch to ON Notes reviewed Observes 32 ABFP discharge pressure gauge NOT indicating 600 psig Rotate handle until pressure indicates approximately 12 12.5 psig Switch rotated to Manual Rotate knob until indicator 12 psig Observe inlet pressure approximately 600 psig Observes discharge pressure approximately 600 CCR Informed File: 0610011604-1.doc Difficulty:

3 Time: 20 Task Number: 0610010404 3-S0P-ESP-1 In Locally Start 32 Aux Boiler Feedpump 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:

Difficulty:

3 Time: 20 Task Number: 0610010404 In Page 7 of7 INITIAL CONDITIONS:

1. The Control Room has been evacuated due to a fire. 2. No ABFPs started. 3. An NPO is available to control feedwater flow to the individual SGs. 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 Inform the RO when 32 ABFP discharge pressure is 600 psig. Task v Start 32 CCW Pump from Page 1 ENTERGY JOB PERFORMANCE Operator Name: Employee 10 #: Evaluator:

UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: 0840281604*1.doc Difficulty:

2 Time: 10 Task Number: 0840280504 3*S0P*EL*12 In l Start 32 CCW Pump from MCC312A Page 2 of7 JPM Title: Start 32 CCW Pump from MCC312A\t. JPM Number: In Plant KA Number and Importance:

2.1.30 Ability to locate and components, including local RO 4.4 SRO Suggested Environment:

In Actual Testing Alternate Path: Time Critical: Estimated Time: Actual Time: ,

3-AOP-SSD-1 Control Room Inaccessibility Safe File: 0840281604-1.doc Difficulty:

2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Start 32 CCW Pump from Page I, INITIAL CONDITIONS:

- '}i!!lJill" 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 32 CCW Pump running from its alternate feed File: 0840281604-1.doc Difficulty:

2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Start 32 CCW Pump from Page 4 of 7 I Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation Remove load from Bus 312 per Attachment 1 2. CUE: MCC-A, Cor E-1 feeder breaker open Visually verify 32 CCW pump is not running 3 CUE: Nuclear NPO reports 32 CCW pump is not running Verify 32 CCW Pumps transfer switch is de-energized

4. CUE: Nuclear NPO reports all 8 lights are extinguished

5. Review Caution and Note Unlock and place 32 CCW pump alternate feed transfer switch in Alternate feed position *16 CUE: Nuclear NPO reports transfer switch rotated clockwise 360 0 to Alternate Feed position Unlock and place disconnect switch on 312A for 32 CCW pump to on 17 CUE: Disconnect switch is on Start 32 CCW pump 18 CUE: Key switch in start position Verify 32 CCW pump is running 9 CUE: Red running light is illuminated File: 0840281604*1.doc Difficulty: 2 Task Number: 0840280504 3-S0P-EL-12 STANDARD MCC-A feeder OR MCC-C feeder OR MCC-E-1 feeder open Direct Nuclear NPO to verify pump is not running Direct Nuclear NPO to verify all eight indicating lights are off Caution and Note reviewed Direct Nuclear NPO to rotate disconnect switch 360 0 to a Itemate feed position Unlock and place disconnect switch to on Push in and turn key switch to start position Observe red running light illuminates Time: 10 minutes In Plant Start 32 CCW Pump from MCC312A Page 5 of7 STEP DESCRIPTIONS t CUES & NOTES STANDARD StU JPM Complete File: 0840281604-1.doc Difficulty:

2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Start 32 CCW Pump from MCC312A Page 6 of7 1'1' t Any area of weakness observed?

YEsDNOD Examinee Signature All areas of observed Evaluator Description of problem area: Description of reviewed information:

File: 0840281604-1.doc Difficulty:

2 Time: 10 Task Number: 0840280504 3-S0P-EL-12 In Page 7 of 7 INITIAL CONDITIONS:

The plant is in MODE 3 Control of 32 CCW pump from the Control Room is prevented due to Control Room evacuation due to a fire Normal 480 volt power to the CCW pumps is not available 32 CCW pump will be the only load on MCC-312A Power is available to MCCs-312 and 312A The Nuclear NPO is standing by to assist you INITIATING You are the BOP and the Shift Manager has directed you to transfer the supply for 32 CCW pump to MCC-312A and start the pump per Section Task Perform Local Containment Isolation Valve Lineup Page 1 of ENTERGY JOB PERFORMANCE Operator Name: Employee ID #: Evaluator:

Date: SAT UNSAT This JPM was administered for qualification?

YES NO The Training Department developed this material for the Entergy training programs.

Text materials and figures contained in this document are developed for the purpose of instruction and should not be used in connection with either plant maintenance or plant operation.

This material may not be reproduced without the authorization of the Manager, Nuclear Training.

File: Difficulty:

3 Time: 20 Task Number: 3-S0P-CB-11 In Perform Local Containment Isolation Valve Lineup Page 2 of JPM Title: Perform Local Containment Isolation Valve JPM Number: In Plant -KA Number and Importance:

2.1.30 Ability to locate and components, including local RO 4.4 SRO Suggested Environment:

In Actual Testing Alternate Path: Time Critical: Estimated Time: Actual Time: __

3-S0P-C8-11 Non-Automatic Containment Isolation File: Difficulty:

3 Time: 20 Task Number: 3-S0P-C8-11 In Perform Local Containment Isolation Valve Lineup IVSW Page 3 of 7 INITIAL CONDITIONS:

The plant experienced a Small Break The operating crew is in 3-ES-1.3, Transfer to Cold Leg Internal Recirculation is All RCPs are INITIATING CUES: You are the Nuc Side NPO and the CRS has directed you to perform 11 Attachment 1 steps 1-5. TASK STANDARD:

3-S0P-CB-11 Attachment 1 Steps 1-5 complete.

File: Difficulty:

3 Time: 20 Task Number: 3-S0P-CB-11 In I Perform Local Containment Isolation Valve Lineup Page 4 of 7 Denotes Critical Step STEP DESCRIPTIONS I CUES & NOTES Inform operator to BEGIN after his completion of review of the Initiating Cues and log time below 1. Commence evaluation

2. Observe Note before Step 1 Open IV-1492 Manual N21VSW Header 13. Isolation Open IV-1493 Manual Seal Water Header 14. Isolation Open IV-1443 ManualN2 Header 15. 1090 Outlet Isolation Close SI-859A Accumulator Drain/Safety

6. Injection Test Une Isolation Close SI-859C Accumulator Drain/Safety

7. Injection Test Une Isolation Close SA-24-1 Station Air to Containment

18. Containment Isolation Valve Close SA-24-2 Station Air to Containment

.9. Containment Isolation Valve STANDARD S/U Observes Note Locates and Opens Valve Locates and Opens Valve Locates and Opens Valve Verified Closed Using COL Verified Closed Using COL Locates and Closes Valve Locates and Closes Valve File: Difficulty:

3 Time: 20 Task Number: 3-S0P-CB-11 In Perform Local Containment Isolation Valve Lineup IVSW Page 5 of7 STEP DESCRIPTIONS I CUES &NOTES Ensure Breakers are Open MCC-36C AC-MOV-743 RHR Miniflow Isolation AC-MOV-744 RHR Pump Discharge Isolation CH-MOV-441 31 RCP Seal Injection Isolation CH-MOV-442 32 RCP Seal Injection 110. Isolation CH-MOV-443 33 RCP Seal Injection Isolation CH-MOV-444 34 RCP Seal Injection Isolation SI-MOV-885A Containment Sump RHR Suction Ensure Breakers are Open MCC-36C AC-MOV-1870 RHR Miniflow Isolation CH-MOV-250A 31 RCP Seal Injection Isolation CH-MOV-250B 32 RCP Seal Injection Isolation* CH-MOV-250C 33 RCP Seal Injection Isolation CH-MOV-250D 34 RCP Seal Injection Isolation SI-MOV-885BA Containment Sump RHR JPM STANDARD Locate and Observe Breakers Open If necessary Simulate Opening Breakers Locate and Observe Breakers Open If necessary Simulate Opening Breakers Difficulty:

3 Time: 20 minutes Task Number:

In Plant Perform Local Containment Isolation Valve Lineup IVSW Page 6 of7 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:

3 Time: 20 Task Number: 3*S0P*C8-11 In Page 7 of7 INITIAL CONDITIONS:

The plant experienced a Small Break The operating crew is in 3-ES-1.2, Post LOCA Cooldown and INITIATING CUES: You are the Nuc Side NPO and the CRS has directed you to perform 11 Attachment 1 steps 1-5. Task Appendix D Scenario Outline Form ES-D-1 Facility:

IPEC Unit3 Scenario No.: 1 Op-Test No.: 1 Examiners:

Operators:

Initial Plant is at 45%. 31 EDG is OOS for an oil system Return power to 100%.31 EDG is OOS and not expected back on this Event Malf. No. No. 1 NIA 2 PRS006 B 3 CVCOO3 4 EPSOO5 D 5 ATS004 AlB PRSOO3 D 6 SIS004A IB 7 EPSOO1 Event Type* R(ATC) N(BOP} . N(CRS) I(ALL) TS(CRS) C(ALL) TS(CRS) C(ALL) M(ALL) C(CRS) C(ALL) * (N)ormal, (R}eactivity, Event Description Perform power ascension.

Controlling PZR level instrument fails low causing letdown to isolate. Channel is defeated and letdown is restored.

Letdown leak inside containment.

Leak will be isolated.

480V Bus 6A fault. Sequential loss of Main Feedwater Pumps leading to plant trip. PORV fails open, cannot be isolated.

31 and 32 Safety Injection Pumps will not auto-start. (Neither board operator credited since either one may start pump.) Station Blackout when Containment Phase A is reset. (l)nstrument, (C}omponent, (M)aior 2010 IP3 NRC Exam Scenario 1 Page 10f 13 Session Outline: The session begins with power at 45% and 31 EDG out of service for an oil system modification.

The team has been instructed to return the plant to 100% at 10% an hour. They will begin raising power per POP-2.1, "Operation above 45% Power". When sufficient load ascension has been observed, the controlling PZR Level channel will fail low causing Letdown to isolate, The team will respond and restore Letdown per AOP-INST-1, "Instrument or Controller Failures", When Letdown has been restored, a leak will occur on the Letdown line inside containment.

This can be isolated per AOP-LEAK-1, "Sudden Increase in Reactor Coolant System Leakage".

Following leak isolation, a fault of 480V Bus 6A will occur. The team will respond per AOP-480V-1, "Loss of Normal Power to any Safeguards 480V Bus". When the team has had time to address Charging, Service Water and RCP seal cooling, the Main Boiler Feed Pumps will sequentially trip. In response, the Team will trip the reactor as per the guidance of AOP-FW-1, "Loss of Feedwater" (although formal entry into the AOP is not required).

On the trip, PORV PCV-456 will fail open. Since Bus 6A is faulted, the MOV Block valve for this PORV cannot be closed. 31 and 32 SI pumps will not start, but can be started manually.

RCPs will be tripped due to loss of subcooling, A LOOP will occur when Containment Isolation Phase A is reset. The team will have to respond per EOP LOOP-1, "Loss of Offsite Power after SI Reset", When the team announces transition to E-1, the scenario will be terminated.

Procedure flowpath:

POP-2.1, AOP-INST-1, AOP-Leak-1, AOP-480V-1, E-O, LOOP-1, E-1 Critical Tasks: CT 1: Start at least 1 High Head Safety Injection Pump. CT 2: Trip RCPs when RCP trip criteria are met. CT 3: Start Essential Service Water Pump to cool EDGs following LOOP, 2010 IP3 NRC Exam Scenario 1 Page 20f 13 Setup/Event IC Reset SES Setup Batch File Floor Setup Event Event Role Play Event 3

Role Play Event 4 Simulator Setup and Instructor Directions INSTRUCTOR Expected response/instructor cues ACTIONS Reset Simulator to 65% power IC Loads L T -460 fails low on trigger 2 Run setup schedule 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 Perform setup checklist.

HANG PROTECTED EQUIPMENT tags for: Update the Protected 32 and 33 EDG Equipment PC. PTO 31 EDG Risk is Yellow Power Ascension Make notifications as requested by team. Click the Trigger 2 LT-460 fails low w/o ramp or delay button MAL-PRS006B at lead evaluator direction.

If I&C requested to Inform team that a troubleshooting investigate:

package is being developed.

Letdown leak in VC w/o ramp or delay Click the Trigger 3 MAL-CVC003 button at lead evaluator direction.

When called to support Open/adjust 33 charging pump recirc Excess Letdown valve Fault on Bus 6A w/o ramp or delay Click the Trigger 4 button MAL-EPS005D at lead evaluator direction I 2010 IP3 NRC Exam Scenario 1 Page 30f 13 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS Role Play If asked to investigate Bus6A Event 5 Click the Trigger 5 button at lead evaluator direction Role Play If asked for field actions Expected response/instructor cues Bus has smell of ozone and probably tripped on actual fault. More troubleshooting will be required .

MBFPs trip sequentially 31 trips on trigger MAL-ATS004A 32 trips with 60 second delay ATS004B Support team as requested.

2010 IP3 NRC Exam Scenario 1 Page 40f 13 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: Page 1 of 1 Event

Description:

Power Ascension 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 When sufficient load ascension has been observed notify booth to i Event 2. 2010 IP3 NRC Exam Scenario Page 50f 13 Appendix Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No.: 1 Event No.: Page 1 of 1 Event

Description:

Controlling PZR Level instrument fails low. Time Applicant's Actions or Behavior Diagnose level failure based on:

PZR Low Level Alarm

LCV-459 Indicates Closed Announce failure of PT -460 Place charging pump controller in 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 L/460A LEVEL DEFEAT in DFT CH2 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. Most limiting AOT is hours to trip bistables When T.S. has been referenced, the next event can be entered. The next step in the is to trip bistables.lfthis is observed bistable Loop 2 High Level Trip in rack A-10 will Lead Evaluator Instruct booth to enter Event 3 2010 IP3 NRC Exam Scenario Page 60t 13

_A-'-p-'-p_en_d_i_x_D

_________R_e_9....u_irEtd Operator Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: Page 1 of # Event

Description:

Letdown leak inside containment.

Time 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, CRS Enters AOP-LEAK-1 Sudden Increase in Reactor Coolant System Leakage CRS Will check for leaks in PORVs, Safeties, SGs CRS Go to section for letdown leak BOP Close 200B, 459 and 460 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 Have 33 Charging Pump recirc valve opened Open Excess Letdown isolation valves Align Excess Letdown to RCDT for warmup Align Excess Letdown to VCT* ATC Adjust charging pump speed to restore PZR level and maintain seal injection CRS Should address T.S. for RCS leakage and possibly PZR high level. 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 Page 70f 13 Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Page 1 of 1 Event

Description:

480V Bus 6A fault. ...... Position Applicant's Actions or Behavior CREW Diagnose Loss of Bus 6A ATC I BOP Start a charging pump Should call Nuke NPO to open recirc valve for running charging pump BOP Start SW Pumps after checking pressure CRS Check TS. in either 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AOT for inoperable 480V bus or due to 2 inoperable offsite circuits to bus. Note: Event may proceed, but there will be no resolution on returning power to the bus. II Lead Evaluator When sufficient actions have been observed have booth insert Event 5 2010 IP3 NRC Exam Scenario 1 Page Bof 13 Appendix Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No.: 1 Event No.: S Page 1 of 1 Event

Description:

Sequential loss of Main Feedwater Pumps leading to plant trip. Time 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 ATC Verifies reactor trip by Flux decreasing Rod Bottom Lights lit IRPls < 20 steps

Reactor trip and bypass breakers ATC Verifies turbine trip based on stop valve BOP Verifies Power to 480V

SA, 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. Actions will be continued on Event 6 2010 IP3 NRC Exam Scenario Page 90f 13

____________

__________..__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.

Position icant's Actions or Behavior CRS/ATC May observe that are no running HHSI pumps and start 31 and 32 SI Pum at this time. ATC Place 32 AFW pump in service to 33 and 34 SGs since 33 AFW does not have BOP or ATC 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

Reset Phase A initiate CRS/ATC

MBFP

MFRVs

SG Blowdown Valves

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

Containment Spray not required

RCP seal cooling ATC 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 SA from 33 EDG. Continued actions will be on Event 7 D-2 2010 IP3 NRC Exam Scenario 1 Page 100f 13 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event

Description:

Station Blackout when Containment Phase A is reset Page 1 of 1 Time Position CREW CRS BOP nose Loss of Offsite Power BOP ATC/BOP ATC/BOP ATe/BOP ATC CRS/ATC Lead Evaluator Starts 31 SI P Starts 31 and 33 Fan Cooler Units Establishes AFW flow to 31 and 32 SG from 32 AFW Start 31 Back in E-O determine need to transition to E-1 for stuck Terminate scenario when transition to E-1 is announced PORV 2010 IP3 NRC Exam Scenario 1 Page 110f 13 Appendix 0 Required Operator Actions Form ES-D-2 Emergency Classification ALERT: Per EAL 3.1.2 Primary system leakage exceeding capacity (75 gpm) of a single charging pump. 2010 IP3 NRC Exam Scenario 1 Page 120f 13 Turnover

% RCS PZR Press PZR Level RCS Total RCS Unidentified Condenser Air RCS Gas Risk Plant Equipment Status: 31 EDG is OOS for oil system modification.

Instructions:

Return unit to 100% at 10% per hour. Today/Now PowerOps 45% Equilibrium 1040 ppm Channel 1 Channel 2 0.1 gpm 0.01 gpm 6SCFM 1.78E-2 I-lCi/cc Yellow 2010 IP3 NRC Exam Scenario 1 Page 130f 13 Appendix Scenario Outline Form ES-O-1 Facility:

IPEC Unit 3 Scenario No.: Op-Test No.: .-1 Operators:

Initial Plant is at 5%.31 Charging Pump is OOS for Come up to 10% power, then warm up the MTG and place it in service. 31 Charging Pump is OOS not expected back on this Malf. Event Event No. Type* Description N/A R(ATC) Perform power ascension.

N(CRS) N(BOP) XMT-I(ALL) 32 SG Pressure Channel Failure causing ADV to TS(CRS) MAL-C(CRS) 31 CCW Pump trips and 32 CCW fails to C(BOP)MAL-C(CRS) CCW leak at 31 CCW Pump. Can be C(BOP)MAL-C(CRS) Main Steam header break with no MSIVs auto-closing and 1 MSIV MSSOO9 failing open. C(ATC)A MAL-M{ALL) Failure of the Reactor to trip both Auto and Manual. Team will RPSOO2 emergency borate and manually insert control rods. AlB MAL-C(BOP) 31 Fan Cooler Unit fails to I * (N)ormal, (R)eactivity, (I)nstrument. (C)omponent, (M)ajor 2010 IP3 NRC Exam Scenario Page 10f 16 Session Outline: The evaluation begins with the plant at 5% power ready to raise power and place the MTG in service. The following equipment is out of service: 31 Charging pump for PM. The team has been instructed to raise power to 10% and begin warming up the MTG to bring the unit on line. When sufficient power ascension has occurred, a failure of the 32 SG Pressure C channel 429C) will occur. 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 Building.

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 A TWS 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, 31 FCU does not auto-start.

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 I Simulator Setup and Instructor Directions INSTRUCTOR ACTIONS IC Reset SES Setup Load setup Schedule Schedule file File Transfer Actions to the Director Verify malfunctions I overrides entered Floor Perform setup checklist Distribute turnover sheets Event 1 Power Event 2 Actuate Event At lead evaluator direction

Role If NPO sent to investigate Role If I&C ask Event Actuate Event 3 At lead evaluator

direction Role If N PO sent 2010 IP3 NRC Exam Scenario 2 EXPECTED Reset Simulator to 5% power IC Holds off 31 Charging pump Inserts 31 FCU failure to auto-start Loads Rx trip breakers failure to auto-open Loads Rx trip breakers failure to manually open (from CCR) Loads 32 SG Press Channel C Failure on Event 1 Loads CCW pump failure on Event 2 Loads CCW leak on Event 3 Loads Main Steam header break on Event 4 Loads failure of all MSIVs to auto close

Loads failure of 34 MSIV to close in auto or manual Loads autostart failure of 32 CCW Pump Place cis in TPO and hang Danger 31 Charging Place Protected Equipment tags 32 & 33 Charging Update the protected equipment 32 SG Pressure Channel C will fail high ramp or MAL SGN002F to Nothing unusual at transmitter.

A troubleshooting package is being developed.

31 CCW Pump trips and 32 fails to MAL-CCW001 B to failure to autostart at MAL-CCW001A to Indications are that 31 CCW Pump breaker tripped on overcurrent.

Motor is hot and smells like winding damage may have occurred.

Page 30f 16 Simulator Setup and Instructor Directions Setup/Event Event 4 Role Play Role Play Role Play Event 5 INSTRUCTOR ACTIONS Actuate Event 4 At lead evaluator direction If NPO sent to investigate If NPO dispatched to makeup to CCW: LOA RMW012, 1 LOA RMW013, 1 If NPO dispatched to split headers:

LOACCW015

LOACCW016 Activate Event 5 At lead EXPECTED CCW Leak at 31 HX (will be reported as from 31 CCWseal) MAL-CCW005A to 500 with 120s ramp After NPO dispatched to locate leak, wait 2 minutes then report a lot of water is flowing out of 31 CCW pump seals. If the team directs the NPO to isolate the leak then, isolate by deleting CCWOO5A. Note: The CCW Surge tanks may empty if the leak is not isolated.

The team will then trip the operating CCW pumps and attempt to trip the reactor. Event 2 (steam line break) should be activated prior to the reactor trip. OPEN CCW makeup valves: PW-831A PW-831B Operate valves as requested:

NOTE: 832A I 764A not modeled i

759C 759D I Inserts Steam Break in Turbine Building

on East Header at 100,000 Ib/hr ramped i over.300 seconds. MAL-MSS009A to 100000 with 300s ramp 2010 IP3 NRC Exam Scenario 2 Page 40f 16 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS NOTE: MAL MSSOO9A Role Play As directed by lead evaluator After the Team diagnoses the steam break Role Play Event 6 If asked to locally close 34 MSIVs in the ABFP building ATWS Entered in Setup Role Play When NPO sent to locally open Rx Trip Breakers Delete reactor trip breaker malfunctions Role Play When NPO dispatched to isolate seal injection Event 7 Entered in Setup EXPECTED RESPONSE/INSTRUCTOR CUES If the Team delays, increase the size of the steam break until the Team Trips the Rx. Call as the NPO to the CCR and report there is a lot of steam in the Turbine Building and appears to be from the 33' elevation.

NPO is unable to close 34 MSIVs. It appears to stuck open. Rx trip breakers fail to open from the CCR. They will open when tripped open locally by the NPO Wait until Emergency Boration is commenced before locally opening reactor trip breakers MAL-RPSOO2A RTBs fail to open (auto) MAL-RPSOO2B RTBs fail to open (manual) 241A LOA-CVCOO7 241B LOA-CVCOO8 241C LOA-CVCOO9 2410 LOA-CVC010 Failure of 31 FCU to autostart.

2010 IP3 NRC Exam Scenario 2 Page Sot 16 Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: Event No.: _1_ Page _1_of .1 Event

Description:

Perform power ascension.

..'" 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 CRS Supervise reactivity Lead Evaluator When sufficient load ascension has been observed notify booth to Event 2010 IP3 NRC Exam Scenario 2 Page 60f 16 II Appendix D Required Operator _A_c_.....ti

_._o__n..c...s_____F_o_r_m_E_S_-_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 ADVOpen

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 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 I Lead Evaluator When bistables are tripped instruct booth to insert Event 3. 2010 IP3 NRC Exam Scenario 2 Page 70f 16

0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: 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 day 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 80f 16 I _A----'-pp'-e_n_d_i_x_D

______R_eq--'-u_i_re_d_O--'-p_e_ra_t_o_r

_A_c_ti_o_n_s

____Form ES-D-2 Op-Test No.: _1_ Scenario No.: 2 Event No.:-A-Page _1_of ..Q 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 event) ! ! CRS Enters AOP-CCW-1, Loss of CCW ! BOP Calls NPO to makeup 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 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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

___________

__

________F_o_r_m__

Op-Test No.: _1_ Scenario No.: Event No.: Page _1_of .1 Event

Description:

Main Steam header break with no MSIVs auto-closing and 1 MSIV failing open. limB I Position Applicant's Actions or CREW Diagnose steam break downstream of Noise Steam flow increase all channels Tavg lowering Turbine power lowering Reactor power increasing

CRS May enter AOP-UC-1 or may just give order to: Trip the reactor

Then close ATC Will attempt to trip Note: At this point actions will be tracked on D-2 for Events 6 and 7 2010 IP3 NRC Exam Scenario Page 100f 16 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenar i o No.: Event No.: l Page _1_of JI. Event Description

Failure of the Reactor to trip both Auto and Manual. Time Position icant's Actions or Behavior CRS Instruct team to n ..rTnrlrn immediate actions of FR-S1 ATC Will insert control rods BOP BOP the reactor BOP BOP/ATC Note: When emergency boration has been initiated, the NPO will trip the reactor locally. 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 VC ventilation i solation CRS Check SI status. SI will have actuated due to steam leak. BOP Performs 35 42 of E-O ATC Checks reactor is subcritical ATC Secures Emergency Boration (charging pump may be secured due to SI) Closes MOV-333 Place BATPs i n slow speed Place HCV-104/105 to 25% ATC Checks RCP seal cooli . CCW will be available for seal rnn,lInn 2010 IP3 NRC Exam Scenario 2 Page 110f 16 Appendix 0 Required Operator Actions Form ES-D-2 ATe 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 0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scena r io No.: ..L Event No.: Page _1_of .1 Event Description

3 1 Fan Cooler Unit fails to auto-start. Time Position icant's Actions or Behavior BOP While performing SI verification steps will note that 31 FCU did not start and will start it. CRStATC Return to E-O ATC If not done close MSIVs -34 will not close CRStATC Perform E-O actions:

Verify reactor trip

Verify turbine trip

Verify power t o 480V busses

Verify SI actuated CRStATC Verify AFW Flow:

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

This also be where team addresses faulted SG Note: It is critical that the following task be performed prior to exiting E-2, however it is acceptable and preferred that this action be performed sooner. BOPtATC BOP Performs RO-1 procedure for SI verification and reset:

Verifies SI equipment (may start 31 FCU if not already done) -. Resets SI

Resets Phase A 2010 IP3 NRC Exam Scenario 2 Page 130f 16 Appendix 0 CRS/ATC CRS Lead Evaluator Required Operator Actions Form ES-O-2 Continue with E-O: Verifies feedwater 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 Checks if SGs are

Announces transition to E-2, Faulted SG Isolation 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 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 Tumover DatelTime:

Today/Now Condition:

PowerOps % Power: 5% 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 6SCFM RCS Gas activity 1.78E-2 IJCi/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. 2010 IP3 NRC Exam Scenario 2 Page 160f 16 Appendix 0 Scenario Outline Form ES-O-1 Facility:

IPEC Unit 3 Scenario No.: 3 Op-Test No.: -.1 Examiners:

Operators:

Initial Plant is at 100%. 31 AFW Pump is OOS due to high vibrations.

PORV 455C is inoperable due blowing Maintain 100% power conditions.

31 AFW Pump is OOS due to high vibrations.

PORV 455C inoperable due to blowing . Malf. No. 1 CVC049 2 CVCOO5C 3 SGN005C 4 5 SGN005C PRS003D AI R002C 6 CFWOO1C 7 SISOO4A Event Type* I(ALL) C(ALL) TS(CRS) C(ALL) TS(CRS} R(ATC) N(CRS) N(BOP) M(ALL) C(CRS) C(ATC) C(BOP) Event Description VCT level instrument fails low. 33 Charging Pump Trip. 900 gpd SGTL on 33 SG. Tech Spec required shutdown.

SGTL becomes SGTR. PORV and Instrument Air to VC Valve failures will lead to loss of pressure control. 33 AFW Pump fails to 31 Safety Injection Pump fails to

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2010 IP3 NRC Exam Scenario 3 Page 10f 15 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 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago due to high vibrations during its PT (TS 3.7.5 -72 hr AOT) PORV 455C was declared inoperable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 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 Critical Tasks: CT 1: Establish 365 gpm AFW flow. CT 2: Isolate 33 SG (ruptured SG). CT 3: Establish and maintain cooldown in E-3. 2010 IP3 NRC Exam Scenario Page 20f 15 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS Ie Reset SES Setup Schedule File Ie 11 VerifY malfunctions

/ overrides entered Floor Setup Perform setup checklist Distribute turnover sheets Ensure Rx Vessel Head Vent valve fuses are available in A TC drawer Event #1 Role Play Click the Event 1 button At lead evaluator direction If I&C or NPO called to investigate Event #2 Role Play Click the Event 2 button At lead evaluator direction IfNPO sent to investigat SPONSEnNSTRUCTOR Reset Simulator for proper Ie Deenergizes 31 ABFP Deenergize PCV-455C & Block Valve 535 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 SI pump Loads failure ofPCV-1228 Ensure 33 Charging pump is in service Place cis in TPO and hang Danger tag for: 31 ABFP Place PORV 455C in Closed Place block valve 535 to TPO Remove PCV -455C fuses in rear of Flight Panel Place Protected Equipment tags for: 32 & 33 ABFPs Update the protected equipment PC display VCT Level Instrument Fails Low I&C will inform team that a troubleshooting package will be developed NPO will find no issues with the running charging pump 33 Charging pump trip CHARGING PUMP 33 TRIP NPO reports no obvious problems 2010 IP3 NRC Exam Scenario 3 Page 30t 15 Event #3 I Click the Event 3 button I SOTL on 33 S/O 900 gpd no ramp ! At lead evaluator I direction Insert malfunction SGN005C to 0.1 on event 3 STEAM GENERA TOR 33 TUBE LEAK Event #5 I Rol' Play I Click the Event 5 button At lead evaluator direction I

At CCR request SOTR on 33 S/O 400 gpm no ramp -Insert malfunction STEAM GENERATOR SGN005C to 201 on event 5 33 TUBE LEAK Perform various LOA's per NPO local task list i Role Play If asked to investigate 33 ABFP trip No obvious signs of pump problem but breaker shows over current trip 2010 IP3 NRC Exam Scenario 3 Page 40f 15

______R_equired Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: Event Page _1_of .1 Event

Description:

VCT level instrument fails low.

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 At this point there are no more actions until the instrument is repaired.

Instruct booth to insert Event 2. 2010 IP3 NRC Exam Scenario Page 50t 15 I Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: -L Page _1_of .1 Event

Description:

33 Charging Pump Trip. Position CREW CRS BOP ATC ATC BOP BOP BOP BOP BOP ATC BOP Lead Evaluator Applicant's Actions or Behavior Diagnose 33 Charging Pump Trip:

RCP Thermal Barrier Low DP Alarm

480V Motor Trip Alarm

Amber light on 33 Charging Pump Switch Enters AOP-CVCS-1 Closed LCV-459 and 460 Starts 31 or 32 Charging Pump Adjusts charging pump speed in manual to maintain 6-12 gpm seal injection flow Closes AOV-200B Place PCV-135 in manual and 50% Place TCV-130 in manual and 50% Opens LCV-459 and 460 Opens AOV-200B Increases charging pump speed Adjusts PCV-135 and TCV-130 as necessary and may return valves to auto at this time. 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.

Instruct the booth to insert Event 3. 2010 IP3 NRC Exam Scenario 3 Page 60f 15 II Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: Scenario No.: Event No.: Page _1_of .1 Event

Description:

900 gpd SGTL on 33 SG. Time Position Applicant's Actions or CREW Diagnoses

Increased trend on R-15 Steam Jet Air Ejector

Eventual Alert on R-15

Slight 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. Time compression will be used for chemistry BOP May perform Secondary Plant Isolation in parallel with SID:

Bypass and Isolate Condensate Polisher

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

Close LCV-1129 CRS Will determine that SID is required to be: * < 50% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Mode 3 within and additional 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Note: The plant ;s in a T.S. required shutdown, but this may have to discussed as a followup with CRS. Note: Actions will continue on Event 4 D-2 2010 IP3 NRC Exam Scenario 3 Page 70f 15

-.:;A:....:J.::.pJ:..pe.:::..:n:..::...d=i.:::..:x--=O=----

____

Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: -L Event No.: Page _1_of .1 Event

Description:

Tech Spec Shutdown ..." Applicant's Actions or Behavior ATC Develops reactivity plan using reactivity summary sheet CRS Uses POP-2.1 attachment for load reduction Note: If requested, notifications will be made for CRS by personnel outside the control CREW Hold reactivity ATC Performs Boration for load 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 When sufficient actions for shutdown are observed instruct booth to insert Event 5 2010 IP3 NRC Exam Scenario Page Sof 15 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: Event No.: Page _1_of .1. Event

Description:

SGTL becomes SGTR. PORVand Instrument Air to VC Valve failures will lead to loss of pressure control. Position CREW ATC BOP CRS ATC BOP CRS ATC ATC BOP Applicant's Actions or Behavior Diagnoses that SGTL has become SGTR:

Lowering PZR Level

Lowering PZR Pressure and possible Low Pressure Alarm

R-15 in Alarm May start a second charging pump May reduce letdown to 45 gpm Instruct Crew to:

Trip Reactor

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

Trip/bypass breakers open

Flux decreasing

Rod bottom lights lit

IRPls < 20 steps Verifies turbine trip:

May note that stop valves were previously closed

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

All powered from offsite power 2010 IP3 NRC Exam Scenario 3 Page 90f 15 Appendix 0 Required Operator Actions Form ES-D-2 ATC Verify SI:

SI will be actuated

SI buttons will be pressed CRS Enters E-O and re-performs first four Note: Actions will be continued on Event 6n D-2 2010 IP3 NRC Exam Scenario 3 Page 100f 15 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No. : Event No. : ..JJ!L Page _1_of .it. Event Description

33 AFW Pump and 31 SI Pump fail to auto-start Time Position ATC/BOP BOP CRS/ATC 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 Performs E-O actions: Verifies FW isolation Verifies SI flow Verifies Containment Spray not required Verifies RCP seal cooling Verifies RCS Temperature Checks if RCP trip criteria are met. 2010 IP3 NRC Exam Scenario Page 110f 15 Appendix D CRS/ATC CRS/ATC CRS/ATC CRS/ATC CRS/ATC CRS/ATC CREW CREW CREW CRS/ATC CRS/ATC CRS/ATC CRS/ATC CRS/ATC Required Operator Actions Form ES-D-2 Perform E-O diagnostic steps and determine that transition to E-3, Steam Generator Tube R Check if RCP tri criteria are met Ensure at least one PORV block valve 0 Reset SI if not al RO-1 Attempt to establish IA to VC if not already done per RO-1. PCV-1228 will not 0 Secure RHR Pu in auto Check RCP seal coolin o 'ust to maximum Check subcoolin

>60F 2010 IP3 NRC Exam Scenario 3 Page 120f 15 Appendix 0 CRS/ATC CRS/ATC CRS CRS/ATC CRS/ATC CRS/ATC v CRS/ATC ATC/BOP Lead Evaluator Required Operator Actionl! ____

Determine that normal spray is not available for depressurization Attempt to depressurize using PORV 456 Transition to ECA-3.3 Check 33 SG Level < 75% (should be < 75% at this pOint): Procedure will address attempting to establish spray, aux spray or PORV Check PZR Level is >14% Check subcooling

>40F Check >365 gpm AFW flow available for heat sink Check RVLlS >72% Secures SI Pumps and places in auto Terminate Scenario 2010 IP3 NRC Exam Scenario Page 130f 15 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 140f 15 Turnover Date/Time:

Condition:

Power % Power: Xenon:

RCS Boron: 1040 PZR Press Control: Channel PZR Level Control: Channel RCS Total Leakage: 0.1 RCS Unidentified Leakage: 0.01 Condenser Air leakage RCS Gas activity 1.78E-2 Risk Assessment: Plant Equipment Status: # 31 ABFP was declared inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago due to blowing its control power fuses. TIS is in progress.

Per TS 3.4.11, the block valve has been closed with power removed and a 7 day AOT entered. Instructions:

Maintain 100% power. 2010 IP3 NRC Exam Scenario Page 150f 15

@@ Line 2: / Line 2: @@
 | number = ML103080923
 | issue date = 08/13/2010
-| title = Indian Point, Unit 3 - Draft Operating Exam (Sections a, B, and C) (Folder 2)
+| title = Draft Operating Exam (Sections a, B, and C) (Folder 2)
 | author name =
 | author affiliation = NRC/RGN-I
@@ Line 14: / Line 14: @@
 | document type = License-Operator, Part 55 Examination Related Material
 | page count = 213
+| project = TAC:U01789
+| stage = Draft Other
 }}

v t e Letter Sequence Draft Other
TAC:U01789, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML103090017, ML103090020, ML103090036, ML103090054, ML103410223
MONTHYEAR2010-07-20 [Table View]

ML103080923: Difference between revisions

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