ML031830298

Final - Outlines (Change Summaries - Optional)

ML031830298
Person / Time
Site:	Seabrook
Issue date:	06/05/2003
From:	Roy D Florida Power & Light Energy Seabrook
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-443/OL-03-301 50-443/OL-03-301
Download: ML031830298 (30)

Text

ES401 Written Examination Form ES-401-9 Review Worksheet

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other Y LOK LOD (FIH)

(1-5)

Stem Cues T/F Cred. Partial Job-Minutia #/

Back-Q= SRO Focus Dist.

Link units ward WA Only 1

2 3

X 4

X 5

6 X

7 8

9 10

6.

7.

U/E/S Explanation S

S U

condition in stem made correct answer incorrect; modified condition stated answer was incorrect; further info brought by licensee inoorporated into w m c t answer editing to make answer more clear

'D distractor too close to being correct answer; rewrote distractor.

S U

S S

S S

7.

At a minimum, explain any 'U" ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2

Form ES-401-9

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

Q#

LOK LOD (F/H)

(1-5)

Stem Cues T/F Cred. Partial Job-Minutia #/

Back-Q= SRO U/E/S Focus Dist.

Link units ward WA Only 11 S

12 S

13 S

14 S

15 S

16 S

17 S

18 S

19 X

U 20 S

21 S

22 S

23 S

24 S

25 S

26 S

27 X

U 28 S

29 S

30 S

7.

Explanation editing; comcted editorial; comcted.

editorial; comcted.

editorial: comcted question did not reflect realistic situation; question replaced.

distractor too close to right answer (minutia related); distractorchanged 45 of 46 NUREG-1021, Revision 8, Supplement I

ES-401 2

Form ES-401-9 Q#

31

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

LOK LOD (FM) (1-5)

Stem Cues T/F Cred. Partial Job-Minutia #I Back-Q= SRO UWS Explanation Focus Dist.

Link S

~

32 33 34 35 36 37 38 39 S

initial conditions modified for clarity 40 S

41 S

~~~~~

~~

~

S S

X U

distractor D could be correct sometimes; changed distractor S

S procedures have been revised such that question is no longer relavent t

~~

~~~~

X job function; question replaced.

S 42 43 S

S I

I 49 S

added initial condition for clarity I

I I

I I I I I I I

I s

44 45 46 47 48 50 I I

I I

I I

I I

I I

I I

I I s 1 X

U low operational validity; replaced with better question distractor B could be correct in some situations, made initia/ conditions mom restrictive to make distractor always wrong distractor C was not completely incorrect; distractor was changed.

X X

U S

S editorial; comcted.

45 of 46 NUREG-1021, Revision 8, Supplement 1

ES-401 2

Form ES-401-9 45 of 46 NUREG-1021, Revision 8, Supplement 1

ES-401 2

Form ES-401-9

1.

Q# LOK (FM) 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90

~~

~~~

~

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

LOD (1-5) Stem Cues T/F Cred. Partial Job-Minutia #I Back-Q= SRO U/WS Explanation Focus Dist.

Link units ward WA Only S

S S

answers required detailed knowledge of procedure steps; refocused answer on broader topic.

X S

editing; corrected edits S

S D distractor unclear; rewonled D distractor distracton were requiring memorization of MCC loads; distractom rewritten at a broader level X

S U

S S

S S

S S

X Distractor D could be construed as correct; rewrote distractor distractor D was correct answer; restnrctured initid conditions to make D immct.

distractor C was too close to correct answer; changed distractor X

X U

S S

45 of 46 NUREG-1021, Revision 8, Supplement 1

ES-401 2

Form ES-401-9 45 of 46 NUREG-1 021, Revision 8, Supplement 1

ES-401 2

Form ES-401-9 45 of 46

~~~

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~

NUREG-1 021, Revision 8, Supplement 1

ES-401 Record of Rejected WAS Form ES-40 1-1 0 Tier I Group 211 I

I1 111 3

3 (RO) 111 211 3

112 112 211 213 211 212 112 211 3

~~

Randomly Selected WA 001 K6.09 067AK1.Ol 076AA1.04 2.1.24 2.4.1 5 026AK3.0 1 071A3.03 2.3.10 060 2.4.39 O6IAKI -01 072A1.01 034K6.02 068k4.01 01 I K5.12 029EK1.03 004A2.27 2.1.21 Reason for Rejection NR-45 not used at Seabrook; replaced with 001 K6.03 Discriminatory question for fire classification that is operationally valid was not possible; replaced with 067AK1.02 Discriminatory and operationally valid question not possible; replaced with 076AK3.05 Sampled on operating test; replaced with 2.1.I 1

Not applicable to Ros at Seabrook; replaced with 2.4.21 NIA at Seabrook; replaced with 026AK3.02 WA oversampled; replaced with 071A3.02 Topic oversampled; replaced with 2.3.1 No eplan responsibilities for RO wrt gas radwaste; replaced with 060 2.1.I 1

Radiation detector limitations topic is non discriminatory; replaced with 061AA2.05 Non-discriminatory topic; replaced with 072A3.01 Topic oversampled on written exam; replaced with 034K4.01 No discriminatory value; replaced with 068A2.04 No discriminatory value: replaced with 01 I K5.15 No discriminatory value ineffects of boration on reactivity during ATWS; replaced with EA2.01 No operational validity with improper RWST boron concentration; replaced with A2.18 Sampled on operations exam; replaced with 2.1.1 NUREG-I 021, Revision 8, Supplement 1 46 of 46

ES-401 Record of Rejected WAS Form ES-401-10 Tier I Group 212 111 Randomly Selected WA 103A4.04 1 511 7AK3.07 Reason for Rejection WA rejected to provide for SRO level discriminatory question; replaced with 103A1.01.

WA was incorrectly transferred from RO outline; corrected back to 15/17 2.1.7 NUREG-I 021, Revision 8, Supplement 1 46 of 46

ES-401 PWR SRO Examination Outline Form ES-401-3 3317033777 Facilitv:

Seabrook Date of Exam:

05/30/2003 Exam Level: SRO

~~~

~

~ Note:

1.

2.

Ensure that at least two topics from every WA category are sampled within each tier 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 exam must total 100 points.

Select topics from many systems; avoid selecting more than two or three WA topics from a given system 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 WAS in Tiers I and 2 shall be selected from Section 2 of the WA 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 SRO license level, and the point totals for each system and category. WAS below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

I (i.e., the "Tier Totals" in each WA category shall not be less than two).

3.

4.

5.

6."

7.

Abnormal Plant I T o t a l s I I

I I

I I

I I

I I

I I

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat4 4

4 4

5 17 NUREG-I 021, Revision 8, Supplement 1 26 of 46

Emergency and Abnormal Plant Evolutions -Tier 1IGroup 1 I

I I

I I

I EIAPE # I Name I Safety Function 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod I 1 000005 InoperableIStuck Control Rod / 1 00001 1 Large Break LOCA / 3 W/E04 LOCA Outside Containment I 3 K1 X

X 000029 Anticipated Transient w/o Scram I 1 000040 (BWIEO5 CEIEO5. W/E12) Steam Line Rupture - Excesshe Heat transfer I 4 CEIAI 1; WIE08 RCS Overcooling - PTS I 4 X

000067 Plant Fire On-site I 9 X

WA Topic(s)

AK2.08 Individual rod display lights and indications AA1.01 Demand position counter and pulselanalog converter AKI.05 Calculation of minimum shutdown margin EKI.01 Natural circulation and cooling, including reflux boiling.

Imp.

3.0 2.9 4.1 4.4 3.9 Points 1

1 1

X EK2.1 Components, and functions of control and safety systems, includin instrumentation, signals, interlocks, failure modes, and automaic and manual features.

EA1.I Components, and functions of control and safety systems, includin instrumentation, signals, interlocks, failure modes, and automa& and manual features.

2.1.7 Abilit to evaluate plant performance and make o erational jud mentsiased on operating characteristics, reactor Eehavior, and insEument interoretation.

3.7 1

WIEOI & E02 Rediagnosis & SI Termination I 3 000015/17 RCP Malfunctions I 4 BWIE09; CEIA13; WIE09&El0 Natural Circ. I 4 X

7 4.2 1

3.8 I

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

000024 Emergency Boration I 1 I

AA1.I7 Emergency borate control valve and indicators AK3.02 PCCW responses to an ESFAS signal.

EA2.01 Reactor nuclear instrumentation 3.9 3.5 4.7 3.8 000026 Loss of Component Cooling Water I 8 I

1 1

EK1.2. Normal, abnormal and emergency o erating rocedures associated with (Uncontrolled Depressurizagon of alfSteam Generators).

EK2.1 Components, and functions of control and safety systems, includin instrumentation, signals, interlocks, failure modes, and autornaic and manual features.

1 3.7 3.1 4.5 3.9 3.9 1

000051 Loss of Condenser Vacuum I 4 000055 Station Blackout I 6 000057 Loss of Vital AC Elec. Inst. Bus I 6 000059 Accidental Liquid RadWaste Rel. I 9 AK3.01 Loss of steam dump capability upon loss of condenser vacuum EA1.07 Restoration of power from offsite AA2.20 Interlocks in effect on loss of ac vita1,electrical instlument bus that must be bypassed to restore normal equipment operation AA2.05 The occurrence of automatic safety actions as a result of a high PRM system signal I

000062 Loss of Nuclear Service Water I 4 3.9 2.5 2

2.4.12 Knowledge,of general operating crew responsibilities during emer ency operations.

AA2.85 normal values for SWS-header flow rate and the flow rates to the components cooled by the SWS 1

AKI.02 Fire Fiqhtina 3.9

\\

000069 (WIE14) Loss of CTMT Integrity I 5 000074 (W/E06&E07) Inad. Core Cooling I4 000076 High Reactor Coolant Activity I 9 X

X X

X I

I I

I I

WA Category Totals:

1 5 1 4 1 4 1 4 1 5 EK2.2 Facilitys heat removal s stems, including primary coolant, emergenc coolant, the decay xeat removal systems, and relations between txe proper operation of these systems to the operation of the facilitv.

11 3.8 1

EK3.3 Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

EKI.2 Normal abnormal and emergency operating procedures associated with (Degraded Core Cooling).

3.9 2

4.1 2

AK3.05 Corrective Actions as a result of high fission product radioactivity in the RCS Group Point Total:

24 3.6 1

ES-401 X

E/APE #I Name I Safety Function 000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA I 3

BWIE08; WIE03 LOCA Cooldown - Depress. I 4 WIE11 Loss of Emergency Coolant Recirc. I 4 EK2.1 Com onents, and functions of control and safety systems, 3.3 1

includin insyrumentation, signals, interlocks, failure modes, and automa8c and manual features.

000022 Loss of Reactor Coolant Makeup I 2 000025 Loss of RHR System I 4 000027 Pressurizer Pressure Control System Malfunction I 3 000032 Loss of Source Range NI I 7 000033 Loss of Intermediate Range NI I 7 1

000037 Steam Generator Tube Leak I 3 000038 Steam Generator Tube Rupture I 3

BWIE04; WIE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 000058 Loss of DC Power I 6 000060 Accidental Gaseous Radwaste Rel. I 9 000061 ARM System Alarms I 7 W/EI6 High Containment Radiation I 9 2.8 1

X AA1.02 Components served by instrument air to minimize drain on system 16 4

2 2

3 4

Group Point Total:

000065 Loss of Instrument Air I 8 WA Category Point Totals:

Form ES-401-3 PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 1

1 1

1 1

1 I

I NUREG-I 021, Revision 8, Supplement 1 28 of 46

ES-401 1

1 EIAPE # I Name I Safety Function 000028 Pressurizer Level Malfunction I 2 000056 Loss of Off-site Power I6 WIEI 3 Steam Generator Over-pressure I4 1

Group Point Total:

3 WIE15 Containment Flooding I 5 KIA Category Point Totals:

29 of 46 NUREG-1021, Revision 8, Supplement 1

PWR SRO Examination Outline Plant Systems - Tier 2/Group 1 ES-401 System # I Name K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G

WA Topic(s) 001 Control Rod Drive 003 Reactor Coolant Pump X

X K1.10 knowledge of the cause-effect X

K5.54 Definition and units of reactivity relationship blw the RCPS and the RCS 2.1.27 Knowledge of system purpose and or function.

004 Chemical and Volume Control X

A2.18 High VCT level.

013 Engineered Safety Features Actuation X

A3.01 Input channels and logic 014 Rod Position Indication X

K3.02 Plant computer 015 Nuclear Instrumentation X

A2.02 Faulty or erratic operation of detectors or compensating components function of major system components and controls.

K4.02 Correlation of fan s eed and flow-path changes with containmenrpressure 017 In-core Temperature Monitor X

2.1 -28 Knowledge of the purpose and 022 Containment Cooling X

026 Containment Spray X

A4.01 CSS controls 056 Condensate X

X K1 Knowledge of the hysica! connections and/or cause-effect rektionships between the Condensate s stem and the following systems: K1.03 M!W A2.04 Loss of condensate pumps A I.07 Feed Pump s eed including normal control speed for StWL6.

malfunction of the ANV will have on the following: K3.02 SIG 059 Main Feedwater X

X K3.04 RCS 061 AuxiliarylEmergency Feedwater X

K3 Knowledge of the effect that a loss or 063 DC Electrical Distribution X

KI.02 AC electrical system 068 Liquid Radwaste 071 Waste Gas Disposal X

A3.02 pressure-regulating system for WG 072 Area Radiation Monitoring X

A3.01 changes in ventilation lineup X

K5.04. Biological hazards of radiation and the resulting goal of ALARA header WA Category Point Totals:

3 0

3 I

2 0

1 3

3 1

2 Group PointTotal:

NUREG-1021, Revision 8, Supplement 1 30 of 46 Form ES-401-3 Imp.

Points 3.1 1

3.2 2

2.9 3.1 1

3.9 1

2.8 1

3.5 1

3.3 1

3.4 1

4.3 1

2.6 2

2.8 3.8 2

2.6 4.4 1

3.2 1

3.5 1

3.8 1

3.1 1

19

ES-401 PWR SRO EXE Plant Systems 029 Containment Purge II I

I I

I I

I I

11 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 039 Main and Reheat Steam 055 Condenser Air Removal X

062 AC Electrical Distribution K/A Category Point Totals:

1 1

1 1

1 2

2 nination Outline Form ES-401-3 Imp.

Points A2 A3 A4 G

KIA Topic@)

X A2.03 Loss of forced circulation 4.3 1

A I,14 Reactor vessel level 3.9 1

K6.02 PZR 3.5 1

I I

I I

I I

I I

1 K1.06 AFW system 3.5 1

I I

I I

I I

K5.01 Purpose of charcoal filters 3.4 1

3 2

2 1

Group Point Total:

17 31 of 46 NUREG-1021, Revision 8, Supplement 1

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Date of Examination: 6/02/03-6/06/03 Operating Test No.:

Facility: Seabrook Station Exam Level (circle one): RO / SRO(I) / SRO(U) 11 B.1 Control Room Systems System / JPM Title II Type Code*

Safety Function 1

a. 001 Control Rod Drive / 1/M Plot performance. Identify that the reactor goes critical below -500 pcm value.

b. 006 ECCS / Transfer SI to Cold Leg Recirculation (CBS-VI4 fails)

(SRO-U)

/I 2

c. 010 Primary Pressure Control System / Depressurize the RCS during a natural circulation cooldown with letdown unavailable IAW ES-0.2.

(SRO-U) 6

d. 062 AC Electrical distribution I Loss of All AC Power; failure of EDG output breaker and charging pump auto start.

e. 028 Hydrogen Recombiners / Start hydrogen recombiners.

(SRO-U)

/I D, S 5

f. 012 RPS Power Range NI Failure ll 7

4(sec)

L

g. 076 Service Water System / Transfer Service Water to the Cooling Tower 11 8.2 Facility Walk-Through

a. 005 RHR / Manual Operation of RHR TCV for mid-loop operations.

(SRO-U)

b. 064 EDG / Local EDG Normal Start and Load 11 (SR0-U)

c. 061 EFW/ Reset the TDEFW pump turbine trip throttle valve.

ll

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

ES-301 Administrative ToDics Outline Form ES-301-1 escription Loss of RHR Cooling SDM Calculation Review Facility: Seabrook Station Examination Level: SRO Administrative Topic/Subject A. 1 A.2 A. 3 A.4 Tagouts Radiation control Emergency Classification, Notifications, and PAR.

JPM Date of Examination:

Operating Test Number:

Describe method of evaluation:

1. ONE Administrative JPM, OR

2. TWO Administrative Questions 2.1 2 5 Ability to obtain and interpret station reference materials such as as graphs, monographs, and tables which contain performance data. SRO: 3.1.

JPM: Evaluate loss of cooling conditions and determine time to boilina from chart.

2.1.25 Ability to obtain and interpret station reference materials such as as graphs, monographs, and tables which contain performance data. SRO: 3.1.

JPM: Review a SDM calculation for Natural Circulation Cooldown.

2.2.13 Knowledge of tagging and clearance procedures. SRO:

3.8.

JPM: Review a tagout request.

2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. SRO: 3.1 JPM: Contaminated iniured man actions.

~~~

2.4.38 Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator. SRO: 4.0 JPM: Given a set of conditions, the applicant will make an EAL determination, PAR, and make required notifications.

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Seabrook Station Exam Level (circle one): RO / SRO(1) / SRO(U)

Date of Examination: 6/02/03-6/06/03 Operating Test No.:

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

Safety Function II I

a. 001 Control Rod Drive / 1/M Plot performance. Identify that the reactor goes critical below -500 pcm value.

b. 006 ECCS / Transfer SI to Cold Leg Recirculation (CBS-V14 fails)

(SRO-U)

(I 2

3

c. 010 Primary Pressure Control System / Depressurize the RCS during a natural circulation cooldown with letdown unavailable IAW ES-0.2.

(SRO-U) 6

d. 062 AC Electrical distribution / Loss of All AC Power; failure of EPS on shutting EDG output breaker.

5

e. 028 Hydrogen Recombiners I Start hydrogen recombiners.

(SRO-U)

f. 012 RPS Power Range NI Failure

g. 076 Service Water System / Transfer Service Water to the Cooling Tower B.2 Facility Walk-Through 7

4(sec)

a. 005 RHR I Manual Operation of RHR TCV for mid-loop operations. r (SRO-U)

D 6

b. 064 EDG I Local EDG Normal Start and Load

/I (SR0-U)

D 4(sec)

c. 061 EFWI Reset the TDEFW pump turbine trip throttle valve.

II

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

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

F o

~

ES401-5 Topic Knowledge of operator responsibilities during all modes of plant operation.

license.

Knowledge of less-than-1 -hour technical specification statements for svstems Knowledge of conditions and limitations in the facility sabrook KIA #

2.1.2 Imp.

4.0 3.9 3.8 2.1.10 2.2.1 2 2.2.25 2.1.1 1

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Knowledge of surveillance procedures.

3.4 1

Knowledge of bases in technical specifications for limiting 3.7 1

conditions for operations and safety limits.

2.1.4 2.2.1 1 Total Knowledge of the process for controlling temporary 3.4 1

changes.

2.3.2 2.3.4 2.3.1 0

2.3.1 Level

SRO Knowledge of facility A U R A program.

Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

Knowledge of 10 CFR: 20 and related facility radiation control requirements.

Points 1

2.4.1 2.4.1 0 2.4.1 5 1

Knowledge of EOP entry conditions and immediate action steps.

Knowledge of annunciator response procedures.

Knowledge of communications procedures associated with EOP implementation.

1 2.4.2 2.4.1 1 Knowledge of shift staffing requirements.

3.4 1

I Knowledge of system set points, interlocks and automatic 4.1 1

Knowledge of abnormal condition procedures.

3.6 1

actions associated with EOP entry conditions.

Total 5

Facility:

Category Conduct of Operations Equipment Control Radiation Control Emergency Procedures1 Plan NUREG-1021, Revision 8, Supplement 1 40 of 46 I

3.8 1 1 I

a

+

3.0 14 4.6 I 1

ES-401 PWR RO Examination Outline Form ES-401-4 1

2 3

Tier Totals

2.

Plant Systems 2

2 2

1 2

2 2

3 3

2 2

23 2

2 2

2 1

2 2

2 2

2 1

20 1

1 0

1 1

0 1

1 1

1 0

8 5

5 4

4 4

4 5

6 6

5 3

51 33 of 46 NUREG-1021, Revision 8, Supplement I

3. Generic Knowledge and Abilities Cat 1 Cat2 Cat 3 3

3 3

Cat4 4

13

Form ES-401 PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1IGroup 1 EIAPE #I Name / Safety Function K1 K2 K3 A1 A2 G

WA Topic(@

Imp.

000005 Inoperable/Stuck Control Rod / 1 X

AKl.05 Calculation of minimum shutdown margin 3.3 00001 5/17 RCP Malfunctions I 4

X 2.1.7 Abili to evaluate plant performance and make o rational 3.7 jud mentsgased on operating characteristics, reactor ghavior, and insfrument interpretation.

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

BW/EO9; CE/A13; WIE09&E10 Natural Circ. I 4

X 3.1 000024 Emergency Boration I 1 X

AA1.17 Emergency borate control valve and indicators 3.9 000026 Loss of Component Cooling Water I 8

000027 Pressurizer Pressure Control System X

AK2.03 Controllers and positioners Malfunction I 3 Rupture - Excesshe Heat fransfer I 4

X AK3.02 PCCW responses to an ESFAS signal.

3.2 2.6 000040 (BWIE05' CE/EO5' W/E12) Steam Line X

EK1.2 Normal, abnormal and emergency o erating rocedures 3.5 CE/All; WIE08 RCS Overcooling - PTS / 4 associated with (Uncontrolled Depressurirabon of alpsteam Generators).

X EK2.1 Components and functions of control and safety systems, 3.4 includin instrumenthion, signals, interlocks, failure modes, and automalc and manual features.

000051 Loss of Condenser Vacuum I 4 X

AA2.01 cause for low vacuum condition 2.7 000055 Station Blackout I 6 X

EA1.07 Restoration of power from offsite 4.3 3.6 000057 Loss of Vital AC Elec. Inst. Bus I 6 000062 Loss of Nuclear Service Water I 4 000067 Plant Fire On-site I 9

X AKl.02 Fire Fighting X

AA2.20 Interlocks in effect on loss of ac vital electrical instrument bus that must be bypassed to restore normal equipment operation emergency operations.

X 2.4.12 Knowledge,of general operating crew responsibilities during 3.4 3.1 3.4 000069 (WIE14) Loss of CTMT Integrity I 5 X

EK2.2 Facility's heat removal s stems, including primary coolant, emergen betyeen %e propei operation of these systems to the operation of the facility.

EK3.3 Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

AK3.05 Corrective Actions as a result of high fission product radioactivity in the RCS coolant the decay {eat removal systems, and relations 000074 (WIE06LE07) Inad. Core Cooling I 4 000076 High Reactor Coolant Activity I 9

K/A Category Totals:

3 3

4 2

2 2

Group Point Total:

X X

4.0 2.9 NUREG-1021, Revision 8, Supplement 1 34 of 46 ES-401-4 Points 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 16

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions -Tier 1IGroup 2 A 2 G E/APE #I Name I Safety Function I K1 I K2 I K3 I A1 I

I I

I WA Topic@)

Imp.

Points I

I I

I 000003 Dropped Control Rod I 1

000008 Pressurizer Vapor Space Accident I 3

000009 Small Break LOCA I 3 X

X X

AA1.01 Demand position counter and pulseIanalog converter AK3.03 Actions contained in EOP for PZR vapor space accident/ LOCA 2.9 1

4.1 1

I "

WIEO1 & E02 Rediagnosis & SI Termination I 3 EK2 Knowled e of the interrelations between the small break LOCA and the following: l!K2.03 SIGs WE16 High Containment Radiation I S I

3.0 1

00001 1 Large Break LOCA I 3

WIE04 LOCA Outside Containment I 3 X

X EK2.1 Cgm onents and functions of control nd safety systems, includin insfrumenthtion, signals, interlocks, &lure modes, and automa& and manual features.

3.5 1

I I

I I

ll I EK1.01 Natural circulation and cooling, including reflux boiling.

I 4.1 I 1 WIEl 1 Loss of Emergency Coolant Recirc. I 4

~

~

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X EK3.3 Manipulation of controls required to obtain desired operating results dunng abnormal, and emergency situations.

3.8 1

I 1

I 1

I EAl.1 Com onents and functions of control and safety systems, includin insfrumenthtion, signals, interlocks, failure modes, and automa& and manual features.

3.7 1

X X

AA2.02 Charging pump problems 3.2 1

2.9 1

2.1.12 Ability to apply technical specifications for a system.

EA2.01 Reactor nuclear instrumentation 4.4 1

AK2.01 Power supplies, including proper switch positions 2.7 1

X 4 I 2 I Group Point Total:

I 17 EK3.05 Normal operating precautions to preclude or minimize SGTR EA1.2 Operating behavior characteristics of the facili.

35 of 46 NUREG-1021, Revision 8, Supplement 1 4.0 1

3.7 1

X AA2.05 The occurrence of automatic safety actions as a result of a high PRM system signal 3.6 1

X X

2.1.1 1 Knowledge of conduct of operations requirements.

3.0 1

3.5 1

AA2.05 Need for area evacuation; check against existing limits EK2.1 Corn onents and functions of control and safety systems, includin inshnentbti n si nals, interlocks, failure modes, and automah and manual8ebtuyes.

3.0 1

WA Category Point Totals:

1 4

3 3

ES-401 WAPE #I Name I Safety Function KI 000028 Pressurizer Level Malfunction I 2 000056 Loss of Off-site Power I 6 000065 Loss of Instrument Air I 8

WIE13 Steam Generator Over-pressure I 4 WIEl5 Containment Flooding I 5 X

WA Category Point Totals:

1 PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1IGroup 3 Form ES-401-4 K2 K3 A I A2 G

WA Topic@)

imp.

Points X

AK2.02 Sensors and detectors 2.6 1

X EAl.1 Corn onents, and functions of control and safety systems, 3.1 1

includin insfrumentation, signals, interlocks, failure modes, and automalc and manual features.

EK1.l Components, capacity, and function of emergency systems.

2.8 1

1 1

1 Group Point Total:

3 NUREG-1021, Revision 8, Supplement 1 36 of 46

ES-401 001 Control Rod Drive 003 Reactor Coolant Pump K5.54 Definition and units of reactivity K6.03 Reactor Trip Breakers, including controls.

004 Chemical and Volume Control 2.8 2

3.7 013 Engineered Safety Features Actuation 015 Nuclear Instrumentation 017 In-core Temperature Monitor AI.02 RCP pump and motor bearing tern ratures 2.1.E Knowledge of system purpose and or function.

022 Containment Cooling I

2..9 2

2.8 056 Condensate K2 Knowledge of bus power supplies to the followin : K2.05 MOVs A2.18 8 igh VCT level.

X 2.7 2

3.1 059 Main Feedwater A3.01 Input channels and logic A403 Trip bypasses 061 Auxiliary/Emergency Feedwater 3.7 1

3.0 1

P PI X

X 3.0 3.1 2.6 2.6 Examination Outline ems - Tier 2/Group 1 X

2 2

Form ES-401-4 K3 Knowled e of the effeqt that a loss or malfunction !f the MRN will have on the followin : K3.04 RCS A1.07 peed Pump speed. including normal I

I 3.6 2

2.5 WA Topic(@

I Imp. I Points I

I A4.02 Tern erature values used to determine 8CSIRCP omration durina inadequate &re cooling (i.e., if appli&ble, avera e of five highest values) 2.1.2fKnowledge of the purpose and function of major system components and controls.

K2.01 Containment cooling fans K4.02 Neutralized boric acid to reduce corrosion and remove inor anic fisqion product iodine from steamgNAOH) in containment spray K1 Knowledge of the hysical connections and/or cause-effect regtionships between the Condensate s stem and the following systems: K1.03 NihrJ A2 Ability to a) predict the impacts of the following malkmctions or o rations on the Condensate System; and &based on those predictions use r d u r e s to correct, control, or miti afe the consequences of those malfi.k!ons or operations: A2.04 Loss of condensate pumps control speed for'lCS I

I K6 Knowledae of the effect of a loss or I 2.6 I 2 I 4.2 I malfunction ?if the followin will have on the ARN components:K6.02 Bumps K3 Knowledae of the effect that a loss or m-aliiin-&n-~f the-A-m wiil -have followina: K3.02 SIG I

I

068 Liquid Radwaste Kl.06 ARM and PRM systems A3.02 pressure-regulating system for waste gas vent header.

071 Waste Gas Disposal 3.1 2

2.8 072 Area Radiation Monitoring I

I A3.01 changes in ventilation alignment KIA Category Point Totals:

2 2.9 1

A2.04 failure of automatic isolation.

K5.04. Biological hazards of radiation and the resulting goal of AIARA I 1:: I II Group Point Total:

23 37 of 46 NUREG-I 021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Plant Systems - Tier 2/Group System # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 002 Reactor Coolant X

006 Emergency Core Cooling X

010 Pressurizer Pressure Control X

01 1 Pressurizer Level Control 012 Reactor Protection X

014 Rod Position Indication X

01 6 Non-nuclear Instrumentation X

X 026 Containment Spray 029 Containment Purge 033 Spent Fuel Pool Cooling 035 Steam Generator 039 Main and Reheat Steam 055 Condenser Air Removal X

062 AC Electrical Distribution X

X X

063 DC Electrical Distribution X

064 Emergency Diesel Generator X

073 Process Radiation Monitoring X

075 Circulating Water X

079 Station Air X

086 Fire Protection X

WA Category Point Totals:

2 2

2 2

1 2

2 2

2 NUREG-1021, Revision 8, Supplement 1 38 of 46 Form ES-4014 2

A4 G

WA Topic(s)

Imp.

Points A2.03 Loss of forced circulation 4.1 1

A1.14 Reactor vessel level 3.5 I

K6.02 PZR 3.2 I

3.6 1

K5.15 PZR level indication when RCS is saturated.

K4.07 First-out indication 3.0 1

2.5 1

K3.02 Plant computer K1.06 AFW system 3.6 1

X A4.01 CSS controls 4.5 I

X 2.4.31 Knowledge of annunciators alarms 3.3 I

and indications, and use of the response instructions.

A3.02 Spent fuel leak or rupture 2.9 1

X A4.06 S/G isolation on steam leak or tube 4.5 I

rupturelleak A2.04 Malfunctioning steam dump 3.4 1

2.5 1

K3.01 Main condenser K4.07 One-line diagram of 4kV to 480V 2.7 1

distribution, including sources of normal and alternative power K1.02 AC electrical system 2.7 1

2.7 1

K6.07 Air receivers A1.Ol Radiation levels 3.2 1

K2.03 Emergency/essential SWS pumps 2.6 1

2.9 1

A2.01 Crossconnection with IAS A3.02 Actuation of the FPS 2.9 1

2 1

Group Point Total:

20

ES-401 PWR RO Examination Outline Form ES-401-4 I

1 078 Instrument Air X

A3.01 Air pressure 3.1 1

WA Category Point Totals:

I 1

0 1

I 0

1 1

1 1

0 Group PointTotal:

8 Plant-Specific Priorities System / Topic

~

~~

Recommended Replacement for...

Reason Points

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

Form ES-401-5 Seabrook Date of Exam:

06/02/03 Exam Level: RC I

I I

KIA #

Topic Imp.

Points 2.1.2 Knowledge of operator responsibilities during all 3.0 1

modes of plant operation.

2.1.I Knowledge of conduct of operations 3.7 1

2.1.1 1 Knowledge of less than one-hour technical 3.0 1

requirements.

seecification action statement for svstems.

I 2.2.12 I Knowledge of surveillance procedures.

I 3.0 I

1 2.2. 25 2.2.1 1 Total 2.3.2 2.3.4 2.3.1 Knowledge of bases in technical specifications 2.5 1

for limiting conditions foroperations and safety limits.

Knowledge of shift turnover practices.

2.5 1

Knowledge of facility ALARA program.

2.5 1

Knowledge of radiation exposure limits and 2.5 1

3 contamination control, including permissible levels in excess of those authorized.

radiation control requirements.

Knowledge of 1 OCFR20 and related facility 2.6 1

Total 2.4.1 Knowledge of EOP entry conditions and immediate action stet>s.

2.4.10 Knowledge of annunciator response 2.4.21 2.4.2 procedures.

Knowledge of the parameters and logic used to assess the status of safety functions.

Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

1 3

1 4*3 I 3.0 I 1

Total 1

4