Text

Final Outlines (Folder 3)
	ML070310117
Person / Time
Site:	Indian Point
Issue date:	11/01/2006
From:	; Division of Reactor Safety I
To:	; Entergy Nuclear Operations
	Sykes, Marvin D.
References
	Download: ML070310117 (33)
	v • d • e

Indian Point 3 Written Exam Question Replacement As a result of questions raised by the licensee pertaining to the development of the examination, the NRC initiated an investigation to determine the existence of an exam compromise. No evidence was found to support an exam compromise. However, due to the lack of licensee documentation of training that was conducted just prior to the exam, compromise could not be completely ruled out. Therefore, in order to ensure the discriminatory value of the exam, twenty five questions were removed from the exam to be replaced with questions based upon new WA's that were selected by the NRC.

The following 25 questions (20 RO and 5 SRO) were removed from the licensee's original submittal:

7, 10, 13, 14, 20, 23, 30, 31, 33, 41, 46,47,49, 52, 55, 60, 67, 71, 73, 74, 78, 82, 83, 96, 100 These questions were replaced with questions based upon the following WAS:

RO (Common) Questions Tier 1 / Grour, 1 000025 AA 2.06 000057 G 2.1.30 000058 AK 3.02 000062 AA 2.06 Tier 1 /Group 2 000061 AA2.06 W/E 16 EA 1.1 SRO Only Questions Tier 1 / Group 1 000062 G 2.4.6 Tier 2 / Group 1 006 A 3.07 007 G 2.4.31 010 A 4.02 061 K3.01 073 K 3.01 076 A 4.02 103 A 2.04 Tier 1 / Group 2 000028 EA 2.03 W/E 10 EA 2.01 Tier 2 / Grow 2 068 K 5.04 071 A3.03 086 K 4.04 Generics G 2.2.23 G 2.3.4 G 2.4.16 G 2.4.48 Generics G 2.2.28 G 2.4.26

ES-40 1 PWR RO Examination Outline Form ES-401-2 10 G2.1 G2.2 G2.3 G2.4 2

3 2

3

3. Generic Knowledge and Abilities late: I.

2.

3.

4.

5.

6.

7.

Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO outlines (i.e. except for one category in Tier 3 of the SRO-only outline, the Tier totals in each WA category shall not be less than two).

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 final RO exam must total 75 points and the SRO-only exam must total 25 points.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site -specific systems that are not included on the outline should be added. Refer to ES-401,, for guidance regarding the elimination of inappropriate K/A statements.

Select topics from many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

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.

IP 3 - RO Outline Rev 0 Page 1 of 13 NUREG-1021, Revision 9

ES-401 PWR RO Examination Outline Form ES-401-2

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G*

on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group (Note #I does not apply). Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the WA numbers, descriptions, IRs, and point totals on form ES-401-3.

Limit SRO selections to WAS that are linked to 10 CFR 55.43.

9.

IP 3 - RO Outline Rev 0 Page 2 of 13 NUREG-1021, Revision 9

ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (RO)

Form ES-401-2 ElAPE # I Name I Safety Function II IK1 /K2 lK3 IA1 I N I Number KIA Topic(s) 000007 (BWIEO2 & E l 0; CEIEO2) I Reactor Trip -

R EA1.04 Ability to operate and monitor RCP operation and flow rates as 3.6 1

Stabilization - Recoverv I 1 thev amlv to a reactor trio 000008 I Pressurizer Vapor Space Accident I 3 R

000009 I Small Break LOCA I 3 R

AA2.20 EK2.03 Ability to determine and interpret the effect of an open PORV on Knowledge of the interrelations between the small break LOCA 3.4 2

code safety, based on observation of plant parameters as they apply to the Pressurizer Vapor Space Accident and the SGs 3.0 3

00001 1 I Large Break LOCA I 3 R

00001 5/17 RCP Malfunctions I 4 EA2.14

.t..;.

Ability to determine or interpret the actions to be taken if limits for PTS are violated as they apply to the Large Break LOCA comoonents and controls 3.6 8

3.2 4

Knowledge of the purpose and function of major system

!/ 000022/LossofReactorCoolantMakeu~I2 I

I I

I Not Selected I

I 000025 I Loss of RHR System 14 000026 I Loss of Component Cooling Water I 8 R

R Ability to determine and interpret the existence of proper RHR overpressure protection as it applies to the Loss of RHR System The ability to determine and interpret the location of a leak in the CCWS as they apply to the Loss of Component Cooling Water 000027 I Pressurizer Pressure Control System R

AK2.03 Malfunction I 3 000029 I Anticipated Transient w/o Scram I 1 EKI.01 R

Knowledge of the interrelations between the Pressurizer 2.6 5

Pressure Control Malfunction and controllers and positioners Knowledge of the operational implications of reactor nucleonics 2.8 6

and thermo-hvdraulics behavior as thev amlv to the ATWS 000038 I Steam Generator Tube Rupture I 3 R

000040 (BWIE05; CEIEO5; WIE12) I Steam Line RuDture - Excessive Heat Transfer 14 EA1.16 I--

Ability to operate and monitor SG atmospheric relief valve and 4.4 75 secondary PORV controllers and indicators as they apply to a SGTR Not Selected 000054 (CEIEO6) I Loss of Main Feedwater I 4 R

AKI.01 000055 I Station Blackout I 6 Knowledge of the operational implications of the MFW line 4.1 9

break depressurizes the SG (similar to a steam line break) as they apply to the Loss of Main Feedwater Not Selected 000056 / Loss of Off-site Power I 6 l R I I I 1 - 1 IAK1.O1 000057 I Loss of Vital AC Elec. Inst. Bus I 6 R

G2.1.30 000058 1 Loss of DC Power 16 R

AK3.02 NUREG-1021, Revision 9 Page 3 of 13 Knowledgeof the operational implications of the principles of cooling by natural convection as they apply to Loss of Offsite Power Ability to locate and operate components, including local control of dc power as it applies to the Loss of DC power Knowledge of the reasons for actions contained in EOP for loss 3.4

ES-401 I.

I UAPE # I Name I Safety Function K1 K2 K3 AI A2 G

Number KIA Topic(s)

Imp.

Q#

RO INDIAN POINT UNIT 3 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier I/Group 1 (RO)

Form ES-401-2 000062 / Loss of Nuclear Service Water / 4 000065 / Loss of Instrument Air / 8 W/E04 / LOCA Outside Containment / 3 WIEI I I Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 / Inadequate Heat Transfer -

Loss of Secondary Heat Sink 14 I

I KIA Catenow Point Totals:

1 3 1 2 R

1 3

R AA2.06 Ability to determine and interpret the length of time after the loss 2.8 14 of SWS flow to a component before that component may be damaged as it applies to the Loss of Nuclear Service Water Not Selected characteristics of the facility as they apply to a LOCA Outside Containment selection of appropriate procedures during abnormal and emergency operations as it applies to the Loss of emergency Coolant Recirs EA1.2 Ability to operate and I or monitor operating behavior 3.6 15 EA2.1 Ability to determine and interpret the facility conditions and 3.4 16 R

G2.4.20 Knowledge of operational implications of EOP warnings, 3.3 17 cautions and notes I

I I

I 3 1 I Group Point Total:

NUREG-1 021, Revision 9 Page 4 of 13

INDIAN POINT UNIT 3 EIAPE # I Name I Safety Function ES-401 K1 K2 K3 AI A2 G

Number KIA Topic(s)

Imp.

Q#

PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 (RO)

Form ES-401-2 000001 / Continuous Rod Withdrawal / 1 R

AKI.06 000003 I Dropped Control Rod I 1 00005 Inoperable/Stuck Control Rod / 1 000024 Emeruencv Boration / 1 000028 I Pressurizer Level Malfunction / 2 I

I I

I I I

I AK2.02 000032 / Loss of Source Range NI I 7 000033 / Loss of Intermediate Range NI I 7 000036 (BW/AO8) I Fuel Handling Accident / 8 000037 / Steam Generator Tube Leak / 3 R

AA2.12 000051 I Loss of Condenser Vacuum / 4 R

G2.2.12 000059 /Accidental Liauid Radwaste Rel. / 9 000061 I ARM System Alarms / 7 R

AA2.06 000067 I Plant Fire On-site I 9 000068 (BW/AO6) I Control Room Evac. I 8 000069 (W/E14)/ Loss of CTMT Integrity I 5 R

AK3.01 I

I 1

1 1

000074 (WIE06 & E07) I Inad. Core Coolinu I 4 I

1 1

000076 / High Reactor Coolant Activity / 9 I

I I

I WEIOI & 02 / Rediagnosis & SI Termination / 3 W/E13 / Steam Generator Over-pressure / 4 WIE15 I Containment Floodina / 5 WIE16 I High Containment Radiation I 9 I I I I I I I EA1.l BWIAOI / Plant Runback I 1 BW/A02 & A03 / LOSS Of NNI-WY I 7 BW/A04 /Turbine Trip / 4 I

I I

BW/AO5 / Emergency Diesel Actuation / 6 I

I 1

1 1

1 NUREG-1021, Revision 9 Page 5 of 13

INDIAN POINT UNIT 3 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)

ES-401 PWR Examination Outline Form ES-401-2 EIAPE # I Name I Safety Function Ki K2 K3 AI A2 G

Number WA Topic(s)

Imp.

Q#

BWIAO7 / Flooding / 8 1 BW/E08; W/E03/LOCACooldownIDepress./4 I I

I 1

I I

I I Not Selected I

I I

1 I Not Selected I

BW/E03 / Inadequate Subcoolinn Marain / 4 I

I I Not Selected I

BWIEO9; CE/AI 3; W/E09 & 10 Natural Circ./ 4 BW/EI3 & E14 / EOP Rules and Enclosures CE/AI 1; W/E08 I RCS Overcooling - PTS I 4 NUREG-1021, Revision 9 Not Selected Not Selected orocedures during all modes of Dlant ooeration R

G2.1.23 Ability to perform specific system and integrated plant 3.9 26 Page 6 of 13 CE/AI 6 / Excess RCS Leakage / 2 CE/EO9 I Functional Recovery Not Selected Not Selected WA Category Point Totals:

1 1 1

1 1 2 1 2 1 2 1 I Group Point Total:

9

INDIAN POINT UNIT 3 Plant Systems - Tier 2IGroup 1 (RO)

Form ES-401-2 ES-401 PWR Examination Outline Imp.

System # I Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

Number WA Topic(s)

Q#

NUREG-1021, Revision 9 Page 7 of 13 R

A4.07 Ability to manually operate and I or monitor 2.6 R

K6.04 Knowledge of the effects of a loss or 2.8 303 Reactor Coolant Pump 303 Reactor Coolant Pump in the control room RCP seal bypass malfunction on the containment isolation valves affecting RCP operation will have on the RCPs interlock which provide for oxygen control of the RCS dilution and boration considerations ECCS, including RHR pumps indications, and use of the response instructions or cause-effect relationship between the CCWS and the RCS, in order to determine sources(s) of RCS leakage into the CCWS the control room PZR Heaters parameters exceeding design limit associated with operating the RPS controls including trip setpoint adjustments parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including T-hot.

malfunction of the ESFAS will have on the containment containment cooling fans Not Selected malfunction of the CSS will have on the CCS 304 Chemical and Volume Control R

K4.01 Knowledge of CVCS design feature and I or 2.8 005 Residual Heat Removal R

K5.09 Knowledge of the operational implications of 3.2 006 Emergency Core Cooling R

A3.07 Ability to monitor automatic operation of the 3.6 007 Pressurizer ReliefIQuench Tank R

G2.4.31 Knowledge of annunciators alarms and 3.3 008 Component Cooling Water R

K1.04 Knowledge of the physical connections and I 3.3 01 0 Pressurizer Pressure Control R

A4.02 Ability to manually operate and/or monitor in 3.6 01 2 Reactor Protection R

A I.01 Ability to predict and I or monitor changes in 2.9 01 3 Engineered Safety Features Actuation R

A I.09 Ability to predict and I or monitor changes in 3.4 01 3 Engineered Safety Features Actuation R

K3.03 Knowledge of the effects that a loss or 4.3 022 Containment Cooling R

K2.01 Knowledge of power supplies to the 3.0 025 Ice Condenser 026 Containment Spray R

K3.01 Knowledge of the effect that a loss or 3.9 27 38 28 29 30 31 32 33 34 35 42 36 37

WA Topic(s)

Imp.

System # I Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

Number NUREG-1021, Revision 9 Q#

Page 8 of 13

m d

4 v!

m a

System # / Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

Number WA Topic(s)

Imp.

Q#

K5.04 Not Selected Knowledge of the operational implication of the 3.2 52 biological hazards of radiation and the resulting goal of AURA as they apply to the Liquid Radwaste System PWR RO Examination Outline Plant Systems - Tier 2/Group 2 Form ES-401-2 ES-401 001 Control Rod Drive 002 Reactor Coolant Not Selected of the RCP on the RCS R

K6.02 Knowledge of the effect or a loss or malfunction 3.6 I 01 I Pressurizer Level Control I

I I

I Not Selected I

I I

Knowledge of the physical connections and I or cause effect relationships between the I I I K1.O1 I RPlS and the CRDS 014 Rod Position Indication 015 Nuclear Instrumentation K5.02 Knowledge of the operational implications of 2.7 58 discriminator/cornpensation operation concepts as they apply to the NIS Not Selected Not Selected Not Selected 016 Non-nuclear Instrumentation 01 7 In-Core Temperature Monitor 027 Containment Iodine Removal R

A2.03 Malfunctions or operations on the HRPS; and based on those predictions use procedures to correct, control or mitigate the consequences of the hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment 3.4 59 I

I I

I I Not Selected I

I I

033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator Not Selected Not Selected Not Selected 1 041 Steam Dump/Turbine Bypass Control I

~

I I

I 1

r-i T I I

I I G c t e d

-1 I

I I

rt t Ability to predict and /or monitor changes in parameters associated with operating the MT/G system controls including expected response of secondary plant parameters following T/G trip 3.3 61 045 Main Turbine Generator A I.06 K3.01

~~

Knowledge of the effects that a loss or malfunction of the CARS will have on the main condenser w

Condensate Liquid Radwaste 068 Page 10 of 13 NUREG-I 021, Revision 9

INDIAN POINT UNIT 3 PWR RO Examination Outline Plant Systems - Tier 2/Group 2 Form ES-401-2 ES-40 1 System # I Name I Imp. I Q#

K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

Number K/A Topic(s) 071 Waste Gas Disposal 1

0 1

072 Area Radiation Monitoring 1

1 1

075 Circulatino Water R

R 079 Station Air 086 Fire Protection A3.03 Ability to monitor automatic operation of the 3.6 55 Waste Gas Disposal System including radiation monitoring system alarm and actuating signals ARM system including changes in ventilation alignment A3.01 Ability to monitor automatic operation of the 63 K/A Category Point Totals:

K4.04 NUREG-I 021, Revision 9 Knowledge of design features(s) and /or 3.1 60 interlocks(s) which provide for personnel safety 2 t

~

~~

0 0

Group Point Total:

10 I

I I

I Not Selected I

I t

I Not Selected I

I Page 11 of 13

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

Form ES-401-3

~

Category Conduct of Operations ll 11 Facilitv:

Indian Point Unit 3 Date of Exam:

10/23/06 Exam Level: RO KIA #

Topic Imp.

Q#

G2.1.1 Knowledge of conduct of operations 3.7 64 G2.1.32 Ability to explain and apply all system limits and 3.4 65 2

requirements precautions Total G2.3.10 Equipment Control Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exDosure G2.2.1 G2.2.23 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could effect reactivity Ability to track limiting conditions for operations G2.2.28 Knowledge of new and spent fuel movement 1 Drocedures Total 2.6 G2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized 2

Total Radiation Control Emergency Procedures /

Plan Tier 3 Point Total RO I

10 G2.4.18 I Knowledae of the sDecific bases for EOPs G2.4.48 1 Ability to interpret control room indicationso G2.416 verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions Knowledge of EOP implementation hierarchy and coordination with other s u ~ ~ o r t Drocedures Total 1

3 NUREG-1021, Revision 9 Page 12 of 13

ES-401 Record of Reiected WAS Form ES-40 1 -4 Tier / Group 1

Randomly Selected WA I Reason for Rejection 1 /I I 000026AA2.06 1 Test same area as Tier 2 Group 1 - 003K6.04 - Replaced with 000026AA2.01 2/2 000014K1.02 Previously approved (2) question rejected by NRC, unable to write any other question to meet knowledge - Replaced with 000014K1.01 20 questions randomly replaced by the NRC with new N/As picked by the NRC NUREG-1021, Revision 9 Page 13 of 13

ES-40 1

PWR Examination Outline Form ES-401-2 Facility:

Indian Point 3 Date of Exam:

I 1/17/2006 Exam Level:

SRO Abnormal Plant 7

G2.1 G2.2 G3.3 G4.4 2

2 1

2

3. Generic Knowledge and Abilities Note:

1.

2.

3.

4.

5.

6.

7.*

8.

9.

Ensure that at least two topics from every K/A category are sampled within each tier of the RO and SRO outlines (i.e. except for one category in Tier 3 of the SRO-only outline, the Tier totals in each WA category shall not be less than two).

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 f 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site -specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

Select topics from many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

The generic (G) K/As in tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.

On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group (Note #I does not apply). Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the K/A catalog, and enter the KIA numbers, descriptions, IRs, and point totals on form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

I NUREG-1 021, Revision 9 Page 1 of 10

ElAPE # I Name I Safety Function K I K2 K3 A I A2 G

Number KIA Topic(s)

Imp.

Q#

SRO ES-40 1 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (SRO) 000007 (BW/E02 & E10; CE/EO2) I Reactor Trip -

Stabilization - Recovery / 1 000008 I Pressurizer Vaoor Soace Accident I 3 000009 / Small Break LOCA I 3 I

I I

I 00001 1 / Large Break LOCA / 3 000015/17 RCP Malfunctions I 4 000022 / Loss of Reactor Coolant Makeuo I 2 I

I I

I 000025 / Loss of RHR System I 4 76 S

S S

S AA2.07 Ability to determine and interpret pump cavitation as it applies to the 3.7 Loss of Residual Heat Removal System.

000026 / Loss of Component Cooling Water I 8 000027 / Pressurizer Pressure Control System Malfunction / 3 I

I I

000029 I Anticipated Transient wlo Scram / 1 I

I I

000038 / Steam Generator Tube Rupture I 3 000040 (BW/EO5; CE/E05; W/E12) I Steam Line Rupture - Excessive Heat Transfer I 4 EA2.1 Ability to determine and interpret the facility conditions and selection of appropriate procedures during abnormal and emergency operations as they apply to the Uncontrolled Depressurization of all Steam Generators 4.0 77 000054 (CE/EO6) I Loss of Main Feedwater / 4 000055 I Station Blackout / 6 000056 I Loss of Off-site Power I 6 79 000057 / Loss of Vital AC Elec. Inst. Bus I 6 000058 / Loss of DC Power I 6 AA2.19 Ability to determine and interpret plant automatic actions that will occur on a loss of a vital ac electrical instrument bus as it applies to the loss of a vital AC Instrument Bus G2.1.33 Ability to recognize indications for system operating 3.4 parameters which are entry-level conditions for technical specifications 4.3 80 000062 / Loss of Nuclear Service Water 14 000065 I Loss of Instrument Air I 8 WE04 / LOCA Outside Containment I 3 G2.4.6 Knowledge of system based EOP mitigation strategies 4.0 78 W/EI 1 / Loss of Emergency Coolant Recirc. / 4 I

I I

BW/E04; WlE05 I Inadequate Heat Transfer -

Loss of Secondary Heat Sink / 4 K/A Cateaorv Point Totals:

EA2.1 Ability to determine and interpret facility conditions and selection 4.4 81 of appropriate procedures during abnormal and emergency operations as they apply to the Loss of Secondary Heat sink Grouo Point Total:

6 NUREG-I 021, Revision 9 Page 2 of 10

ES-40 1 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (SRO)

II ElAPE # I Name I Safety Function I K1 I K2 I K3 I AI I A2 I G I Number 1 KIA Topicb)

I Imp.

I Q#

II 000001 / Continuous Rod Withdrawal / 1 I

I I

I 000003 / Droooed Control Rod / 1 I

I I

I I 00005 Inoperable/Stuck Control Rod / 1 I

I I

I 1 000024 Emergency Boration / 1 000028 / Pressurizer Level Malfunction / 2 S

AA2.03 Ability to determine and interpret charging subsystem flow 3.3 82 indicator and controller as they apply to the Pressurizer Level Control Malfunctions 000032 I Loss of Source Range NI I 7 000033 / Loss of Intermediate Range NI / 7 000036 (BW/AO8) / Fuel Handling Accident / 8 000037 / Steam Generator Tube Leak / 3 11 000051 I Loss of Condenser Vacuum I 4 I

I I

I 000059 /Accidental Liquid Radwaste Rel. / 9 000060 / Accidental Gaseous Radwaste Rel. I 9 000061 /ARM System Alarms / 7 000067 / Plant Fire On-site / 9 1 WE/OI & 02 / Rediaanosis & SI Termination / 3 I

I I

1 W/E13 /Steam Generator Over-pressure/4 I

I I

I W/E15 / Containment Flooding I 5 S

G2.1.7 Ability to evaluate plant performance and make operational 4.4 85 judgments based on operating characteristics, reactor behavior and instrument interpretation W/E16 / Hiah Containment Radiation / 9 I BW/AOI I Plant Runback / 1 I

I I

I

' BW/AO2 & A03 / Loss of NNI-WY 17 BW/A04 /Turbine Trip / 4 BW/AO5 / Emergency Diesel Actuation I 6 BWlAO7 / Flooding / 8 1 BW/E03 / lnadecluate Subcoolinq Marqin / 4 I

I I

NUREG-1021, Revision 9

~

Page 3 of 10

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (SRO)

I-I ElAPE # I Name I Safety Function K1 K2 K3 AI A2 G

Number KIA Topic@)

Imp.

Q#

CEIEOS I Functional Recovery WA Category Point Totals:

I 2

2 Group Point Total:

4 NUREG-1021, Revision 9 Page 4 of 10

System # / Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G Number K/A Topic(s)

Imp.

Q#

ES-40 1 PWR Examination Outline Form ES-40 1 -2 Plant Systems - Tier 2/Group 1 (SRO)

I I

I 1

1 I

~~~

003 Reactor Coolant Pump I

I I

I A2.32 Ability to predict the impacts of expected reactivity changes after valving in a new mixed=bed demineralizer that has not been preborated and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank I

I I

1 I

I I

I 008 Component Cooling Water 01 0 Pressurizer Pressure Control G2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits 012 Reactor Protection 01 3 Engineered Safety Features Actuation I

I I

025 Ice Condenser 059 Main Feedwater S

A2.07 Ability to predict the impacts of a trip of MFVV pump turbine on the MFVV and based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations S G2.1.I2 Ability to apply technical specifications for a system 061 Auxiliary / Emergency Feedwater 062 AC Electrical Distribution I

I I

063 DC Electrical Distribution I

I I

064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water NUREG-1021, Revision 9 I

I I

S A2.01 Ability to predict the impacts of loss of SWS and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations I I H I I I

I I

I Page 5 of 10

System # I Name NUREG-1021, Revision 9 K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

Number KIA Topic(s)

Imp.

Q#

Page 6 of 10 KIA Category Point Totals:

I 3

2 Group Point Total:

5

/I ES-401 PWR Examination Outline Plant Systems - Tier 2/Group 2 (SRO)

Form ES-401-2 I

I I Imp. I Q#

System # I Name I K1 I K2 I K3 I K4 I K5 I K6 I A I I A2 I A3 I A4 I G I Number I KIA Topic(s) 002 Reactor Coolant I 015 Nuclear Instrumentation I

l l

I 016 Non-nuclear Instrumentation I

l l

017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 1 029 Containment Purge I

l l

033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator I

! 041 Steam DurnoRurbine Bvaass Control I

I I

045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste l

1 071 Waste Gas Disposal I

l l

1 072 Area Radiation Monitoring I

l l

NUREG-1021, Revision 9

System # I Name K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

Number WA Topic(s)

NUREG-1021, Revision 9 Imp.

Q#

Page 8 of 10 WA Category Point Totals:

1 2

I Group Point Total:

3

ES-40 1 Generic Knowledae and Abilities Outline (Tier 3) (SRO) Form ES-401-3 Radiation Control Facility: Indian Point Unit 3 Date of Exam:

10/23/06 SRO 2.3.6 Knowledge of the requirements for reviewing and 3.1 98 Total 1

approving release permits Category I K/A#

2.4.41 2.4.26 2.1.I 1

Operations 2.1.33 Conduct of t Total Knowledge of emergency action level thresholds and classifications including fire brigade and portable fire fighting equipment usage 4.1 3.3 Knowledge of facility protection requirements Topic I Imp.

Knowledge of less than one hour technical specifications for a system Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications Q#

94 95 2

2.2.28 t 2.2.24 Equipment Control Knowledge of new and spent fuel movement procedures I

3.8 Ability to analyze the affects of maintenance activities on LCO status 96 97 I Total 1

2 Emergency Procedures /

Plan 99 100 2

NUREG-1021, Revision 9 Page 9 of 10

ES-40 1 Record of Reiected WAS (SRO)

Form ES-401-4 Randomly Selected WA 05862.1.30 Tier / Group 1 /I Reason for Rejection Did not meet guidance in ES-401, Attachment 2 - Replaced with 058G2.1.32 (supplied by NRC) 1 /I 05862.1.32 Unable to write a valid question for KIA - Replaced with 05862.1.33 (supplied by NRC) 5 questions randomly replaced by the NRC with 5 new WAs picked by the NRC NUREG-1021, Revision 9 Page 10 of 10

ES-301 Administrative Topics Outline Form ES-307-1 M, R Facility: Indian Point Unit 3 (rev. 2)

Examination Level: RO SRO Determine minimum staffing requirement and determine from Operations schedule which personnel cankannot be called in.

Candidate reviews Overtime Scheduling Guidelines and a staff Date of Examination: 10/23/06 Operating Test Number: 1 R9D3P Administrative Topic (see Note)

Calculate a Release Rate for a Liquid Release. With the computer not available, the candidate uses multiple worksheets to calculate the most restrictive release rate based upon sample activity, boron Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type I

Describe activity to be performed Perform Daily Containment Leakage Calculation.

Elapsed time from previous reading is calculated. Integrator readings are obtained for each of four weld channel zones and the difference from the previous readings are calculated. The four leakage readings are summed and then divided by the elapsed time to obtain daily leakage.

Generate a Manual Tagout Candidate will prepare a manual tagout (normal means using the SOMs computer application is not available). Candidate will review drawings and tagout points and enter the points and desired position/condition onto the manual tagout form.

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

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( S 3 for ROs; _C 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 2 1)

(P)revious 2 exams ( 1 ; randomly selected)

ES-301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 M9 Facility: Indian Point Unit 3 (rev. 2)

Examination Level: RO 0 SRO Review/Approve a Tagging Order (Faulted)

Candidate will review PLlDs and associated components identified on the tag-out required to provide protection. An error will be identified Date of Examination: 10123/06 Operating Test Number: 1 Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Describe activity to be performed

~

~~

~

Review Daily Containment Leakage Calculation (Faulted)

A completed calculation is supplied that contains two errors. The CRS will review the calculation, note and correct the errors.

Determine minimum staffing requirement and determine from Operations schedule which personnel canlcannot be called in.

Candidate reviews Overtime Scheduling Guidelines and a staff schedule to determine which individuals can cover an unplanned illness without exceeding limits for hours worked. Candidate provides explanation of why unavailable operators cannot be called in.

N, R Review/Approve a Gaseous Release Permit (Faulted)

Candidate will review a completed permit that contains a calculation error. The permit will be reviewed, the error will be identified and corrected.

EAL Classification and Part 1 Form Following the simulator scenario, the CRS candidate will classifiy the event (highest level EAL achieved if the classification escalated during the scenario) and complete the NY State part 1 form.

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

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( S 3 for ROs; s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 2 1)

(P)revious 2 exams (< 1; randomly selected)

ES-301, Page 22 of 27

ES-301 Control Room/l n-P ant Systems Outline Form ES-301-2 Facility: Indian Point Unit 3 (Rev.1)

Date of Examination: 10/23/06 Exam Level: RO ~

~

s 6

6

~

Operating Test No.:

1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Emergency Borate

a.

1 A, N, S

b. Reset SI Using Key Switches

~~~

~~

C. Realign SI For High Head Recirculation

d. RCP #2 Seal Failure Actions L, N, S

e. Transfer from AFW Feed to Low Flow Bypass Feed N, S

f. Align Containment Spray System During Loss of Emergency Coolant Recirculation N, S N, s

g. Restore Steam Flow Channel to Service

h. Adjust R-20 Process Radiation Monitor Setpoints Safety Function 1

2 3

4P 4s 5

7 9

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

. I.

4s Open Steam Supply Valves to 32 ABFP

j. Start the Appendix R Diesel 6

I A, E, N, R

k. Align Backup Cooling to the Charging Pumps 8

~

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

I

Type Codes (A)lternate path (C)ontrol room (0)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (S)imulator P I C A Criteria for RO I SRO-I I SRO-U 4-6 14-6 12-3 5 9 1 s 8 / 1 4 2 1 I:, 1 1 2 1 2 1 I 2 1 1 2 1 2 2 l > 212 1 I 3 / I 3 / 5 2 (randomly selected) 2 1 I:, 1 1 2 I ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 System / JPM Title Type Code*

a.

Safety Function

b.

~~

L, N, S N, S

e. Transfer from AFW Feed to Low Flow Bypass Feed

f. Align Containment Spray System During Loss of Emergency Coolant Recirculation C.

I I

4s 5

I N,S I

4p

d. RCP #2 Seal Failure Actions I

A, E, N Start the Appendix R Diesel i-6

9.

I I

k. Align Backup Cooling to the Charging Pumps

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

I A, E, N, R 8

overlap those tested in the control room.

Type Codes (A)lternate path (C)ontrol room (0)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (Skmulator (RPA Criteria for RO I SRO-I I SRO-U 4-6 14-6 I 2-3

< 91s 8 1 ~ 4 2 1 I 2 1 I > 1 2 1 I 2 1 I > 1

> 2 1 2 2 1 2 1

> I 1 2 1 1 2 1 3 I 3 I I 2 (randomly selected)

ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 N, S L, N, S

d. RCP #2 Seal Failure Actions

e. Transfer from AFW Feed to Low Flow Bypass Feed Facility:

Indian Point Unit 3 (Rev. 1)

Date of Examination: 1 0Q3106 Exam Level: RO ~

~

Operating Test No.:

1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) 4P 4s

~

System / JPM Title N, S

f.

Align Containment Spray System During Loss of Emergency Coolant Recirculation Emergency Borate

a.

5

b. Reset SI Using Key Switches N, s

g. Restore Steam Flow Channel to Service C. Realign SI For High Head Recirculation 7

Type Code*

A, D A, E, N

i. Open Steam Supply Valves to 32 ABFP Start the Appendix R Diesel

j.

Safety Function 4s 6

1

Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including I(A)

( V A (P)revious 2 exams (S)imulator 2

Criteria for RO I SRO-I I SRO-U 4-6 14-6 12-3

< 9 1 2 8 / < 4 2 1 I:: 1 1 2 1 2 1 I:: 112 1

21 2 21:: 1

< 3 I I 3 I < 2 (randomly selected) 2 1 I:: 1 I 2 1 3

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

I A, E, N, R

k. Align Backup Cooling to the Charging Pumps 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

I ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-I I Facility:

Indian Point 3 Scenario No:

1 Op-Test No: 1 I Examiners:

Ope rat0 rs:

I Initial Conditions:

Scenario begins at 6% power with turbine close to sync speed. The team will continue with the startup by synchronizing the unit to the grid and increasing power.

startup. Synchronize the unit to the grid and increase power at 150 MW Malf.

No.

N/A XMT-RCS052 Turnover:

Continue with the per hour.

Event No:

1 2

3 4

5 6

7 MAL-SGN005D MAL-SGN005D MAL-EPSOO6 M AL-S IS004A MAL-SIS004C MAL-SG N004P Event Type*

N (BOP)

N (CRS)

R (CRS)

R (ATC)

I (ATC)

I (CRS)

C (ALL)

M (ALL) c (BOP)

C (BOP)

C (ATC)

Event Description Sync turbine and raise power Thot fails high. CRS references TS SG Tube Leak. CRS references TS

~~

SGTR - Manual reactor trip and manual SI actuation Loss of offsite power when 6.9 KV busses transfer

~

31 and 33 SI pump auto start failure SG safety fails open on ruptured SG I * (N)ormal, (R)eactivity, (I)nstrurnent, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No:

2 Op-Test No:

1 Examiners:

Operators:

Initial Conditions:

The scenario begins at 100% power with 32 EDG out of service due to malfunctioning governor.

Turnover:

32 EDG out of service due to malfunctioning governor.

Maintain current plant conditions.

Event No:

1 2

3 4

5 6

7 8

Malf.

No.

MAL-SWS001 C MAL-EPS005C N/A MAL-NIS006A MAL-EPS001 MAL-DSG001 A MAL-PRS003D MAL-SWS001 E Event Type*

C (BOP)

C (ALL)

R (ATC)

R (CRS)

N (BOP)

N (CRS)

C (ATC)

C(CRS)

M (ALL)

C (BOP)

C (ATC)

C (BOP)

Event Description 33 SWP trips 480V Bus 5A Fault Power Range Channel 41 Upper Detector Fails High Station Blackout 31 EDG fail to start PRZ PORV Fails Open SW pump does not auto start after bus energized

Amendix D Scenario Outline Form ES-D-I Facility: Indian Point 3 Scenario No:

3 Op-Test No: 1 Examiners:

Operators:

Initial Conditions:

The scenario begins at 100% power steady state conditions and no equipment 00s.

Turnover:

Maintain current plant conditions.

Event No:

Event Type*

I (ATC)

I (SRO)

Event PRZR pressure Instrument PT-455 fails high. Spray valves open and actual pressure lowers until manual action is taken.

TS for SRO Descrlptlon Malf.

No.

MAL-PRS005A 1

2 MAL-PRS003C C (ATC)

C (SRO)

PORV 45% fails open. Block valve can be manually closed to isolate the leak. TS for SRO 3

AS IS RWST C (SRO)

Loss of RWST level. Fork truck crashes into RWST resulting in level lowering to about 11 feet over 40 minutes. TS for SRO R (ATC)

R (CRS)

N (BOP)

N (CRS)

Tech Spec Required Shutdown - Due to inoperable RWST, team commences a shutdown.

4 NIA 5

MAL-RCS007C MAL-RCSOI 2C RCP Seal malfunction - High vibrations and # I seal degradation.

During shutdown, indications of RCP malfunction occur.

6 MAL-RCS002C C (ATC)

While team is investigating RCP malfunction the affected RCP trips. RO must manually actuate reactor trip.

~

Seal LOCA on affected RCP occurs resulting in eventual Low Pressure SI actuation SI fails to auto actuate, but manual SI is successful 7

M (ALL)

MAL-RCS001 K 8

MAL-SIS001A MAL-SIS001 B MAL-S I S004B

~~

32 SI Pump fails to auto start 34 and 35 FCU dampers do not auto reposition to incident mode.

9 C (BOP)

C (BOP)

' (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I

Appendix D Scenario Outline Form ES-D-I Facility: Indian Point 3 Scenario No:

4 Rev.1 Op-Test No: 1 I

Operators:

I Examiners:

Initial Conditions:

Scenario begins with the plant stable at 100% power. 31 ABFP has been out of service for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months for bearing inspections with an expected return to service in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Tu rnove r:

31 ABFP has been out of service for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months for bearing inspections with an expected return to service in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Maintain Current Plant Conditions Malf.

I Event No.

I Type*

I XMT-MSSO19 I

I(ATC)

XMT-MSSO19 C (ATC)

N (BOP)

N (CRS)

R (ATC)

R (CRS)

AL-CFW005C C (ALL)

R (ATC)

R (CRS)

MAL-CFW015 1 M (ALL)

MAL-CFWOOl B Event Description PT-412A fails low TS CRS Loss of Condenser Vacuum and subsequent power reduction Condensate Pump trip Event No:

1 2

3 4

5 6

7

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Auto reactor trip failure, one RTB does not open MDAFP 33 fails to start (with 31 MDADP 00s) manual action required to feed with turbine driven ABFP TDAFP trip, results in loss of heat sink

ML070310117

Text

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