ML021350045

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Final - Outlines (Change Summaries - Optional)
ML021350045
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/18/2002
From: Diane Jackson
Public Service Enterprise Group
To: Conte R
NRC/RGN-I/DRS/OSB
References
05000354/2002-301 05000354/2002-301
Download: ML021350045 (35)
v • d • e


Text

NC.TQ-WB.ZZ-0027(Z)

ES-301 Administrative Topics Outline FORM ES-301-1 Page 1 of 1 Facility:

HOPE CREEK Date of Examination:

03/11/02 Examination Level:

Z RO E] SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description
2. TWO Administrative Questions A.1 Conduct of 2.1.25 Ability to obtain and interpret station reference materials Operations such as graphs/monographs/and tables which contain data. (2.8)

Question-Given plant conditions, determine the required Circulation Water System requirements for extreme cold weather.

Plant Parameter (NEW)

Verification 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data. (2.8)

Question-Obtain maximum RWCU return to Feedwater Temperature.

(NEW) 2.1.3 Knowledge of shift turnover practices. (3.0)

Shift Turnover JPM-Complete shift turnover attachment as off-going RO.

(Simulator Perform) (5/00 NRC Exam) (Modified)

A-2 Equipment Control 2.2.12 Knowledge of surveillance procedures. (3.0)

Surveillance JPM-Perform alternate determination of Drywell Air Temperature.

Procedures (Simulator Perform) (NEW)

A-3 Radiation Control 2.3.11 Ability to control radiation releases (2.7)

Radiation Releases JPM-Calculate Iodine Release Rates (Simulator Perform) (NEW)

A.4 Emergency Plan 2.4.39 Knowledge of the RO's responsibilities in emergency plan Emergency Action implementation. (3.3)

Levels and JPM-Perform the Licensed Operator Review of the Operational Classifications Status Board-Hope Creek (Simulator Perform) (NEW)

Last saved: 01/1112002 11:46 AM Page 27 of 64 Rev. I

NC.TQ-WB.ZZ-0027(Z)

ES-301 Administrative Topics Outline FORM ES-301-1 Page 1 of 1 Facility:

HOPE CREEK Date of Examination:

03/11/02 Examination Level:

[

RO

[

SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description
2. TWO Administrative Questions Conduct of Operations 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data.

(3.1)

Question-Given plant conditions, determine the required Circulation Water System requirements for extreme cold weather.

Plant Parameter (NEW)

Verification 2.1.25 Ability to obtain and interpret station reference materials A.1 such as graphs/monographs/and tables which contain data.

(3.1)

Question-Calculate time to establish Secondary Containment following a loss of Shutdown Cooling. (NEW) 2.1.3 Knowledge of shift turnover practices. (3.4)

Shift Turnover JPM-Complete key verification required during CRS shift turnover.

(In-plant Perform)(NEW)

A.2 Equipment Control 2.2.12 Knowledge of surveillance procedures. (3.4)

Surveillance JPM-Perform Drywell Air Temperature Operability Check.

Procedures (Simulator Perform) (NEW)

A.3 Radiation Control 2.3.11 Ability to control radiation releases (3.2)

Exposure Control JPM-Calculate Iodine Release Rates (Simulator Perform) (NEW)

A.4 Emergency Plan 2.4.41 Knowledge of the Emergency Action Level thresholds and Emergency Action classifications. (4.1)

Levels and JPM -Given a set of conditions, classify an event and complete the Classifications Initial Contact Message Form. (Modified)

Last saved: 01/11/2002 11:46 AM Page 27 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2 Page 1 of 1 Facility:

HOPE CREEK Date of Examination:

03/11/02 Examinations Developed by:

Z Facility D

NRC Examination Level:

Z RO Z

SRO(l)

Operating Test Number:

B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a. CRD-Stuck Rod during Shutdown Rod Exercising (N), (A), (L), (S) 1
b. EHC-Respond to Low EHC Pressure (D), (A), (S) 3
c. Recirc-Raise Reactor Recirculation Pump Speed >100%

(N), (S) 4

d. Condensate-Place 2 nd Secondary Condensate Pump In-(D), (L), (S) 2 service
e. RPS-Bypassing Scram during ATWS (D), (S) 7
f.

,IQ U

I r-L I

1 It L,

,I.

I I.

U V.

t (M ), (A), (S) 8

g. EDG-Non-emergency operations of an EDG (D), (S), (E) 6 B.2 Facility Walk-Through
a. RPS MG Set Failure to start (M), (A), (P) 7
b. Sample Primary Containment Atmosphere (D), (P), (R) 5
c. Respond to a Failed Open Safety Relief Valve (Abnormal)

(D), (P), (E) 3

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA, (E)SF Last saved: 01/11/2002 11:46 AM Page 28 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2 Page 1 of 1 Facility:

HOPE CREEK Date of Examination:

03/11/02 Examinations Developed by:

Z Facility

-]I NRC Examination Level:

EI RO Z

SRO(U)

Operating Test Number:

B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a. CRD-Stuck Rod during Shutdown Rod Exercising (N), (A), (L), (S) 1
b. Instrument Air-Place the Emergency Instrument Air (M), (A), (S) 8 Compressor in service
c. EDG-Non-emergency operations of an EDG (D), (S), (E) 6
d.
e.
f.
g.

B.2 Facility Walk-Through

a. Respond to a Failed Open Safety Relief Valve (Abnormal)

(D), (P), (E) 3

b. Sample Primary Containment Atmosphere (D), (P), (R) 5 C.

Last saved: 01/11/2002 11:46 AM

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA, (E)SF Rev. 1 Page 28 of 64

NC.TQ-WB.ZZ-0027(Z)

Appendix D Scenario Outline Form ES-D-1 Page 1 of 1 Facility:

Hope Creek Scenario Number:

1 Operating Test Number:

Examiners:

Evaluators:

Objectives:

Initial Plant is operating at 80% power. Shutdown in progress. 10-0004, Step 5.1.5.

Conditions:

Shutdown sequence Step 723 Continue with plant shutdown. Place C RFP in Recirc. Reduce power with control Turnover:

rods by inserting RWM Group 84, and then contact Reactor Engineer for further guidance.

Event Malf.

Event Event Description Number Number Type*

1 N(PO)

Place 3rd Reactor Feed Pump in Recirc.

N(SRO)

2.

N(SRO)

Reduce power with Control Rods I(RO)

3.

RR-19 I(SRO)

Flow Comparator Failure C(PRO)

4.

C(PO)

Loss of Reactor Building Ventilation/Secondary Containment C(SRO)

5.

CD-10OA C(SRO)

CRD Pump trip RCIC steam leak w/ failure to isolate/High HPCI Room

6.

RC-09/10 M(ALL)

Temp/Scram

7.

I(PO)

ADS failure to initiate during Emergency Depressurization I(SRO)

(Similar event to Audit, different initiating cause and failure.)

  • (N)ormal, (R)eactivity, Last saved: 01/11/2002 11:46 AM (I)nstrument, (C)omponent, (M)ajor Page 64 of 64 Rev. I

NC.TQ-WB.ZZ-0027(Z)

Appendix D Scenario Outline Form ES-D-1 Page 1 of 1 Facility:

Hope Creek Scenario Number:

2 Operating Test Number:

Examiners:

Evaluators:

Objectives:

Initial Modified ESG-042.

Conditions:

Plant is operating at 95% power. D Circulating Water Pump OOS for maintenance.

Turnover:

Place B RFP in service. Raise Reactor power to 100% with Recirculation flow.

Event Malf.

Event Event Description Number Number Type*

1.

N(PO)

Place RFP in service N(SRO)

2.

C(PO)

Inadvertent Loss of Circulating Water Pump B/Degrading C(SRO)

Condenser Vacuum

3.

R(RO)

Reduce power to maintain Condenser Vacuum

4.

RR-05/

C(RO)

Dual Recirc Seal Failure RR-06 C(SRO)

RR-08/

5.

RR-26 I(ALL)

Recirc Pump Speed Control Failure/High Vibrations/Scram

6.

RR-31 M(ALL)

Recirc Line Break/Primary Containment Failure

7.

C(PO)

Containment Spray Valve Failure C(SRO) 8.

(N)ormal, (R)eactlvity, Last saved: 01/11/2002 11:46 AM (I)nstrument, (C)omponent, (M)ajor Page 64 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

Appendix D Scenario Outline Form ES-D-1 Page 1 of 1 Facility:

Hope Creek Scenario Number:

3 Operating Test Number:

Examiners:

Evaluators:

SPARE Objectives:

SPARE SCENARIO Initial 36% Power. Reactor startup in progress.

Conditions:

Turnover:

Transfer B RPS to the Alternate Power Supply. Raise Reactor power with Control Rods.

Event Malf.

Event Event Description Number Number Type*

1.

N(ALL)

Transfer B RPS to the Alternate Power Supply

2.

R(RO)

Raise power with Control Rods (Similar to Audit, different power)

N(SRO)

3.

NM-21 I(RO)

APRM Malfunction (Similar to Audit, failure is different)

C (P0)

4.

CW-08B C(SO)

Loss of a RACS pump B C(SRO)

5.

EG-04 M(ALL)

Loss of SWC/ATWS/SLC Pump Failure/Loss of Off-site Power I(RO)

6.

CU-I11A/B I(R)Failure of RWCU Isolation Logic

7.

HP-06E I(PO)

HPCI auto initiation failure I _(SRO) I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Last saved: 01/11/2002 11:46 AM Page 64 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Transient and Event Checklist FORM ES-301-5 Page 1 of 1 Operating Test Number:

Minimum Scenario Number Applicant Type Evolution Type Number 1

2 3

4 Reactivity 1

2 Normal 1

1 RO(1)

Instrument 4

35 25,7 Component Major 1

6 6

Reactivity 1

3 Normal 0

As RO Instrument 24 Component Major 1

6 SRO-1(6)

Reactivity 0

Normal 1

1,2 As SRO Instrument 2

3,4,5 Component Major 1

6 Reactivity 0

Normal 1

1,2 SRO-U(7)

Instrument 2

2 Component Major 1

6 (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements.

Author:

GkL-NRC Reviewer:

/1 Last saved: 01/11/2002 11:46 AM Instructions:

,/

Page 31 of 64 Rev. I

NC.TQ-WB.ZZ-0027(Z)

ES-301 Transient and Event Checklist FORM ES-301-5 Page 1 of 1 Operating Test Number:

Minimum Scenario Number Applicant Type Evolution Type Number 1

2 3

4 Reactivity 1

3 Normal 1

1 RO(2)

Instrument 4

47 45 Component Major 1

6 6

Reactivity 1

Normal 0

As RO Instrument 2

Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument 2

Component Major 1

Reactivity 0

Normal 1

1,2 SRO-U(8)

Instrument 23 Component Major 1

6 (4) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(5) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(6) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insig t to the applicant's competence count toward the minimum requirements.

Author:

"ý ua

'-I NRC Reviewer:

/

Last saved: 01/11/2002 11:46 AM Instructions:

Page 31 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Transient and Event Checklist FORM ES-301-5 Page 1 of 1 Operating Test Number:

Evolution Type Minimum Scenario Number Applicant Type Number 1

2 3

4 Reactivity 1

2 Normal 1

1 RO(3)

Instrument 4

35 2,5,7 Component Major 1

6 6

Reactivity 1

Normal 0

As RO Instrument 2

Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument 2

Component Major 1

Reactivity 0

Normal 1

SRO-U Instrument 2

Component Major 1

Instructions:

(7) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(8) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(9) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements.

/ f Author:

NRC Reviewer:

77 Last saved: 01/11/2002 11:46 AM

// //

Page 31 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Transient and Event Checklist FORM ES-301-5 Page 1 of 1 Operating Test Number:

Minimum Scenario Number Applicant Type Evolution Type Number 1

2 3

4 Reactivity 1

3 Normal 1

1 RO(4)

Instrument 4

47 45 Component Major 1

6 6

Reactivity 1

Normal 0

As RO Instrument 2

Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument 2

Component Major 1

Reactivity 0

Normal 1

SRO-U Instrument 2

Component Major 1

Instructions:

(10) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(11) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(12) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements.

Author:

NRC Reviewer:

Last saved: 01/11/2002 11:46 AM aýL-E a-L-Page 31 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Transient and Event Checklist FORM ES-301-5 Page 1 of I Operating Test Number:

Evolution Type Minimum Scenario Number Applicant Type Number 1

2 3

4 Reactivity 1

2 Normal 1

1 RO(5)

Instrument 4

35 2,5,7 Component Major 1

6 6

Reactivity 1

Normal 0

As RO Instrument 2

Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument 2

Component Major 1

Reactivity 0

Normal 1

SRO-U Instrument /2 Component Major 1

(13) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(14) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(15) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements.

, /2 Author:

NRC Reviewer:

// //>

7/

1/.

Last saved: 01/11/2002 11:46 AM Instructions:

Page 31 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Competencies Checklist FORM ES-301-6 Page 1 of 1

(,spplicant #1

,/-.pplicant #2

,..Applicant #3 (R)ROI!/SRO U

(,R9RSRO-I/SRO-U (R 9 LR0@SO-tSRO U Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

Understand and Interpret 3,5, 2,5, 2,4, 3,5, 26 Annunciators and Alarms 6

2,6 6,7 5,6 6

Diagnose Events and 3,5, 2,6, 2,6, 4,5, 3,5, 2,6, Conditions 6

7 7

6 6

7 Understand Plant and System 2,3, 1,2, 1,2, 2,3, 2,3, 1,2,

Response

5,6 6,7 5,6, 4,5, 5,6 6,7 7

6 1,2, 1,2, 452,,

1,2, Comply With and Use 2,3, 5,6, 5,6, 6

5,6, Procedures (1) 5,6 7

7 23 1,2, 1,2, 34 2,3 1,2, Operate Control Boards (2) 5,6 7

7 5,6 5,

6, 7

7 7

Communicate and Interact 2,3, 1,2, 1,2, 1,2, With the Crew 5,6 5,6, 5,6, 5,6 5,

6, 7

Demonstrate Supervisory Ability (3)

Comply With and Use Tech.

Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle the applicant's license type and enter one or more examiners to evaluate every applicable omptenc for Author:

NRC Reviewer:

/A numbers that will allow the Last saved: 01/11/2002 11:46 AM Page 32 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Competencies Checklist FORM ES-301-6 Page 1 of 1

-,Applicant #4

,--pplicant #5 AppRiant#6 (R)ROUISRO U R(,,RgSRO I!SRO U Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

4 Understand and Interpret 2,5, 2,4, 3,5 2,6 2,4 2,4, Annunciators and Alarms 6,7 5,6 6

5,6 5,6 Diagnose Events and 2,6, 4,5, 3,5, 2,6, 2,4, 4,5, Conditions 7

6 6

7 5,6 6

Understand Plant and System 12, 2,3, 2,3, 1,2, 1,2, 2,3, 5,6, 4,5, 5,6 6,73,4, 4,5,

Response

7 6

5,6 6

1,2,

~2,3, 45 Comply With and Use 1,2, 4,5, 2,3, 1,2, 4,5, 5,6, 6

5,6, 4,5, 6

Procedures (1) 6 5

6 1,2, 2,3, 1,2, 3,4, Operate Control Boards (2) 5,6, 5,

2 5,6, 5,2 7

5,6 5,6 5,6 Communicate and Interact 1,2, 3,4, 2,3, 1,2, 1,2, With the Crew 7 5,6 5,67 5,6, 5,6 7

Demonstrate Supervisory 2,3, 4,5, Ability (3) 6,7 Comply With and Use Tech.

4 Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable comp tencycfor eV applicant.

Author:

=

/

NRC Reviewer:

Last saved: 01/11/2002 11:46 AM Page 32 of 64 Rev. 1

NC.TQ-WB.ZZ-0027(Z)

ES-301 Competencies Checklist FORM ES-301-6 Page 1 of 1 Applica*-#-7---,

Applicat R_

_O

,R,0 RO/SRO 4XQOP Competencies SCENARIO SCENARIO 1

2 3

4 1

2 3

4 Understand and Interpret 2,4 2,4 Annunciators and Alarms 5,6 5,6 Diagnose Events and 2,4, 2,4, Conditions 5,6 5,6 Understand Plant and System 1,2, 1,2, 3,4, 3,4,

Response

5,6 5,6 Comply With and Use 2,3, 2,3, 4,5, 4,5, Procedures (1) 6 6

Operate Control Boards (2) 1,2, 1,2, Communicate and Interact 3,4, 3,4, With the Crew 5,6, 5,6, 7

7 Demonstrate Supervisory 2,3, 2,3, 4,5, 4,5, Ability (3) 6,7 6,7 Comply With and Use Tech.

4 Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable comretency for ry applicant.

Author:

NRC Reviewer:

7 /'

1/

Last saved: 01/11/2002 11:46 AM Page 32 of 64 Rev. 1

ES-401 System # Name 295005 Main Turbine Generator Trip 295006 SCRAM 295006 ýSCRAM 295007 !High Reactor Pressure 295007 High Reactor Pressure 295009 Low Reactor Water Level 295010 High Drywell Pressure 295014 inadvertent Reactivity Addition 295014 Inadvertent Reactivity Addition 295015 Incomplete SCRAM 295024 High Drywell Pressure BWR RO Examination Outline Emergency and Abnormal Evolutions - Tier 1/Group 1 K1 K2 K3IA1 A2 G KA Topic(s)

X X

X X

X X 12.1.28 Knowledge of the purpose and function of major system components and controls.

AK1.01 Decay heat generation and removal.

AK2.05 Shutdown cooling: Plant-Specific AK3.04 Safety/relief valve operation: Plant-Specific "X I AA2.01 Reactor water level X "

AA1.02 Drywell floor and equipment drain sumps SAK2.04 Void concentration AK3.01 Reactor SCRAM X

!EA1.10 A.C. distribution

!High Drywell Pressure High Reactor Pressure High Reactor Pressure Reactor Low Water Level SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown High Containment Hydrogen Concentration X 2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions.

X EA2.06 Reactor water level X

EK1.05 Exceeding safety limits X

EK2.13 ARI/RPT/ATWS: Plant-Specific X

1EK3.03 Operation of hydrogen and oxygen recombiners Tuesday, March 26, 2002 5:38:22 PM ES-401-2 Imp. Pts.

3.2 1

3.7 1

2.9 1

4.0 1

4.2 1

3.6 1

3.2 1

4.1-1 295024 295025 295025 295031 295037 500000 3.4 1

2.1 1_

3.7 1

4.4 1

4.1 1

3.0 1

Page 1

ES-401 System #

295001 295002 295003 295003 295004 295008 295008 295011 295012 295013 295016 Name Partial or Complete Loss of Forced Core Flow Circulation Loss of Main Condenser Vacuum Partial or Complete Loss of A.C. Power Partial or Complete Loss of A.C. Power Partial or Complete Loss of D.C. Power High Reactor Water Level High Reactor Water Level High Containment Temperature (Mark III Containment Only)

High Drywell Temperature High Suppression Pool Temperature

!Control Room Abandonment IAK2.01 Suppression pool cooling X

AA1.02 Reactor/turbine pressure regulating system 295017 High Off-Site Release Rate 295018 Partial or Complete Loss of Component Cooling Water 295019 Partial or Complete Loss of Instrument Air 295019 Partial or Complete Loss of Instrument Air 295020 Inadvertent Containment Isolation 295022 Loss of CRD Pumps 295026 Suppression Pool High Water Temperature 295027 High Containment Temperature (Mark Ill Containment Only)

Tuesday, March 26, 2002 5:38:22 PM X

X MAA2.01 Instrument air system pressure X

MAA1.02 Instrument air system valves: Plant-Specific X

IAK2.03 Accumulator pressures.

LA E K1.02 Steam condensation Page 2 3.6 1

2.9 1

3.5 3.3 3.4 3.5 1

1*

1 1

I BWR RO Examination Outline ES-401-2 Emergency and Abnormal Evolutions - Tier 1/Group 2 K1 K2 iA1 A2 KATopic(s)

Imp. Ptsj X

1,AA1.02 RPS 3.3 1

X AK1.04 Increased offgas flow 3.0 1

i AA1.03 Systems necessary to assure safe plant shutdown 4.4 1

! 'X ý2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of 3.3 1

IRHR) mitigation strategies.

X l iAK3.03 Reactor SCRAM: Plant-Specific 3.1 1

X 1 IAK3.04 Reactor feed pump trip: Plant-Specific 3.3 1

SX I IAA1.01 Reactor water level control: Plant-Specific 3.7 1

X ii TAK1 n1 Presure/temneratuire reifir'nshin

3.

1

ES-401 System #

295028 295029 295030 295033 295034 295038 295038 600000 BWR RO Examination Outline Emergency and Abnormal Evolutions - Tier 1/Group 2 K K EKK31Al A2 EGmKA Topic(s)

X

ýEKi.02 Equipment environmental qualification IName High Drywell Temperature IHigh Suppression Pool Water Level I

Low Suppression Pool Water Level High Secondary Containment Area Radiation Levels Secondary Containment Ventilation High Radiation IHigh Off-Site Release Rate High Off-Site Release Rate IPlant Fire On Site Tuesday, March 26, 2002 5:38:23 PM IEK1.02 Protection of the general public IEA2.03 Radiation levels I 2 5 Kct p

Atc

'e 4 X ý2.4.25 Knowledge of fire protection procedures.

ES-401-2 Imp. Pts.

2.9 1

3.8 1

4.2 1

3.5 1

2.9--

Page 3

JES-401 System # IName 295021 ILoss of Shutdown Cooling 295023 Refueling Accidents 295023,Refueling Accidents 295032 !High Secondary Containment Area

!Temperature 295035 iSecondary Containment High Differential lPressure 295036 Secondary Containment High Sump/Area Water Level 295036 Secondary Containment High Sump/Area

'Water Level BWR RO Examination Outline Emergency and Abnormal Evolutions - Tier 1/Group 3 K1 K2iK3 A 1A2 G KA Topic(s)

X 2.4.11 Knowledge of abnormal con

-XT TrAA1.02 Fuel pool cooling and cleai X

dition procedures.

nup system EK3.01 Emergency depressurization iEK2.01 Secondary containment equipment and floor drain system Tuesday, March 26, 2002 5:38:23 PM ES-401-2 Imp. IPts.

3.4 1

2.9 1

2.6 1

3.1 1

Page 4

E mS-40 1

rSystem FName BWR RC Plant Sy K IK2 K3 K4 K5 K6 AI A2

Examination Outline stems - Tier 2/Group 1 A3 A4 G KA Topic(s) 201001 IControl Rod Drive Hydraulic System 201002 Reactor Manual Control System 201002 Reactor Manual Control System X

201005 Rod Control and Information System (RCIS) 202002 Recirculation Flow Control System X

203000 RHR/LPCI: Injection Mode (Plant X

Specific) 203000 RHR/LPCI: Injection Mode (Plant S pecifi c) 206000 High Pressure Coolant Injection System 206000 High Pressure Coolant Injection System 207000 Isolation (Emergency) Condenser 209001 Low Pressure Core Spray System X

209001 Low Pressure Core Spray System X

209002 High Pressure Core Spray System (HPCS) 211000 Standby Liquid Control System 211000 Standby Liquid Control System X

"212000 Reactor Protection System 212000 Reactor Protection System X

X 1 A3.05 Reactor water level 2.8 1

I X 2.4.21 Knowledge of the parameters and logic used to assess the status of 3.7 1

safety functions including:

1.Reactivity control 2.Core cooling and heat removal 3.Reactor coolant system integrity 4.Containment conditions 5.Radioactivity release control.

IK4.08 Continuous In rod insertion 3.2 1

K6.04 Feedwater flow inputs: BWR-3, 4, 5,6 K1.14 Shutdown cooling system: Plant-Specific 1X A4.07 Reactor water level X

A3.07 Lights and alarms: BWR-2, 3, 4 X

A1.06 System flow: BWR-2, 3, 4 KK1.10 Emergency generator K2.02 Valve power 3.5 1

3.6 1

4.5 1

3.9 1

3.8 1

3.7 1

2.5 1

X 2.4.10 Knowledge of annunciator response procedures.

3.0 K1.05 RWCU 3.4 2.1.23 Ability to perform specific system and integrated plant procedures during 3.9 different modes of plant operation.

I-3.3 K5.02 Specific logic arrangements 3.3 Tuesday, March 26, 2002 5:38:39 PM ES-401-2 Imp. Pts.

Page 1

ES-401 System Name 215003 Intermediate Range Monitor (IRM) System 215004 Source Range Monitor (SRM) System 215005 Average Power Range Monitor/Local Power Range Monitor System 215005 Average Power Range Monitor/Local Power Range Monitor System 216000 Nuclear Boiler Instrumentation 216000 Nuclear Boiler Instrumentation 217000 Reactor Core Isolation Cooling System (RCIC) 218000 Automatic Depressurization System 223001 Primary Containment System and Auxiliaries 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off 239002 Relief/Safety Valves 239002 Relief/Safety Valves 241000 Reactor/Turbine Pressure Regulating System 259001 Reactor Feedwater System 259002 Reactor Water Level Control System 261000 Standby Gas Treatment System 261000 Standby Gas Treatment System 264000 Emergency Generators (Diesel/Jet)

BWR RO Examination Outline Plant Systems - Tier 2/Group 1 K1 QK2 K3T K4 K51 K6,AI A2 A3 [A41 G KA Topic(s)

X X

X 1

X X

xX x

IA3.03 RPS status

K3.05 Reactor power indication K5.05 Core flow effects on APRM trip setpoints K2.01 Analog trip system
Plant-Specific A2.08 Elevated containment temperature IK4.05 Prevents radioactivity release to auxiliary/reactor building IK6.13 Applicable plant air system/ nitrogen make-up system.

IK3.16 Shutdown cooling system/RHR IK4.01 Redundancy iA1.05 Reactor water level AA1.02 Acoustical monitor noise: Plant-Specific X

"K6.03 Emergency diesel generator system X { A4.07 System flow Tuesday, March 26, 2002 5:38:40 PM 73 iX Page 2 ES-401-2 Imp. Pts.

3.6 1

3.8 1

3.6 1

2.8 1

3.2 1

3.2 1

3.2 1

3.2 1

3.0 1

3.7 1

3.7 1

3.0 1

3.1 1

IES-401 System IName Ki K2XK3:K4 201003 Control Rod and Drive Mechanism X

201004 Rod Sequence Control System (Plant Specific) 201006 Rod Worth Minimizer System (RWM)

X I(Plant Specific) 202001 iRecirculation System X

202001 IRecirculation System 204000 [Reactor Water Cleanup System 205000 Shutdown Cooling System (RHR

!Shutdown Cooling Mode) 214000 1Rod Position Information System 215002 Rod Block Monitor System 219000 IRHR/LPCI: Torus/Suppression Pool

,Cooling Mode 226001 !RHR/LPCI: Containment Spray System Mode 226001 RHR/LPCI: Containment Spray System Mode 230000 RHR/LPCI: Torus/Suppression Pool Spray Mode 239001 IMain and Reheat Steam System 245000 !Main Turbine Generator and Auxiliary

Systems 256000 Reactor Condensate System X

256000 [Reactor Condensate System 262001 iA.C. Electrical Distribution 262001 A.C. Electrical Distribution 262002-Uninterruptable Power Supply (A.C./D.C.)

Tuesday, March 26, 2002 5:38:40 PM BWR RO Examination Outline Plant Systems - Tier 2/Group 2 K5 K6 Al A2 A3 A41 GKAlopic(s)

K4.05 Rod position indication X

X X

K3.01 Reactor manual control system: P-Spec(Not-BWR6)

K3.07 Vessel bottom head drain temperature K

IA4.04 System flow A2.14 System high temperature A3.01 Valve operation X

A3.05 Containment pressure AA1.06 System flow K6.01 A.C. electrical X

K5.02 Turbine operation and limitations K4.06 Control of extraction steam X

A2.13 Loss of applicable plant air systems X

IK6.01 D.C. power K2.01 Off-site sources of power Page 3 ES-401-2 Imp.

Pts.

3.2 1

"3.2 1

2.9 1

3.7 1

3.2 1

3.3 1

4.0 1

3.2 1

3.3 1

2.8 2.8 2.9 3.1 3.3 1

1 1

1 X!

IES-401

!System Name K

263000 D.C. Electrical Distribution 263000 D.C. Electrical Distribution 271000 Offgas System 272000 Radiation Monitoring System 286000 Fire Protection System 290001 Secondary Containment 290003 Control Room HVAC 300000 Instrument Air System (IAS) 400000 Component Cooling Water System (CCWS)

BWR RO Examination Outline Plant Systems - Tier 2/Group 2 1 1,2 1<31Ka4KB5KB6KAl A2FA3A4 G Topic(s)

X K2.01 Major D.C. loads SX A1.01 Battery charging/discharging rate SK1.02 Process radiation monitoring system X

i; K6.03 A.C. power x

(K5.01 Airborne contamination (e.g., radiological, toxic gas, smoke) control Tuesday, March 26, 2002 5:38:41 PM ES-401-2 Imp. Ptsj 3.1 1

2.5 1

3.1 1

2.8 1

3.2 1

Page 4

Ki1 K21.3[K4 K5 215001 Traversing In-Core Probe 1 X 233000 Fuel Pool Cooling and Clean-up 234000 Fuel Handling Equipment 239003 IMSIV Leakage Control System 268000 ýRadwaste 288000 Plant Ventilation Systems 290002 Reactor Vessel Internals 290002 Reactor Vessel Internals BWR RO Examination Outline Plant Systems - Tier 2/Group 3 kK6 AlA2TA31A4 G KA Topic(s)

,K1.05 Primary containment isolation system: (Not-BWR1)

IA1.01 Radiation level x

IA2.02 Overpressurization transient

!K3.03 Reactor power Tuesday, March 26, 2002 5:38:41 PM 1,ES-401 System ýName ES-401-2 Imp. Pts.

3.3 1

2.7 1

"3.6 1

3.3 1

Page 5

ES-4(

Facilit Conduc Equipm Generic Knowledge and Abilities Outline (Tier 3)

ES-401-5 ty: Hope Creek Date of Exam 03/12/2002 Exam Level: RO Category KA #

Topic Imp.

oints ct of Operations I 2.1.33 Ability to recognize indications for system operating parameters which 3.4 1

are entry-level conditions for technical specifications.

2.1.3 Knowledge of shift turnover practices.

3.0 1

2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

2.8 1

Total 3

"ient Control 2

Knowledge of the refueling process.

2.6 1

2.222 Knowledge of limiting conditions for operations and safety limits.

3.4 1

2.2.30 Knowledge of new and spent fuel movement procedures.

2.6 1

Total 3

Radiological Controls 2.3.1,

Knowledge of 10 CFR 20 and related facility radiation control 2.6 1

requirements.

2.3.11 Ability to control radiation releases.

2.7 1

2.3.9 Knowledge of the process for performing a containment purge.

2.5 1

2.3.2 Knowledge of facility ALARA program.

2.5 1

Total 4

Emergency Procedures 2.4.5 Knowledge of the organization of the operating procedures network for 2.9 1

and Plan normal, abnormal, and emergency evolutions*

2.4.34 lKnowledge of RO tasks performed outside the main control room during 3.8 1

lemergency operations including system geography and system "2.4.18 Knowledge of the specific bases for EOPs.

2.7 1

Total 3

Tier 3 Target Point Total (RO/SRO) 13 ke tft k

ý Tuesday, March 26, 2002 5:38:52 PM

IES-401 System # Name 295003 Partial or Complete Loss of A.C. Power 295006 SCRAM 295006 SCRAM 295007 High Reactor Pressure 295007 High Reactor Pressure 295009 Low Reactor Water Level 295009 Low Reactor Water Level 295010 High Drywell Pressure 295013 High Suppression Pool Temperature 295014 Inadvertent Reactivity Addition 295014 Inadvertent Reactivity Addition 295015 !incomplete SCRAM 295015 Incomplete SCRAM 295016 Control Room Abandonment 295017 ýHigh Off-Site Release Rate 295023 IRefueling Accidents 295023 Refueling Accidents 295024 High Drywell Pressure 295024 High Drywell Pressure BWR SRO Examination Outline ES-401-1 Emergency and Abnormal Evolutions -Tier 1/Group 1 Ki.K2 K3 Al A2 G KATopic(s)

Imp. Pts.

"X AA1.03 Systems necessary to assure safe plant shutdown 1 4.4 1

1 X 2.1.28 Knowledge of the purpose and function of major system components and controls.

3.3 1

X i AK1.01 Decay heat generation and removal.

3.9 1

X AK2.05 Shutdown cooling: Plant-Specific 3.1 1

X AK3.04 Safety/relief valve operation: Plant-Specific 4.1 1

I IAA2.01 Reactor water level 4.2 1

X 2.4.6 Knowledge symptom based EOP mitigation strategies.

4.0 " 1 S AA1.02 Drywell floor and equipment drain sumps 3.6 1

!AK2.01 Suppression pool cooling 3.7 1

X F AK3.01 Reactor SCRAM 4.1 1

X AK2.04 Void concentration 3.3 1

X IAK3.01 Bypassing rod insertion blocks 3.7 1

X i2.3.4 Knowledge of radiation exposure limits and contamination control, including 3.1 1

ýpermissible levels in excess of those authorized.

X

'AA1.02 Reactor/turbine pressure regulating system 3.1 1

1 X

AA2.01 Off-site release rate: Plant-Specific 4.2 1

X AA1.02 Fuel pool cooling and cleanup system 3.1 1

X 2.4.11 Knowledge of abnormal condition procedures.

3.6 1

X -X EAI.10 A.C. distribution 3.6 1

Th X 2.1.6 Ability to supervise and assume a management role during plant transients and 4.3 1

upset conditions.

Tuesday, March 26, 2002 5:39:27 PM Page 1

JES-401 System # IName 295025 IHigh Reactor Pressure 295026 ISuppression Pool High Water Temperature 295027 High Containment Temperature (Mark Ill Containment Only) 295030 TLow Suppression Pool Water Level 295030 ILow Suppression Pool Water Level 295031 Reactor Low Water Level 295037 SCRAM Condition Present and Reactor PPower Above APRM Downscale or Unknown 295038 !High Off-Site Release Rate 500000 IHigh Containment Hydrogen Concentration BWR SRO Examination Outline Emergency and Abnormal Evolutions - Tier l/Group 1 Ki K2 K3 Al A2 G KA Topic(s)

X JEK1.05 Exceeding safety limits

-X EK1.02 Steam condensation X

I EK2.03 LPCS X

EA2.04 Drywelli suppression chamber differential pressure: Mark-I&ll X

EK2.13 ARI/RPT/ATWS: Plant-Specific X

IEK1.02 Protection of the general public X

EK3.03 Operation of hydrogen and oxygen recombiners Tuesday, March 26, 2002 5:39:28 PMPa ES-401-1 Imp. Pts.

4.7 1

3.8 1

3.9 1

3.7 1

4.2 1

4.4 1

3.5 1

Page 2

ES-401 System # Name 295001 Partial or Complete Loss of Forced Core F Circulation 295002 Loss of Main Condenser Vacuum 295004 Partial or Complete Loss of D.C. Power 295004 Partial or Complete Loss of D.C. Power 295005 Main Turbine Generator Trip 295008 High ReIactor Water Level 295008 High Reactor Water Level 295011 iHigh Containment Temperature (Mark III IContainment Only) 295012 High Drywell Temperature 295018 Partial or Complete Loss of Component "Cooling Water 295019 Partial or Complete Loss of Instrument Air low BWR Emergency and /

K1 K2 K3 AlA2. G X

X xt x

XX X

X SRO Examination Outline

\\bnormal Evolutions - Tier 1/Group 2

ýKA Topic(s)

AA1.02 RPS AK1.04 Increased offgas flow AK3.03 Reactor SCRAM: Plant-Specific

AA2.01 Cause of partial or complete loss of D.C. power AA2.04 Reactor pressure AA1.01 Reactor water level control
Plant-Specific AK3.04 Reactor feed pump trip: Plant-Specific AK1.01 Pressure/temperature relationship AA2.03 Cause for partial or complete loss AA1.02 Instrument air system valves: Plant-Specific 295020 Inadvertent Containment Isolation 295021 jLoss of Shutdown Cooling 295022 Loss of CRD Pumps 295022 Loss of CRD Pumps I X 295028 High Drywell Temperature X

295029 High Suppression Pool Water Level 295032 High Secondary Containment Area Temperature 295033 !High Secondary Containment Area Radiation Levels Tuesday, March 26, 2002 5:39:28 PM X 2.4.41 Knowledge of the emergency action level thresholds and classifications.

X 2.4.48 Ability to interpret control room indications to verify the status and operation of system, and understand how operator action s and directives affect plant and system conditions.

AK2.03 Accumulator pressures.

.EK1.02 Equipment environmental qualification Page 3 ES-401-1 Imp. Pts.

3.3 1

3.3 1

3.5 1

3.6 1

3.8 1

3.7 1

3.5 1

3.5 3.5 3.1 1

1 4.1 3.8 3.4 3.1 1

]1 S1 1

iES-401 System #

295034 295035 295036 295036 600000 BWR SRO Examination Outline ES-401-1 Emergency and Abnormal Evolutions - Tier 1/Group 2 K1 1K2 K3 Al A2 G KA Topic(s)

Imp. Pts.

X 2.4.30 Knowledge of which events related to system operations/status should be reported 3.6 1

to outside agencies.

EK3.01 Emergency depressurization 2.8 X

EK2.01 Secondary containment equipment and floor drain system 3.2 1 1 Tuesday, March 26, 2002 5:39:28 PM Name Secondary Containment Ventilation High Radiation Secondary Containment High Differential Pressure Secondary Containment High Sump/Area Water Level Secondary Containment High Sump/Area Water Level Plant Fire On Site Page 4

ýES-401

ýSystem iName K1 K2 K 201005 Rod Control and Information System (RCIS) 202002 Recirculation Flow Control System 203000 IRHR/LPCI: Injection Mode (Plant X

Specific) 203000 IRHR/LPCI: Injection Mode (Plant Specific) 206000 High Pressure Coolant Injection System 207000 Isolation (Emergency) Condenser 209001 Low Pressure Core Spray System X

209001 Low Pressure Core Spray System X

209002 IHigh Pressure Core Spray System l(HPCS) 211000 IStandby Liquid Control System 212000 IReactor Protection System 215004 iSource Range Monitor (SRM) System 215004 ýSource Range Monitor (SRM) System 215005 iAverage Power Range Monitor/Local Power Range Monitor System 215005 Average Power Range Monitor/Local Power Range Monitor System 216000 iNuclear Boiler Instrumentation X

216000 Nuclear Boiler Instrumentation 217000 Reactor Core Isolation Cooling System

ý(RCIC) 217000 Reactor Core Isolation Cooling System

!(RCIC) 218000 lAutomatic Depressurization System Tuesday, March 26, 2002 5:39:39 PM BWR SRO Examination Outline Plant Systems - Tier 2/Group 1 3.K4 K 5K6 AI!A21A31A4 G KATopic(s)

SK1.14 Shutdown cooling system: Plant-Specific X

A4.07 Reactor water level X

AA1.06 System flow: BWR-2, 3, 4 K1.10 Emergency generator K2.02 Valve power X

IK5.02 Specific logic arrangements X

IA3.03 RPS status X 2.2.6 Knowledge of the process for making changes in procedures as described in the safety analysis report.

X K5.05 Core flow effects on APRM trip setpoints

_ 'K3.05 Reactor power indication

.,K2.01 Analog trip system: Plant-Specific X

IA2.08 Elevated containment temperature X

ýA2.01 System initiation signal X

-K4.05 Prevents radioactivity release to auxiliary/reactor building Page 1 ES-401-1 Imp.

Pts 3.7 1

4.5 1

3.7 1

3.8 1

2.7 1

3.4 1

3.5 1

3.3 1

3.6 1

3.8 1

2.8 1

3.4 1

3.7 1

3.5 1

[Es-401 ISystem IName 223001 Primary Containment System and Auxiliaries 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off 226001 RHR/LPCI: Containment Spray System Mode 239002 Relief/Safety Valves 241000 Reactor/Turbine Pressure Regulating System 259002 Reactor Water Level Control System 261000 Standby Gas Treatment System BWR SRO Examin Plant Systems - TiE K1 1K21K31K4*K51 K6 A1 'IA21A3 A41C X

  • X*

1x 261000 Standby Gas Treatment System 262001 A.C. Electrical Distribution 264000 !Emergency Generators (Diesel/Jet) i 290001 ISecondary Containment X

x ation Outline er 2/Group 1 SKA Topic(s)

K3.16 Shutdown cooling system/RHR K4.01 Redundancy A3.05 Containment pressure JA1I.05 Reactor water level X 2.4.32 Knowledge of operator response to loss of all annunciators.

S. K6.03 Emergency diesel generator system X

A4.07 System flow K6.01 D.C. power X 12.1.11 Knowledge of less than one hour technical specification action statements for systems.

Tuesday, March 26, 2002 5:39:40 PM ES-401-1 Imp. Pts.

3.3 1

3.2 1

4.0 1

3.8 1

3.5 1

3.1 1

3.2 1

3.4 1

3.8 1

Page 2 i 1 1 :

ES-401 BWR SRO Examina Plant Systems - Tier System Name K1 K2 K3 K4'K5 K6 Al A2 A3A4 G I 201001 Control Rod Drive Hydraulic System X

201002 Reactor Manual Control System X1 201004 Rod Sequence Control System (Plant Specific) 201006 Rod Worth Minimizer System (RWM)

X (Plant Specific) 201006 Rod Worth Minimizer System (RWM)

(Plant Specific) 202001 Recirculation System X

II 204000 {Reactor Water Cleanup System X

205000 Shutdown Cooling System (RHR Shutdown Cooling Mode) 214000 Rod Position Information System 215002 Rod Block Monitor System 215003 Intermediate Range Monitor (IRM) System 219000 IRHR/LPCI: Torus/Suppression Pool

ýCooling Mode 230000 RHR/LPCI: Torus/Suppression Pool XI Spray Mode 234000 Fuel Handling Equipment X

C 239003 MSIV Leakage Control System 245000 ýMain Turbine Generator and Auxiliary Systems 259001 Reactor Feedwater System I

262002 Uninterruptable Power Supply (A.C./D.C.)

263000 D.C. Electrical Distribution XI 2630001D.C. Electrical Distribution 1

Tuesday, March 26, 2002 5:39:40 PM Page 3 tion Outline 2/Group 2 KA Topic(s)

A3.05 Reactor water level K4.08 Continuous In rod insertion K3.01 Reactor manual control sys 2.1.12 Ability to apply technical sp K3.07 Vessel bottom head drain tE

%2.14 System high temperature ES-401-1 I-- -mp.jPts.

2.8 1

3.2 1

3.5 1

4.0 1

2.9 1

3.2 1

tem: P-Spec(Not-BWR6) ecifications for a system.

emperature (6.01 A.C. electrical 3.4 1

2.2.25 Knowledge of bases in technical specifications for limiting conditions for 3.7 1

)perations and safety limits.

42.01 Major D.C. loads 1.01 Battery charging/discharging rate 3.4 2.8 1

ES-401

ýSystem iName 271000 kOffgas System 272000 Radiation Monitoring System 286000 !Fire Protection System 290003 IControl Room HVAC 300000 Instrument Air System (IAS) 400000 IComponent Cooling Water System i(CCWS)

BWR SRO Examination Outline Plant Systems - Tier 2/Group 2 K1 K2 K3 K4IK5 K6,AI A2IA3 A4 G KATopic(s)

X K1.02 Process radiation monitoring system X

K6.03 A.C. power X

K5.01 Airborne contamination (e.g., radiological, toxic gas, smoke) control Tuesday, March 26, 2002 5:39:40 PM ES-401 -1 Imp. Pts.

3.3 1

3.0 1

3.5 1

Page 4

ES-401 System IName 201003 Control Rod and Drive Mechanism 215001 Traversing In-Core Probe 233000 Fuel Pool Cooling and Clean-up 239001 Main and Reheat Steam System 256000 Reactor Condensate System 268000 Radwaste 288000 Plant Ventilation Systems 290002 Reactor Vessel Internals BWR SRO Examination Outline ES-401-1 Plant Systems - Tier 2/Group 3 K1 K2 K3lK4 K5:K6 A1 A21A3lA4 G KATopic(s)

Imp. Pts.

X K4.05 Rod position indication 3.3 1

X K1.05 Primary containment isolation system: (Not-BWR1) 3.4 1

X 2.1.7 Ability to evaluate plant performance and make operational judgments 4.4 1

based on operating characteristics, reactor behavior, and instrument interpretation.

"r X Al.01 Radiation level 3.1 1

a3 Tuesday, March 26, 2002 5:39:41 PM Page 5

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

ES-401-5 Facility: Hope Creek Date of Exam 03/12/2002 Exam Level: SRO Category KA#

Topic Imp.

oints

,Conduct of Operations 2.1.14 Knowledge of system status criteria which require the notification of 3.3 1

plant personnel.

2.1.3 Knowledge of shift turnover practices.

3.4 1

2.1.33 Ability to recognize indications for system operating parameters which 4.0 1

are entry-level conditions for technical specifications.

2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

3.1 1

2.1.34 Ability to maintain primary and secondary plant chemistry within 2.9 1

allowable limits.

'Total 5

Equipment Control

2.2.26
Knowledge of refueling administrative requirements.

3.7 1

12.2.31 Knowledge of SRO fuel handling responsibilities.

3.8 1

2.2.27 Knowledge of the refueling process.

3.5 1

2.2.22

!Knowledge of limiting conditions for operations and safety limits.

4.1 1

Total 4

ýRadiological Controls f22.3.1 Knowledge of 10 CFR 20 and related facility radiation control 3.0 1

.requirements.

2.3.10 Ability to perform procedures to reduce excessive levels of radiation 3.3 1

and guard against personnel exposure.

2.3.4 Knowledge of radiation exposure limits and contamination control, 3.1 1

including permissible levels in excess of those authorized.

2.3.11 Ability to control radiation releases.

3.2 1

Total 4

Emergency Procedures 12.4.34

Knowledge of RO tasks performed outside the main control room during 3.6 1

and Plan emergency operations including system geography and system 2.4.18 Knowledge of the specific bases for EOPs.

3.6 1

2.4.28 Knowledge of procedures relating to emergency response to sabotage.

3.3 1

2.4.5

Knowledge of the organization of the operating procedures network for 3.6 1

normal, abnormal, and emergency evolutions.

Total 4

Tier 3 Target Point Total (RO/SRO) 17 Tuesday, March 26, 2002 5:39:48 PM

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