ML040120735

Draft - Outlines

ML040120735
Person / Time
Site:	Indian Point
Issue date:	12/08/2003
From:	Christman R Entergy Nuclear Northeast
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-286/03-303
Download: ML040120735 (26)

Text

ES-401 PWR -Examination Outline Form ES-401-32 11 Facilitv:

Date of Exam:

I.

1.

1 of 34 NUREG-I 021, Draft Revision 9

ES-401 E/APE#INameISafetyFunction Note: 1.

2.

3.

4.

5.

6.*

7.

h.

I.

K K K A 1

2 3

1 Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D.l.c for additional guidance regarding SRO sampling.

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by &I from that specified in the table based on NRC revisions. The finalRO exam must total 38875 points and the SRO-only exam must total 25 points.

Select topics from many systems and evolutions; avoid selecting more than t w o e

1. bee WA topics from a given system or evolution unless they relate to plant-specific priorities.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryltier.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IR) for the -applicable license level, and the point totals for each system and c a

t e

g 0

r y

k Enter thegroup and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K" and "A." Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

Refer to ES-401,, for guidance regarding the elimination of 000008 Pressurizer Vapor Space Accident I 3 inamrotxiate WA statemen x x lxI I I 000007 (BWIE028E10' CEIEO2) Reactor Trip - Stabilization - Re'covery I 1 Ixamination Outline Form ES-401-23 Evolutions - Tier 1IGrouo 1 fR0 I SROI WA Topic(s)

" I EK1 Knowled e of the operational implications ofthe following concepts as the apply to the reactor trip:

C8R 41.8 / 41.10 / 45.3) kK1.06 Relationship of emergency feedwater flow to S/G and decay heat removal following reactor trip AK2-Knowledge of the interrelations between Pzr Vapor Space Accident (CFR 41.7,45.7)

K2.02 Sensors and Detectors AK3-Knowledge of reasons for the following as they ap 1 to Pzr Va or Space Accidents (CFR 41.~d;.1,45.6,4~13)

K3.04 RCP Tripping Requirements 4.1 2.71 4.6 I

2

ES-401 I EA2 Abilitv to determine or interwet the following a's they apply to a small break LOCA:

CFR 43.5 / 45.13)

B A2.01 Actions to be taken. based on RCS temperature and pressure, saturated and superheated I

EA1 Ability to operate and monitor the following as the a ply to a Lar e Break L8CX CFk 41.7 / 45.5 / 45!6)

BAl.07 Containment isolation system I

I I APE : 015/017 Abilitv to oDerate and/or monitor the followini as t ~ e apply to Reactor Coolant Pump (RCJ)

Malfunctions KFR 41.7 45.5.45.6)

I I AA1.05 RCS flow AA1. Ability to o erate and l o r monitor the Loss of k a c t o r CooLnt Pump Makeup:

CFR 41.7 145.5 / 45.6)

!4A 1.09 RCP. sea!

flows, temperatures, pressures, and vibrations the followin as t E eyap ly to AK3 Knowledge of the reasons for the following res onses as the ap ly to a loss of RHR: (CFk 41.5,41.14l6,4g.13)

AK3.03 Immediate Actions contained in the EOPs for Loss of RHR AA2. Ability to determine and interpret the followin as they apply to the Loss of Eom onent Cooling Water:

-02 The cause of possible CCW loss (W&R 43.5 / 45.P3)

S 2.4.41 Knowledge of the emergency action level thresholds and classifications.

(CFR 43.5 / 45.1 1)

I EA1 Abilitv to oDerate and monitor the followin a's the appl to a reactor trip:

415 / 45.4 45.67 AI.OS Rx Tri~

Switch Pushbuttons.

EK1 Knowhdge of the operational implications of the following concepts as the a 1 to theATWS:

CjR !!{/

4 1.10 / 45.3)

BK1.03 Effects of boron on reactivity 3 of 34 4.8 4.4 3.8 3.3 4.1 3.6 4.1 4.51 3.8 NUREG-1021, Draft Revision 9 1

1 1

1 1

1 1

2

000038 Steam Gen. Tube Rupture 1 3 000040 (BW/EO5; CWEO5; W/E12 Steam Line Rupture - Excessive Jeat Transfer / 4 000054 (CEIEO6) Loss of Main Feedwater I4 000055 Station Blackout I6 000056 Loss of off-site Power I6 000057 Loss of Vital AC Inst. Bus I 6 000058 Loss of DC Power I6 000062 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air I 8 ES-401 EA2 Ability to determine or inter ret the following as they apply to a SGTI!

CFR43.5 /45.13 B A2.12 Status of L SIV activating system AK2. Knowledge of the interrelations between the Steam Line Rupture and the followin : (CFR 41.7 145.7)

AK2.02 5 ensors and detectors AA2. Ability to determine and interpret the following as they apply to the Loss of Main Feedwater 0:

CFR: 43.5 145.13)

L 2.03 Conditions and Reasons for AFW Pp Startul>

EA2 Ability to determine or interpret the followin as they a Station hackout: (&%f,o,?i

/45.13)

EA2.03 Action Necessary To Restore Power 2.4.8 Knowledge of how the event-based emergencylabnormal operatin procedures based EOPs.

(CFR 41.10 /43.5 /45.13) are used in conjunction with t f e symptom-2.2.2 Ability to manipulate the console controls as re uired to operate the facility levels.

(CFR 45.2) between shut 1 own and designated power AAl. Ability to o erate and I or monitor the followin as tEey apply to the Loss of d C Power:

CFR 41.7 145.5 145.6)

L 1.03 Vital and batterv bus comDonents AA2. Ability to determine and interpret the followin as they apply to the Loss of fiuclear Service Water:

C F R 43.5 145.13)

LA 2.02 The cause of Dossible SWS loss 2.1.22 Ability to determine Mode of 0 eration.

(&R: 43.5 /45.13)

WlE04 LOCA Outside Containment I 3 WIEI 1 Loss of Emergency Coolant Recirc. 14 BW/E04; W/E05 Inadequate Heat Trans-fer - Loss of Secondary Heat Sink / 4 WA Category Totals:

5 of 34 ES-401 room team as ap ropriate to the assigned position, in sucg a way that procedures are adhered to and the limitations 111 the facilities license and amendments are not violated.

EA2. Ability to determine and interpret the followin as they apply to and operation within the knitations 111 the facility*s license and amendments.

O8A Outside Containment)

A2.2 Adherence to ap ropriate procedures EK2. Knowledge of the interrelations between the (Loss of Emer ency Coolant Recirculation) an c f the following:

CFR 41.7 / 45.7) k K2.2 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

EK2. Knowledge of the interrelations between the (Inadequate Heat Transfer and the following:

&CFR 41.7 145.7)

K2.2. Facility*s heat removal systems, includmg primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Group Point Total: 25 3.81 4.2 4.3 4.2 NUREG-I 021, Draft Revision 9 2

1 1

ES-401 ES-401 Emeraencv I and EIAPE # I Name I Safety Function I p 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod I 1 000005 InoperableIStuck Control Rod I 1 000024 Emergency Boration I 1 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Range NI I7 000033 Loss of Intermediate Range NI I7 000036 (BWIAO8) Fuel Handling Accident I 8 000037 Steam Generator Tube Leak I 3 000051 Loss of Condenser Vacuum I 4 000059 Accidental Liquid RadWaste Rel. I9 000060 Accidental Gaseous Radwaste Rel. I 9 000061 ARM System Alarms I7 PWR WExaminatic Abnormal Plant Evolution!

000067 Plant Fire On-site I 4 8 I

000068 (BWIA06) Control Room Evac. I8 I

Outline Form ES-401-23 Tier 1IGroup 2 (RO I SRO)

WA Topic@)

IR AK3. Knowledge of the reasons for 41.5,41.10 / 45.6 / 45.13)

AK3.05 Tech Sgec Limit s For Load Reduction to 50 /o power if flux cannot be brought back withm the specified target band.

the following res onses as to the Dropped 8 ontrol 3.7 AA2. Ability to determine and interpret the following as they a ply to the Pressurizer Level Controf Malfunctions: (CFR: 43.5 145.13 power level or T-ave. including mterpretation of malhction AA2.02 PZR level as a function o r) 3.8 I

I AA2. Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum:

CFR: 43.5 145.13)

L 2.02 Conditions requiring reactor andor turbine t r i ~

4.1 AA2. Ability to determine and interpret the following as they apply to the Area Radiation Monitoring:

3.2 I

0 intensity for each ARM system channel

~~

000069 (WE14) Loss of CTMT Integrity I 5 000074 (WIE06&E07) Inad. Core Cooling I 4 000076 High Reactor Coolant Activity I 9 WIEOI & E02 Rediagnosis & SI Termination I 3 WIE13 Steam Generator Over-pressure 14 7 of 34 ES-401 AK1. Knowledge of the operational implications of the following concepts as they apply to Loss of Containment Inte rity:

CFR 41.8 / 41.107 45.3) kKl.01 Effect of pressure on leak rate EK2. Knowledge of the interrelations between the p i g h Containment Pressure an the following: (CFR 41.7 /) 45.7)

EK2.2 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facilitv.

EK1 Knowled e of 0 erational Implications of the foRowing conce ts as the a ply to Saturated Core gooling (E& 41.8,41.1*,45.3)

EKl.3 Annunciators and conditions indicatin signals and remedial actions EA2 Abh to determine and to de raded core cooling (CFL f!x 45.13j EA 2.2 Adherence to appropriate rocedures and operation within P imitations in the facilities license and amendments interpret t 2 e following as the a AK3. Knowledge of the reasons for the followin responses as the apply to the Hi h Weactor Coolant ictivity CFR 4f5,41.10 / 45.6 / 45.13) dk3.05 Corrective actions as a result of high fission product radioactivity level in the RCS EA1. Ability to operate and / or monitor the following as they apply to the (Reactor Trip or Safety In'ectiodRedia nosis (CkR: 41.7 / 45.8,45.4 EA1.3 Desired operating results during abnormal and emergency situations.

2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against YCFR 43.4 / f5.10) ersonnel ex osure.

3.11 3.8 3.6I 4.1 3.6 3.81 3.3 NUREG-I 021, Draft Revision 9 2

2 1

2

W/E15 Containment Flooding I 5 WIE16 High Containment Radiation I 9 X

BWlAOl Plant Run back I 1 BW/AO2&AO3 LOSS O f NNI-XN / 7 BWIAO4 Turbine Trip I 4 BWIA05 Emergency Diesel Actuation I 6 BWIAO7 Flooding I 8 BW/E03 Inadequate Subcooling Margin I 4 I

I BW/EO8; W/E03 LOCA Cooldown - Depress. I 4 BWIEO9; CE/A13; W/EOS&ElO Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CUAl I; WIE08 RCS Overcooling - PTS I 4 CUA16 Excess RCS Leakage I 2 CUE09 Functional Recovery WA Category Point Totals:

3 1

ES-401 ES-401 System # I Name I

System # I Name 003 Reactor Coolant Pump 003 Reactor Coolant Pump 1 PWRG Plant System ES-401 2.4.21 Knowledge of the arameters and logic used to assess tie status of safety "

functions includin :

1. Reactivitv contro 4

2. Core cookn and heat removal

4. Containment conditions

5. Radioactivi release control.

(CFR 43.5 / 4?. 12)

3. Reactor coo f ant system integrity 4.3 1

EK1. Knowledge of the operational implications of the following concepts as they apply to the (High Containment Radiation)

(CFR 41.8 /41.10,45.3)

EK1.2 Normal, abnormal and emergenc operatin procedures associateJwith (-I& containment Radiation).

3.2 1

I I

ri EA1. Ability to operate and I or 3.9 I

monitor the followin as they apply to the (Natural CircJation Cooldown) (CFR 41.7 145.5 145.6)

EA1.2 Operatin behavior 1

charactenstics of the facility.

4 2 9/5 I 9/5 Group Point Total: 14 I/

SExamination Outline Form ES-401-23 I

-Tier ZGroup 1 (RO I SRO)

A A

A G

WA Topic(s)

IR 2

3 4

I x

A3 Ability to monitor automatic 3.1 1

operation of the RCPS, including: (CFR 41.7 / 45.5)

A3.03 Seal D/P I

I

ES-401 1

1 3.11 3.9 2

2 K2 Knowledge of bus power su lies to tKe following:

C!k:

41.7) k2.02 Makeup pum s K3 Knowledge of t i e effecl loss or malfunction of the will have on the following:

ICFR 4 1.7/45/6)

that a cvcs k3.04 RCPS 3.41 2.7 A4 Ability to manually operate and/or monitor in the control room: CFR: 41.7 / 45.5 to 45.8)

A4.0 1 & ontrols and Indication for 2.2.5 Knowledge of the rocess as described in the safety analysis re ort.

(CFR 43.3 /45.1$

RHR munps for making changes in t K e facility 3.9 3.2 1

A3 Ability to monitor automatic operation of the ECCS including: (CFR: 41.7 145.5)

A3.01 Accumulators K1 Knowledge of the physical connections and/or cause effect relationshi s between the PRTS CFR: 41.2 to 415 745.7 to 45.8) k1.03 RCS and the fol P owin s stems:

I 3.3 2.71 3.5 K4 Knowled e of CCWS design whichprovide for the following:

(CFR 41.7)

K4.01 Automatic Start of Standby

-P K2 Knowledge of bus power su lies to the following:

(C& 41.7)

K2.02 Controller for PZR spray valve A3 Ability to monitor automatic operation of the PZR PCS, including: (CFR: 41.7 / 45.5)

A3.02 Pzr Pressure feature@) an % or interlock@)

2 2

3.71 3.2 K1 Knowledge of the physical connections and/or cause effect relationshiDs between the RPS and the follobin systems:

(CFR: 41.2 to 41.9 / 4f7 to 45.8)

K1.O1 120V vitaVinstrument power s stem feature(s) an or interlock(s) which rovide for the following:

(CFR 81.7)

K4.07 First-out indication 4 Knowled e of RPS design d7 2

NUREG-I 021, Draft Revision 9 9 of 34

ES-401 K5 Knowledge of the operational implications of the following conce ts as they ap ly to the ESFAS: CFR 41.f145.7) and ESF channel K5.01 De I mitions of safety train K2 Knowledge of power supplies to the following:

Y CFR 4 1.7) fcz.01 Containment cooling fans K4 Knowled e of CSS Desi Features an&,

Interlocks wEch rovide for the following:

P CFR 41.7)

K4.06 Iodine Scavenging via the CS System A2 Ability to (a CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the conseauences of those redict the im actsofthe rR o owing ma s functions or operations on the malfuictions or o erations:

CFR: 41.5 143.5 745.3 145.13)

L.08 Safe securing of containment spray %hen it can be done.

2.2.2 Ability to manipulate the console controls as required to operate the facility between sdutdown and degignated power levels. (CFR: 45.2) 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the ap ropriate control room (CFR: 41.10,43.5 145.12) re P erence material.

A3 Abilitv to monitor automatic o eratio; of the MFW, including:

(8FR: 41.7 145.5)

A3.04 Turbine driven feed DUD K3 Knowledge of the effect that a loss or malfunction of the AFW will have on the following:

(CFR 4 1.7 / 45.6)

K3.01 RCS A1 Ability to predict and/or monitor changes in parameters (to prevent exceedin design (CFR: 41.5 / 45.5) limits associated wit % o erating the A li W controls inclugng:

Al.01 S/G level 3.2 3.1 3 2 3.7 3.5 3.7 2.6 4.61 4.2 1

1 1

2

062 AC Electrical Distribution

~~

063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 11 of 34 ES-401 K1 Knowledge of the physical connections andlor cause effect relationships between the ac distribution svstem and the followin systkms:

(CFR: 4 f 2 to 41.9)

K1.02 ED/G A2 Ability to (a on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or o erations:

(CFR 41.5 /43.5 p45.3 145.13)

A2.05 Methods for energizing a dead bus redict the im actsofthe 2R o owing ma s functions or operations K2 Knowledge of bus power lies to the following:

Elk: 4 1.7)

AI Ability to predict and/or monitor chan es in parameters associated wit% operating the DC electrical system controls including: (CFR 41.3 / 45.5)

A1.O1 Battery capacity as it is affected by discharge rate

.01 Major DC loads K1 Knowledge of the physical connections and/or cause-effect relationshi s between the EDG x 1.O 1 AC Distribution System A2 Ability to (a maffunctions or o erations on the ED/G system; anJ(b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or o erations:

CFR 41.5 143.5 p45.3 /45.13) k2.02 Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temueratures s stem an B the following systems:

im actsofthe 2R o owing redict the K3 Knowledge of the effect that a loss or malfunction of the PRM system will have on the following:

(CFR: 41.7 / 45.6)

K3.O 1 Radioactive effluent releases 4.41 3.3 3.11 3.3 4.41 2.9 4.2 NUREG-1021, Draft Revision 9 2

2 1

ES-401 A1 Ability to predict and/or monitor changes in parameters (to prevent exceedin design the S iy S controls including:

(CFR: 41.5 145.5)

Al.02 Reactor and turbine building closed coollng water temperatures.

limits associated wit % operating A2 Ability to (a redict the IAS; and (b) base{ on those predictions, use procedures to correct, control, or mitigate the conseauences of those im actsofthe 2i o owing ma s functions or o eratrons on the malfunctions or o erations:

f F R 41.5 143.5 p45.3 145.13) 3.01 Air Dressure 2.1.2 Knodedge of operator responsibilities during all modes of lant o eration.

(CfR 4LvO 145.13) 2.4.46 Ability to verify that the alarms are consistent with the P CFR 43.5 145.3 145.12) lant conditions.

Group Point Total: 32 2814

ES-401 fi 11 ES-401 11 System # I Name 1

01 I Pressurizer Level Control 0 16 Non-nuclear Instrumentation 01 7 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control e e PWR GRBExa 13 of 34 Iutline Form (RO I SRO)

ES-401-24 WA Topic(s)

K5 Knowledge of the following OPS Im lications as a plied to CRDs Kt88 Effects ofioron on temDerature coefficient A4 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 145.5 to 45.8)

A4.01 RCS leakage calculation program using the computer A2 Ability to (a) redict the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions

(&F~:41.5143.5/45.3145.13) or o erations:

.02 Loss of power to the RPIS K6 Knowledge of the effect of a loss or malfunction on the followin will have on the NIS (CFR41.7,45.5 K6.01 Sensors, Detectors, and Indicators im actsofthefo R owing ma P functions or operations on the A2 Ability to (a ma7functions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions redict the im actsofthe $8 o owing or o erations:

(CFZ: 41.5 143.5 145.3 145.5)

A2.01 Thermocouple open and short circuits K5 Knowledge of the operational implications of the following concepts as they apply to the CIRS:

CFR 41.7 I 45.7 k 5.01 Purpose o f charcoal filters NUREG-I 021, Draft Revision 9

ES-401 A1 Ability to predict andlor

~ monitor chan es in parameters to

' prevent exceesing design limits) associated with operating the Containment Purge Svstem r t r o l s including CFR: 41.5 145.5) 1.03 Containment Dresswe.

temDerature. and hGiditv I

A2 Ability to (a mayfunctions or o erations on the GS; and (b) basezon those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or o erations:

fF& 41.5 I 43.5 f 45.3 145.5) 2.02 Reactor triplturbine trip redict the im actsofthe bR o owing S 2.2.17 Knowledge of the process for managing maintenance activities during ower o erations.

(CFR 45.5 145.p3)

K6 Knowledge of the effect of a loss or malfunction on the Fire Protection System followin will have on the : (CFR 41.7 145.7)

K6.04 Fire, smoke, and heat detectors 3.5 1

1

K/A Category Point Totals:

0 0 0 2 2 2 1 3 0 1 1

GroupPointTotal:12 1 on 15 of 34 I 01 2

NUREG-I 021, Draft Revision 9

WA #

2.1.11 2.1.14 2.1.29 2.1.24 2.1.

2.1.

Subtotal Date of Exam:

Topic 2.1.1 1 Knowledge of less than one hour technical specification action statements for systems.

(CFR 43.2 145.13) 2.1.14 Knowledge of system status criteria which require the notification of plant personnel.

(CFR 43.5 /45.12) 2.1.29 Knowledge of how to conduct and verify valve lineups (CFR 4 1.10/45.1145.12) 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR 45.12 145.13) 2.2.29 I 2.2.29 Knowledge of SRO fuel handling I responsibilities 2.2.21 2.2.2 1 Knowledge of pre-and post-maintenance operability requirements. (CFR: 43.2) 2.2.6 2.2.25 2.2.6 Knowledge of the process for making changes in procedures as described in the S A R 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. (CFR: 43.2)

I 2.2.

I 2.2.

I Subtotal I

2.3.6 2.3.4 2.3.1 1 2.3.6 Knowledge of the requirements for reviewing and approving release permits. (CFR: 43.4 / 45.10) 2.3.4 Knowledge of Radiation Exposure Limits and Contamination Control, including permissible levels in excess of those authorized 2.3.1 1 Ability to control radiation releases.

ES-401 ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-40 1-33 Facility:

Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control I (CFR: 45.9 / 45.10)

111 111 26 AK3.01 38 EK1.04 IP3 Does not Have CCW Auto Actions Reflux Boiling not Applicable During SGTR 111 111 000054AA2.07 000055EA2.05 Unable To develop an appropriate question for WA No Indication of DC Bus Voltage in IP3 Control Room ES-401 2.3.1 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

(CFR 41.12 I 43.4.45.9 I 45.10) excessive levels of radiation and guard against personnel exposure. (CFR 43.4 / 45.10) 3.0 1

2.3.10 Ability to perform procedures to reduce 3.3 1

2.3.10 2.3.

Subtotal 2.4.38 2.4.38 Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator.

(CFR: 43.5 145.1 1) 2.4.13 Knowledge of crew roles and responsibilities during EOP flowchart use. (CFR 4 1.10 I 45.12) 4.0

4.

Emergency Procedures I Plan 2.4.13 3.9 1

2.4.1 1 3.6 1

2.4.1 1 Knowledge of abnormal condition procedures. (CFR: 41.10 143.5 145.13) 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures.

(CFR: 41.101433 145.13) 2.4.16 4.0 1

2.4.

2.4 ES-40 1 Record of Rejected WAS Form e5-40 1-+W I

Randomly Selected 11 t::/~

I WA Reason for Rejection 111 40 2.1.4 212 11 K1.05 Steamline Rupture WA Does Not Match Generic Stmt.

IP3 Does Not Have a Reactor Regulating Svstem 13 K1.l IP3 Does Not Have CPS I

I 25 A4.02 IP3 Does Not Have an Ice Condenser I

I I( 212 I 722.4.26 I Fire Protection Generic Stmt Not Applicable to ARM System 17 of 34 NUREG-1021, Draft Revision 9

000003AK3.03 000076AK3.06 2/1 21 1 007K1.04 I

003A3.05 005A4.02 II 211 I 008K5.06 2/1 21 1 ES-401 006A3.08 026K2.02

. I IP3 No Longer Has An Auto Run back On A Dropped Rod

. I There are no EOP driven actions for High Reactor Coolant Activity Importance Value is Less Than 2.5 ImDortance Value is Less Than 2.5 21 1 I 062K4.10 026A2.05 2.2.3 1 2.3.9 4 2.2.18 t AC Electrical Distribution Sampled More Than Twice I

I No Automatic Actions For Lube Oil or Lift Pump on RCPs I

No Heat Exchanger Bypass Valve Exists On IP3

i I

I l IP3 has no Auto ECCS Transfers. such as Recirc SwaD Testing Too Many Power Supplies-Shifted To K5 Duplicate concept to K5.01-Loss of Spray Add Capability 1

No Procedures For Initial Core Loading

! I/

Oversampling of Containment Purge I/

1 No PORV Testing Affects PRT Pressure and Temp ll No significance for shutdown maintenance of the CAR system.

ES-401 ES-40 1 Sample Written Examination Form ES-40 1-65 34 of 34 NUREG-102 1, Draft Revision 9 Methodology Used to Generate IP3 NRC Examination Sample Plant NUREG 1021 Rev 9 -June 11.2003

1.

2.

3.

4.

5.

6.

Utilized IP3 Random Sample Generator (NUREG 102 1 Rev 8 Compliant) To Generate Baseline Sample Plan.

Rejected WAs Based on Feedback fkom IP3 (See Record of Rejected WAS)

Determined Which Selected WAS Left Were SRO Only per 10CFR55.43.

Randomly Added WAS and Randomly Deselected WAS to Get Point Totals Required by NUREG 102 1 Rev 9 Form ES 401-2.

Random SelectiodDeselection Achieved Using Poker Chips Numbered 1-50. For WA Groups With Greater Than 50 Statement Possibilities Excel Spreadsheet Random Number Generator Was Used, Once Final WA Safety FunctiodSystem and Categories Were Randomly Determined, WAS Left Without Specific Topical Statements Were Selected Using The Poker ChipExcel Method.

19 of 34 NUREG-1021, Draft Revision 9

ES-301

~

Administrative Topics Outline Form ES-301-1

~

Facility:

Indian Point 3 Date of Examination:

December 2003 Examination Level (circle one): RO / SRO Operating Test Number:

I Administrative Topic -

&mphm- (see Note)

+A-Conduct of Operations Conduct of Operations f e Equipment Control l

e Radiation Control k4 Emergency Plan Describe activity to be performed-JPM-Conduct an RCS Leakrate Surveillance (REPEAT from last exam) 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation (4.4)

JPM-Conduct a Valve Lineup Verification (New JPM) 2.1.29 Knowledge of how to conduct and verify a valve line up (3.3)

JPM-Actions for lowering Spent Fuel Pool level during refueling operations-transfer tube gate valve open (New JPM) 2.2.27 Knowledge of the refueling process (3.5)

JPM-Determine an Appropriate RWP and Take action for a high radiation alarm.

(REPEAT from last exam) 2.3.2 Knowledge of facility ALARA program (2.9)

JPM-General Emergency Classification Scenario with a PAR call (New JPM) 2.4.41 Knowledge of the Emergency Action Levels thresholds and classifications (4.1)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Form ES-301-2 ES-301 Control Roomlln-Plant Systems

'FestOutline Facility:

Indian Point 3 Exam Level (circle one): RO I SRO(I) I SRO(U)

Date of Examination:

December 2003 Operating Test No.: -l-11 BrSControl Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title I1 a.Sys- 004 Emergency Borate the RCS per ONOP-CVCS-003 K/A 004A4.18-Ability To Manually Operate and/or Monitor In The Control Room The Emergency Borate Valves (4.1)

b. SYS- 006 Initiate Feed and Bleed of the RCS WA EPEOSEAI.I Ability To Operate and/or Monitor The Following As They Apply To Loss Of Secondary Heat Sink-Components and Functions of Control and Safety Systems Including Instrumentation, Signals, Interlocks, Failure Modes, and Auto and Man Features (4.0) 104A

c. sys- 010 Use the Pressurizer PORVs to Depressurize the RCS K/A EPE038EA2.15 Ability To Determine or Interpret The Following As They Apply To A SGTR-Pressure At Which To Maintain The RCS During SIG Cooldown (4.4) 99A

d. SYS- 003 Start an RCP per SOP-RCS-01 (REPEAT from last exam)

K/A 003A4.06 Ability To Manually Operate and/or Monitor in the Control Room-RCP Parameters (2.9)

e. Sys- 026 Initiate Containment Spray (New)

WA 026A4.01 Ability To Manually Operate andlor Monitor In The Control Room-CSS Controls (4.3)

Type Code*

D,S,A,EOP D S D,SS N,S,A,EOP Safety Function 1

2 3

4 5

f. SYS- 062 Transfer 6.9KV Buses I through 4 to the Auxiliary Transformer WA 062A4.01 Ability To Manually Operate andlor Monitor In The Control Room All Breakers (Including Available Switch yard) (3.1)

9. SYS- 01 5 Remove an Intermediate Range Nuclear Instrument Channel Form Service WA 015A4.02 Ability To Manually Operate and/or Monitor In The Control Room - NIS Indicators (3.9) 6 7

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) ai. Sys- 041 WA APE 068AA1.01 Ability To Manually Operate The Following As They Apply To Control Room Evacuation-S/G Atmospheric Relief Valves (4.5)

Local Operation of the Atmospheric Steam Dump Valves bj.Sys- 008 Align City Water to 31 RHR Pump WA APEO26AA1.03 Ability To Operate and/or Monitor The Following As They Apply to the Loss of CCW-Backup to the CCW System (3.6) 04 ek. SYS- 068 Terminate a Waste Gas Decay Tank Release (New)

WA 071A4.27 Ability To Manually Operate and/or Monitor In The Control Room-Opening and Closing Decay Tank Discharge Control Valves (2.7)

D,A,EOP D,R 4

8 9

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, ll (Llow-Power. (RlCA

Amendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.: I Op-Test No.:

1 Examiners:

Alan Blamev Operators:

Joe DAntonio John Caruso Initial Conditions: Plant is at 50% Power, MOL, 31 ABFP is Stop Taaaed For Troubleshootina a Ground.

Turnover:

POP 3.1 to take the unit off-line to investigate a high Main Turbine Vibration. Turbine bearinas 2.3.4 are in the ALERT ranae and slowlv degrading. The orders for the shift are to continue the Shutdown. 31 ABFP is stop taaqed and is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> into its LCO Plant is at 50% Power, MOL, A plant shutdown is in progress in accordance with Event Description Continue Plant Power Reduction per POP-3.1 (MBFP S/D)

Controlling Pressurizer Level Channel Fails High (AOP) 32 Turbine Control Valve Closure (AOP)

Rapid Load Reduction Due To 32 Turbine Control Valve Closure Turbine Trip/ Failure of Auto Reactor Trip (ATWS)

Steam Generator Tube RuDture On 32 S/G 32 MSlV Fails To Close 34 Steam Generator Develops a Fault 1 of41 NUREG-1021, Draft Revision 9

Amendix D Scenario Outline Form ES-D-1 Event Type*

N I

(CRSR0.1 C

AAELKQBPO (CRS RO Ern)

C (CRS.RO.BP0)

C (CRS.RO)

C(CRS.RO1 M ( C R S R O B m 1 Facility: Indian Point 3 Scenario No.:

2 Op-Test No.:

1 Examiners:

Alan Blamev Operators:

Joe DAntonio John Caruso Event Description Continue Startup-Raise Power To 15%

Controlling Pressurizer Pressure Channel Fails High (AOP)

Loss of Condenser Vacuum (AOP)

LOSS Of 5A-480 Volt BUS (AOP) 34 RCP High Vibration (AOP) 34 RCP Seal Leak and Failure Small Break LOCA Turnover:

Plant is at 5% Power, MOL, Raise Power To 15% In Preparation For Rollinq The 11 Main 8

I Turbine I C (cRs.Bw) 31 HHSl Pp Fails To Start 7

1 1 of41 NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Event Type*

IBRS.RO.804 C (CRS.RO1 C(CRS.RO, R,C(CRS.RO.

C(CRS.RO1 M(cRs.Ro.mq 800 11 Facility: Indian Point 3 Scenario No.:

3 Event Description T hot Channel Fails High (AOP)

Loss of the Operating Charging Pump (AOP) 1 Dropped Control Rod (AOP)

Turbine Trip P-8 (No Reactor Trip Expected) (AOP)

Multiple Dropped Control Rods, Reactor Trip Loss of All Feed, Failure of 31 ABFP Op-Test No.:

1 Examiners:

Alan Blamey Operators:

Joe DAntonio John Caruso Initial Conditions: Unit 3 is at 30% Power with a Shut Down in prowess to meet the requirements of the A M Svstem LCO. 31 MBFP has a failed SDeed Control Channel. 32 ABFP is Stowed Taqaed due to a damaaed trb throttle valve.

Turnover:

Unit 3 is at 30% Power with with a Shut Down in Droaress to meet the requirements of the AFW Svstem LCO. 31 MBFP has a failed Speed Control Channel. 32 ABFP is StopDed Tawed due to a damaaed trip throttle valve. Orders for the shift are to continue with the Dlant shutdown in a controlled manner, ensure plant is in mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

1 of41 NUREG-I 021, Draft Revision 9

Amendix D Scenario Outline Form ES-D-1 Event No.

Facility: Indian Point 3 Scenario No.:

4 Malf.

Event Event No.

Type*

Description Op-Test No.:

1 Examiners:

Alan Blamev Operators:

Joe D'Antonio John Caruso Initial Conditions: Unit 3 is at 100% Power. 31 RHR Pump is stop tanned out of service so that the motor can be meanered.

Turnover:

motor can be menaered. RCS Leak Rate is sliahtlv elevated over the last several watches, Operations Management has been informed, and trendinn of dailv leak rate analvsis is Unit 3 is at 100% Power. 31 RHR Pump is stop taaaed out of service so that the C,R Heater Drain Pump Trip (AOP)

ICRS.RO.BOP) 1 2

I(CRS..Bm.RO) 1" Stage Turbine Pressure Channel Fails Low (PT-412A)

(AOP) 4 MiCRS.Bm.RO)

Large Break LOCA 5

I(CRS.RO)

Failure of Auto Safety Injection 6

M(cRs.Ro.Bm) Trip of 32 RHR Pump, Failure of Emergency Coolant Recirculation Capability 1 of41 NUREG-1021, Draft Revision 9