L-03-302, Final - Outlines (Change Summaries - Optional)

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Final - Outlines (Change Summaries - Optional)
ML032650906
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/13/2003
From: Reid J
Public Service Enterprise Group
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-354/OL-03-302
Download: ML032650906 (30)
v • d • e


Text

NC.TQ-WB.ZZ-0027(2)

ES-301 Administrative ToDics Outline FORM ES-301-1 FaciIity: Hope Creek Generating Station Date of Examination: 6/16/03 Examination Level: RO 0 SRO Operating Test Number: V Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. 1 Conduct of 2.1 . I 2 Ability to apply technical specifications to a system. (2.9) 0perat ions JPM- Gather information and determines if conditions are Plant Parameter satisfactory for a Recirculation Pump restart. (New)

Verification (SimuIator Perform) 2.1.31 Ability to locate control room switches/controls and indications and to determine that they are correctly reflecting the desired plant lineup. (4.2)

System Lineup JPM - RHR System Piping and Flow Path Verification (Simulator Perform) (07/02 NRC Exam)

A.2 Equipment Control 2.2.1 2 Knowledge of surveillance procedures. (3.0)

SurveiIIance JPM- Perform alternate determination of Drywell Air Procedures Temperature. (Simulator Perform) (03/02 NRC)

A.3 Radiation Control 2.3.9 Knowledge of the process for performing a containment purge. (2.5)

JPM - Complete containment purge paperwork. (Bank)

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

Communications JPM- Complete the Operational Status Board-Hope Creek (Simulator Perform) (03/02 NRC Modified)

Page 29 of 104 Rev. 2

NC.TQ-WB.ZZ-0027(2)

ES-301 Administrative Topics Outline FORM ES-301-1 Facility: Hope Creek Generating Station Date of Examination: 6116/03 Examination Level: 0 RO SRO Operating Test Number: 1 Ad ministrative Describe method of evaluation:

Topic/Subject I.ONE Administrative JPM, OR Description 2. TWO Administrative Questions 4.1 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, what is the highest recommended Plant Parameter OOKI 07 discharge pressure that gives reasonable Verification assurance of avoiding surge. (New) 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data.

(2-8)

Question- Given plant conditions, determine the Reactor Temperature at which a HPCl high RPV Level 8 Trip occurs durina a Reactor cooldown. (New) 2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities. (3.4)

Shift Manning JPM- Determine if minimum shift manning requirements are met.

(3103 LSRO)

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

SurveiIlance JPM- Perform a review of a completed surveillance. (Modified)

Procedures A.3 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. (3.0)

Question- Given an emergency condition, determine allowable stay times. (Bank) 2.3.1 Knowledge of IOCFR20 and related facility radiation control requirements. (3.0)

Question- Apply the NBU radiation exposure limits for a Declared Pregnant Worker with existing exposure. (Bank)

A.4 Emergency Plan 2.4.38 Ability to take actions called for in the facility emergency Emergency Act ion plan/including (if required) supporting or acting as Levels and emergency coordinator. (4.0)

Classifications JPM - Given a set of conditions, classify an event. (Bank)

Page 29 of 104 Rev. 2

NC.TQ-WB.ZZ-OOZII(2)

ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2 Facility: Hope Creek Generating Station Date of Examination: 6116/03 Examinations Developed by: [XI Facility 0 NRC Examination Level: [XI RO SRO(I) 0 SRO(U) Operating Test Number: 1 B . l Control Room Systems System / JPM Title Type Code* Safety Function

a. Conduct Reactor Recirculation Two Loop Operation /

Respond to a Positive Reactivity Addition (Abnormal)

b. Perform The Weekly RPS Manual SCRAM Test /

Multiple Control Rods Scram During Testing (Abnormal)

c. Place the First RFPT In-Service
d. Equalize SACS Expansion Tank Levels
e. Shutdown the HPCl System
f. Perform Non Emergency Operation of the Diesel Generators
g. Respond To A Low Turbine Hydraulic Pressure (03102 NRC)

B.2 Facility Walk-Through

a. Place the Emergency Instrument Air Compressor In Service (Dh (A), (P)l (R) 8 from the Local Control Panel
b. Bypass A Control Rod in the Reactor Manual Control System (D), (PI 1
c. Defeat ARI Interlocks (Emergency) @)I (P) 7
  • 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 Page 30 of 104 Rev. 2

NC.TQ-WB.ZZ-O027(2)

Appendix D Scenario Outline Form ES-D-1 Examinees: :XE SR02 1 1 ;;

Facility: Hope Creek Generating Station SR04 SR06 Scenario Number: -

Eva1uators:

1 Operating Test Number: -

1 1 Initial 70% Power. A Reactor startup is in progress. (Bank)

Conditions:

Turnover: Continue with Reactor startup.

Event Malf. Event Number Event Description Number Type*

1 Alternate Reactor Auxiliary Cooling Pumps 2 Reactor building isolation EDOZ 3 Loss of station power transformer T-4 and 1OAIIO ED03 RR26/

4 C(ALL) Recirculation pump high vibrations and subsequent trip RR13 RR31I 5 LOCA with Loss of Feedwater FWOI 6 HPOI HPCl auto start failure

  • (N)ormal, (R)eactivity, I i strument , (C)omponent , (M)ajor Page 63 of 104 Rev. 2

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Generating Station Scenario Number: -2 Operating Test Number: - \

Evaluators:

I Initial Reactor startup in progress at approximately 17% power. (New)

Conditions:

Turnover: Withdraw Control Rods. lnerting the Containment. Continue startup.

Event Malf. Event Event Description Number Number Type*

1 Raise Reactor Power with Control Rods 2 CD03 Stuck Control Rod 3 lnerting the Containment (Similar to audit. Audit-pressure control.)

4 ED09A2 Loss of lAD482 inverter 5 MS04 C(ALL) Steam leak in the steam tunnel RR31/

6 M(ALL) Small break LOCNRHR pump room flooding(Fai1ure to isolate)

RH07 7 ADO1 Emergency Depressurization/SRV Failure to open P

~~ ~

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 63 of 104 Rev. 2

NC.TQ-WB.U-0027(2)

Appendix D Scenario Outline Form ES-D-1 d

Facility: Hope Creek Generating Station Scenario Number: - 3 Operating Test Number: - \

l - I -

Examinees: -

SR02 SROI 1 1 -

SR04 -

SR06 SR03 SR05 EvaIuators: -

Initial 95% Reactor power. Shutdown in progress. (Bank Modified)

Conditions:

Turnover: Continue with Reactor shutdown.

Event Malf. Event Event Description Number Number Type*

I Lower Reactor Power with Recirculation Flow Secondary Condensate Pump Trip/Failure of Recirculation Pump to 2 FW04 Runback 3 CUOl RWCU Pump Trip ED011 4 61 M(ALL) Loss of Station Power Transformer, and then a loss of offsite power EG12 DG02/

5 Failure of B EDG, and failure of A EDG breaker to auto close DG08 HP09/

HPCl steam leak with failure to automatically isolate HPIO RCOI RClC turbine overspeed/Emergency Depressurization

  • (N)ormal, (R)eactivity, ( nstrument, (C)omponent, (M)ajor Page 63 of 104 Rev. 2

NC.TQ-WB.ZZ-O027{2)

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Generating Station Scenario Number: - SP Operating Test Number: - \

Examinees: Evaluators:

Initial Plant startup is in progress. Reactor power is approximately 45%. (Bank Modified)

Conditions:

Turnover: Continue with startup.

Event Malf. Event Event Description Number Number Type*

1 Raise power with Control Rods

-e.

NM21/

2 APRM failure upscale with single rod scram CD06 EG04/ Failure of Main Turbine to runback following loss of Stator Water 3

TC06 Cooling RP06/

4 M(ALL) Full-core ATWS (Modified from Half-Core ATWS)

RP07 TCOI -

5 C(ALL) Turbine Bypass Valve failure 10 SLO1/

6 SLC Failure to Automatically Initiate / SLC Pump A trip SL04

  • (N)ormal, (R)eactivity, nstrument, (C)omponent, (M)ajor Page 63 of 104 Rev. 2

Outline Changes Original Exam New Exam Original K A Level New K A Level Reason 295008K203 B 295001K206 B 295008K203 replaced with 295001K206 randomly selected to reduce oversampling of the Reactor Water Level Control topic and increase variety of sampled topics.

295009K201 B 295014K201 B 295009K201 replaced with 295014K201randomly selected to reduce oversampling of the Reactor Water Level Control topic and increase variety of sampled topics.

203000k202 B 206000A402 S Replaced 203000K202 due to too many power supply questions and need for one k/a in category A4. Randomly selected 206000 from unsampled WA's of Teir 2 Group 1.

Randomly selected A402 from the A4 category.

203000K202 B 206000G123 R Replaced 203000K202 due to too many power supply questions and need for one k/a in category G. Randomly selected 206000 from unsampled WA's of Teir 2 Group 1.

Randomly selected G 2.1.24 from the available Generic category WAS.

295038A103 B 295038A102 B 295038A103 Replaced KA due to reduce overemphasis on Process Radiation Monitors. Randomly selected 295038A102 for replacement.

203000K103 B 203000K110 B Changed due to oversampling in RHWLPCI keep-fill systems.

203000K110 ramdomly selected from remaining Kas 239002A206 R 239002A201 R Replaced 239002A206 with 239002A201 randomly selected to reduce sampling in area of high reactor pressure and broaden exam breadth.

290001A301 B 290001A301 B Replaces 290001A302 with 290001A301 due to being too similar to KA 295035.G2.1.32 in question 42. 290001A301 selected due to be the only KA in 290001A3 category.

295036K301 B 295036K303 B Changed KA from 295036 K3.01 to K3.03 due to no plausible reactor coolant leak would cause flooding without other problems.

223002K407 223002K408 B KA 223002K4.07 replaced with 223002K4.08 Original KA material too low discrimintory level for RO's 295024G127 295024G418 R KA changed from 295024G127 to 295024G418 per Chief Examiner request. LOD too low. Non plausible distractors.

2340006446 234000G222 S Original question KA Mismatch. Ability to verify alarms are consistent with plant conditions and Emergency Plan category not suitable for Refueling Equipment system level question. Reselected SRO level Generic KA 234000 G 2.2.22.

Monday, June 02,2003

ES-401 BWR SRO Examination Outline FORM ES-401-1 Facility: Hope Creek Generating Station Date of Exam: 6/17/2003 Exam Level: SRO 1

I WA Category Points Point Tier Group Total K2 K3 K4 K5 K6 AI A2 A3 A4 G*

1. I 1 Emergency &

Abnormal Plant Evolutions Tier Totals I I I I 1 3 2.

Plant Systems I 3 I I Tier 6 Totals Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge and Abilities 4 4 3 6 17 Note: I . Ensure that at least two topics from every WA category are sampled within each tier (Le., the Tier Totals in each WA category shall not be less than two).
2. 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 by31 from that specified in the table based on NRC revisions. The final exam must total 100 points.
3. 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.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the categoryhier.
6. *The generic 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.
7. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified based on plant-specific priorities. Enter the tier totals for each category in the table above.

Page 13 of 46 NUREG-1021, Revision 8, Supplement 1

BWR SRO Examination Outline ES-401-1 Abnormal Evolutions - Tier l/Group 1

. -~~ ~ __ _ _ _ ~ ~ -

System # Name 3 KA Topic(s) mP. ts.

- -~

295003 Partial or Complete Loss c .C. Power AKI .05 Failsafe component design 2.7 1 295003 IPartial or Complete Loss of A.C. Power AK2.04 A.C. electrical loads 3.5 1

~ _.

AK2.05 CRD mechanism 3.3 1 295007 High Reactor Pressure 3.2 1 295007 High Reactor Pressure AK2.02 Reactor power 1 295009 Low Reactor Water Level 1 I - -__ - _---___ -

295010 /High Drywell Pressure 295013 iHigh Suppression Pool Temperature 295014 /InadvertentEactivity Addition 4.1 1 295015 tlncomplete SCRAM I ~ -

295016 IControl Room Abandonment iAK2.03 Control room HVAC 3.1 1 295016 iControl Room Abandonment A K 3 . 0 1 Reactor SCRAM 4.2 I I

295017 /High Off-Site Release Rate system limits and precautions. 3.8 1 295023 IIRefuelingAccidents without reference to procedures those actions that require 4.0 1 components and controls. -

~- ~

295023 lRefueling Accidents 'AKI .03 Inadvertent criticality 4.0 I I

295024 IHigh Drywell Pressure 1E2.04 Suppression chamber pressure: Plant-Specific 3.9 1 I

I 295024 IHigh Drywell Pressure lEA2.01 Drywell pressure 4.4 1 I

295025 High Reactor Pressure I

295026 Eiuppression Pool High Water Temperature lEA1.03 Safetykelief valves: Plant-Specific

-1EK3.04 SBLC injection 4.4

~

4.1 1

I

~

Monday, June 02,2003 8:36:11 AM Page 1

3-40 1 BWR SRO Examination Outline ES-401-1 Emergency and Abnormal Evolutions - Tier l/Group 1 ystem # 1F.Jme (1 K2 K3 A I A2'G/KATopic(s)

Imp. Pts. I 295026 Suppression Pool High Water Temperature X IEK1.G Steam condensation 3.8 1 295027 High Containment Temperature (Mark Ill Containment Only)

~ -

295030 ,Low Suppression Pool Water Level X E i . 0 6 Condensate storage and transfer (make-up to the suppression pool): Plant-Specific 3.4 1

- ~~

295030 jLow Suppression Pool Water Level < 12.2.25 Knowledge of bases in technical specifications for limiting conditions for operations 1 3.7 1 and safety limits.

~~ -

295031 IReactor Low WaterLevel 4.2

- 1 ___

295031 IReactor Low Water Level X EI AO II LOW pressure coolant injection (RHR): Plant-Specific 4.4

_ - ~ ~___ ~

Condition Present and Reactor symptom based EOP mitigation strategies. 4.0 1 Power Above APRM Downscale or Unknown -

55037 SCRAM Condition Present and Reactor EA2.03 SBLC tank level 4.4 1 IPower Above APRM Downscale or Unknown __

...__ - ~-.- - ~

295038 (High Off-Site Release Rate EK3.01 Implementationof site emergency $an 4.5 1

-~

295038 IHigh Off-Site Release Rate

.. -~

~EA1.02Meteorologic;

.-~

instrumentation

-1 3.8 1 I - ~- _._ ~~

~

500000 /HighContainment Hydrogen Concentration EKI .01 Containment integrity 3.9 1 Monday, June 02,20038:36:11AM Page 2

~~~~~

~ ~~-

BWR SRO Examination Outline ES-401-1

-~

iormal Evolutions - Tier IIGroup 2 y s c m # Name A Topic(s) Imp.

~-

295001 Partial or Complete Loss of Forced Core Flow K2.06 Reactor power 3.8 Circulation __

295002 Loss of Main Condenser Vacuum A2.02 Reactor power: Plant-Specific 3.3 1-

~

295004 Partial or Complete Lossof D.C. Power XI .03 Reactor manual control/rod control and information system 2.8

~- ~

.2.25 Knowledge of bases in technical specifications for limiting conditions for operations 3.7 nd safety limits.

~~ _~ --- - .-

,K1.03 Feed flow/steam flow mismatch 3.2

.4.6 Knowledge symptom based EOP mitigation strategies. 4.0 I - -~ -

295012 /High Drywell Temperature ,K1.02 Reactor powerlevel control 3.2 A - - - -

295018 Partial or Complete Loss of Component Cooling Water -

,K2.07 Condensate system 3.2

- __ ~~

295019 or Complete Loss of Instrument Air a2.01 Instrument air system pressure 3.6 i

295020 \Inadvertent Containmentlsolation rK2.03 Drywelkontainment ventilation/cooling: Plant- Specific 3.3 1

- 1 ~~~ ~- ~ ~-

295020 /Inadvertent Containment Isolation LKI.02 Powedreactivity control 3.8 , 1 I

1 ~- - ____ ~

295021 \Lossof Shutdown Cooling iK3.02 Feeding and bleeding reactor vessel 3.4 1 295022 \Loss of CRD Pumps z3.02 CRDM high temperature 3.1 1 295028 /High Drywell Temperature

~

~~~

~~ - ~~-

295029 iHigh Suppression Poolwater Level iA2.03 Drywellkontainment water level 3.5 1

-~ ~

295032 'High Secondary Containment Area

'Temperature Monday, June 02,2003 8:36:12AM Page 3

ES-401 BWR SRO Examination Outline ES-401-1 Abnormal Evolutions - Tier l/Group 2 jystem # !Name K1 S KATopic(s) 295033 ]High Secondary Containment Area Radiation EA1.02 Process radiation monitoring system jLevels Containment Ventilation High 1

Containment High Differential X 2.1.32 Ability to explain and apply system limits and precautions. 3.8 Pressure ~~

Containment High Sump/Area EK3.03 Isolating affected systems 3.6 Water Level

_ - . 1 Monday, June 02,2003 8:36:12 AM Page 4

j ES-40 1 System ]Name 201005 rod Control and Information System I , -

1 BWR SRO Examination Outline Plant Svstems - Tier 2IGrou11 1 C2 K3 K4 K5 K6 A I ,A2 \3 iA4 G Top(c(s)

ES-401-1 Imp. Pts.

l(RCW 202002 IRecirculation Flow Control System 203000 lRHR/LPCI: Injection Mode (Plant Specific]

Ii iI l ~ 1 . 1 0ECCS room coolers 3.2 1

~-

I I I 206000 lHigh Pressure Coolant Injection System lXl A4.02 Flow controller: BWR-2, 3, 4 207000 llsolation (Emergency) Condenser 209001 /Low Pressure Core Spray System m1 - 1 I ~

A2.06 Inadequate system flow 209002 iHigh Pressure Core Spray System (HPCS) 21 1000 iStandbyLiquid Control System K2.02 Explosive valves 1

_ _ _ 1 212000 /Reactor 6oGction System 1 ~A4.04Bypass SCRAM instrument volume high level SCRAM signal 1 1

-1 tI :

X ~

_~ ~ _ _- ~ ._ . .

215004 /Source Range Monitor (SRM) System

_ _ ~I 215005 IAverage Power Range MoGor/Local IPower Range Monitor System

- -~

215005 ,Averagepower Range Monitor/Local

/Power Range Monitor System 216000 /Nuclear Boiler Instrumentation X 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 1

~ _~

216000 /Nuclear Boiler Instrumentation A I .04 System venting 2.8 1 I 1 Isolation Cooling System I 1 K3.01 Reactor water level 3.7 1 (RCIC) ~

3.1 "I Isolation Cooling System IkRCIC) __ I 218000 IAutomaTc Depressurization System I 4.0 1 I

223001 /Primary Containment System and I buxiliaries I I - I 1 1 '

223002 Primary Containment Isolation X 3.7 1

~System/NuclearSteam Supply Shut-Off 226001 ~RHR/LPCI:Containment Spray System X 3.4 1 IMode Mondav. June 02.2003 8:36:21AM

~ ~ _ ~ _- _ ~- _ _ _ ~

33-401 BWR SRO Examination Outline ES-401-1 ystems - Tier 2IGroup 1 System /Name jK1 /K2 27A3 ,A4 G KA Topic(s) 1 ~-

239002 ReliefEafety Valves K A2.04 ADS actuation

~~-~ ~

Pressure Regulating j ~

X 22.22 Knowledge of limiting conditionsfor operations and safety limits.

System i-

~

241000 ReactorITurbine Pressure Regulating lK5.04 Turbine inlet pressure vs. reactor pressure System ~~~ -

I 259002 Reactor Water Level Control System lK3.07 Reactor water level indication

' I I -

~ ~~

259002 Reactor Water Level Control System I( 12.1.33 Ability to recognize indications for system operatingparameters which lare entry-level conditions for technical specifications.

~~

~~

Gas Treatment System ~

___- - - ~

1 - 1 I

,A3.04 Operaion of the governor control system on frequency andvoltage

/control Generators (DieseVJet) iK6.01 Starting air 290001 /Secondary Containment

~~

I lA3.01 Secondary containment isolation IK1.07 Turbine building ventilation (steam tunnel): Plant- Specific 1 3 . 1 1

~~

Monday, June 02,2003 8:36:21 AM Page 2

ES-401 BWR SRO Examination Outline ES-401-1 2/Group 2 ~~

System iName K1 K2 K3 K4 (A Topic(s) Imp.

201001 Control Rod Drive Hydraulic System (6.05 A.C. power 1 3.3

~~

201001 Control Rod Drive Hydraulic System X (3.03 Control rod drive mechanisms 3.2

-~ I 201002 IReactor Manual Control System I1 41.05 Local reactor power 3.6

-~~

201004 iRod Sequence Control System (Plant

/Specific) I I

~

201006 IRod Worth Minimizer System (RWM)  !.I.32 Abilitytoexplain and apply system limits and precautions. 3.8

/(Plant Specific) 202001 IRecirculation System I

1  ;

i 1 -

D.03 Single recirculation pump trip 3.7 I

I I

. -~ ~ ---

204000 /Reactor Water Cleanup System (1.03 Reactor feedwater system 3.1 205000 IShutdownCooling System (RHR Shutdown Cooling Mode) 215002 ]Rod Block Monitor System 215003 llntermediate Range Monitor (IRM) System 1 I

219000 IRHR/LPCI: Torus/Suppression Pool (2.01 Valves 2.9 iCooling Mode 230000 RHRILPCI: Torus/Suppression Pool ,

!3pray Mode

~

234000 IFuel Handling Equipment L.2.22 Knowledge of limiting conditions for operations and safety limits. 4. I I

~ ~~~

239003 IMSlV Leakage Control System II I

1 I

245000 IMain Turbine Generator and Auxiliary I Isystems 259001 IReactor Feedwater System l i 1 1 - .

262002 'Urhterruptable Power Supply (A.C./D.C.) X 1 (1.01 Feedwater level control: Plant-Specific I I 1

263000 1D.C. Electrical Distribution 41.01 Battery charging/dischargingrate 2.8 271000 Offgas System I

Monday, June 02,2003 8:36:22AM Page 3

!S-401 BWR SRO Examination Outline ES-401-1 Plant Systen er 2IGroup 2 (5 K6 A I A2 A: 2 IKA ToGc(s) Imp. Pts.

286000 /Fire Protection System Control Room HVAC A3.01 Initiationheconfiguration 3.5

~-

K5.01 Air compressors 2.5

~-~~ ~~~ ~

~~

Cooling Water System-. 3.9 (CCWS)

Monday, June 02,2003 8:36:22 AM Page 4

I ES-401 BWR SRO Examination Outline ES-401-1

-Tier 2IGroup 3 System /Name 4 4 G IKA Topic(s) Imp.

201003 /Control Rod and Drive Mechanism

~-

215001 Traversing In-Core Probe

_ . - - - _~ - ~

233000 Fuel Pool Cooling and Clean-up ' IAl.01 Surge tank level 2.9

~- -

I 233000 Fuel Pooi Cooling and Clean-up 2 v R k h e a t S y s t e m IK1.09 Component cooling water systems 2.6

. I -

256000 Reactor Condensate System lK4.06 Control of extraction steam 2.8

-L 268000 Radwaste X 12.4.4 Ability to recognize abnormal indications for system operating parametkrs lwhich are entry-level conditions for emergency and abnormal operating brocedures -

4.3 j -- - - _ _ _

Monday, June 02,2003 8:36:22 AM Page 5

ES-401 Generic Knowledge and Abilities Outline (Tier 3) ES-40I-5 Conduct of Operations 2 1.I 1 IKnowledge of less than one hour technical specification action ' 3.8 1 statements for systems.

2.1. I 2 Ability to apply technical specifications for a system. 4.0 1 2.1.34 lAbility to maintain primary and secondary plant chemistry within 2.9 1 lallowable limits. ~- -

2.1.8 iAbility to coordinate personnel activities outside the control room. 3.6 1 Total 4 Equipment Control 2.2.27 IKnowledge of the refueling process. 3.5 1 I

described in the safety analysis report.

l2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 1 2.2.26 Knowledge of refueling administrative requirements. 3.7 1 IRadiological Controls 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and 3.3 1 guard against personnel exposure.

12.3.1I Ability to control radiation releases. 3.2 1 Emergency Procedures and 2.4 48 'Ability to interpret control room indications to verify the status and 3.8 1 Plan loperation of system, and understand how operator action s and

,parameterswhich are entry-level conditions for emergency and 2.4.17 IKnowledge of EOP terms and definitions. 3.8 1

~ _ _ _ _ _ ~ _ _ _ _ _ ~~ _ -~

2.4.30 Knowledge of which events related to system opera<ions/status should - 3.6 1 2.4.47 Ability to diagnose and recognize trends in an accurate and timely 3.7 1 manner utilizing the appropriate control room reference material.

Monday, June 02,2003 8:36:32 AM

ES-401 BWR RO Examination Outline FORM ES-401-2 Facility: Hope Creek Generating Station Date of Exam: 6/17/2003 Exam Level: RO I I I WA Category Points Point Tier Group Total K1 I K2 I K3 K4 K5 K6 AI A2 A3 A4 G*

U 4 2 36

2. 0 I - l Plant 2 4 2 2 2 2 0 1 1 - ' - ' - 1 - 1 Systems 3 1 0 1 0 0 Y Tier Totals 7 4 6 5 4 3 5 5 5 5 2 51 Cat 1 Cat 2 Cat 3 Cat 4
3. Generic Knowledge and Abilities 3 4 2 4 13 Note: 1. Ensure that at least two topics from every WA category are sampled within each tier (Le., the "Tier Totals" in each WA category shall not be less than two).
2. 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 by31 from that specified in the table based on NRC revisions. The final exam must total 100 points.
3. 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.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.
6. *The generic 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.
7. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. WAS below 2.5 should be justified based on plant-specific priorities. Enter the tier totals for each category in the table above.

Page 26 of 46 NUREG-1021, Revision 8, Supplement 1

~~ -~ ~~

' ES-40 1 BWR RO Examination Outline ES-401-2 Emergeno ind Abnormal Evolutions - Tier l/GrouD 1 ~~~~ -

System # IName K1 K21K: Imp.

295005 IMain Turbine Generator Trip AA1.03 Reactor manual control/rod control and information system 2.7 295006 bCRAM x IAK2.05 CRD mechanism 3.1

~~ - ~~ ~

295007 iHigh Reactor Pressure Low pressure system isolation- 3.0

.- __ -I ~~ ~-

295007 IHigh Reactor Pressure X AK2.02 Reactor power 3.8 I

295009 LOW Reactor Water Level lAK3.01 Recirculationpump run back: Plant-Specific I

3.2 295010 IHigh Drywell Pressure 295014 Ilnadvertent Reactivity Addition

~,

X 1AK2.01 RPS , 3.9

~ ~~

295015 /IncompleteSCRAM I

X I

AKI .01 Shutdown margin

- ~-

, 3.6 1 ~- . ~ . _ _

295024 [High D-ywell Pressure 1( 2.4.18 Knowledge of the specific bases for EOPs. 2.7 I

295024 /High Drywell Pressure EA201 Drywell pressure ~ 4.2 295025 /High Reactor Pressure -EA1.03 Safetykelief valvesy%nt-Specific

~~

1 4.4 I

295031 /Reactor Low Water Level EA1.01 Low pressure coolant injection (RHR): Plant-Specific 1 4.4 295037 k R A M Condition Present and Reactor Power iEA2.03 SBLC tank level ' 4.3 IAbove APRM Downscale or Unknown I WI.OI

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I 500000 IHigh Containment Hydrogen Concentration X Containment integrity 1 3.3 I

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Monday, June 02,2003 8:35:41 AM Page 1

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!S-401 BWR RO Examination Outline ES-401-2

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jency Ema ~. - and Abnormal Evolutions - Tier l/Group 2 ~

System # /Name

~~

Loss of Forced Core Flow

~ _ _ .

T: :3 A I A2 G KATopic(s)

AK2.06 Reactor power mP.

3.8

'ts.

1 295002 iLoss ofMain Condenser Vacuum

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295003 /Partial or Complete Loss of A.C. Power 1AK2.04A.C. electri&l loads 3.4 1

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295003 IPartial or CompleTeLoss of A.C. w ;o P iAKl.05 Failsafe component design 2.6 1

0-2 Complete LOSS of D.C. Power

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I __

295008 /High Reactor Water Level iAKl.03 Feed flowisteam flow mismatch 3.2 1 295011 high Containment Temperature ( M a x (ContainmentOnly) 1-295012 /High Drywell Temperature lAKl.02 Reactor power level control 3.1 1

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295013 'High Suppression Pool Temperature iAA1.02 Systems that add heat to the suppression pool 3.9 I K O 1 6 ;Control Room Abandonment IAK3.01 Reactor SCRAM 4.1 1

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295016 kontrol Room Abandonment lAK2.03 Control room HVAC 2.9 1 1 1 I ~

295017 iHigh Off-Site Release Rate X 12.1.32 Ability to explain and apply system limits and precautions. 3.4 1 295018 IPartial or Complete Loss of Component Cooling Water

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295019 IPartial or Complete Loss of Instrument Air iAK2.07 Condensate system 3.2 1

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295020 ~InadvertentContainment Isolation X ~AK2.03Drywell/containmentventilation/cooling: Plant- Specific 3.1 I

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295020 Inadvertent Containment Isolation AKI .02 Power/reactivity control 3.5 1

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295022 LOSS of CRD Pumps X 1AK3.02CRDM high temperature 2.9 1

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295026 Suppression Pool High Water Temperature 'EKI.02 Steam condensation 3.5 1 295026 Suppression Pool High Water Temperature X EK3.04 SBLC injection 3.7 1 Monday, June 02,2003 8:35:42 AM Page 2

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is-401 BWR RO Examination Outline ES-401-2 Emc jency and Abnormal Evolutions - Tier I/Grouo 2 -

Imp.

Temperature (Mark I l l Containment Only)

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lEA1.06 Condensate storage and transfer (make-up to the suppression pool): Plant- 3.4 lspecific I295033 High Secondary Containment Area Radiation Levels

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295034 Secondary Containment Ventilation High Radiation 295038 IHigh Off-Site Release Rate 295038 High Off-Site Release Rate 600000 Plant Fire On Site IEAl.02 Process radiation monitoring system i

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W T M e t e o r o i o g i c a l instrumentation I

iEK3.01 Implementation of site emergency plan

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3.7 3.0 3.6

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Monday, June 02,2003 8:35:42 A M Page 3

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I X Y X c

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al

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!S-401 jystem i/;i Ci+---

201001 Control Rod Drive Hydraulic System BWR RO Examination Outline Plant Systems - Tier 2/Group 1

6 A I A2 A3 A4 I G /KA 1

Topic(s)

IK3.03 Control rod drive mechanisms ES-401-2

, 3.1 1 201001 Control Rod Drive Hydraulic System K lK6.05 A.C. power 133 1

~

X I 3.4 1 i -- -- .- ~-

I I

203000 RHR/LPCI: Injection Mode (Plantspecific) X 1 K1. I O ECCS room coolers 1 I

206000 High Pressure Coolant Injection System ( 2.l.g-Ability to perform specific system and integrated plant procedures during  ! 3.9 1 different modes of plant operation.

1-ll I

207000 Isolation (Emergency) Condenser I I

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209001 Low Pressure Core Spray System K2.01 Pump power ' 3.0 1 209001 j ~ o wPressure Core Spray S y s t e m - 1 1 A2.06 Inadequate system flow '3.2 1 209002 High Pressure Core Spray System (HPCS)

I 1  ! I 21 1000 /Standby Liquid Control System 1 lx lK2.02 Explosive valves 1 3.1 1 21 1000 IStandby Liquid Control System 1 1 I 1 ~- -

K4.02 Component and system testing

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3.0 I 212000 /Reactor Protection System X A3.07 SCRAM air header pressure 3.6 1

-- ---- -- ~ I 212000 IReactor Protection System X 1~4.04Bypass SCRAM instrument volume high level SCRAM signal- l 3.9 1 i "

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215003 ;IntermediateRange Monitor (IRM) System X lA4.03 IRM range switches 3.6 1 I l l  !

i -~~ 1 1 1 ~~

215003 llntermediate Range Monitor (IRM) System ' X /K1.02 Reactor manual control 3.6 1 I ' I I

I ~- .  ! I I

215004 ISource Range Monitor (SRM) System 8 ,

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215005 ;Average Power Range MonitorILocal X lK6.04 Trip units 3.1 1

'Power Range Monitor System 215005 IAverage Power Range Monitor/Local X 3.9 1 (PowerRange Monitor System Monday, June 02,2003 8:35:49AM Page 1

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ES-401 BWR RO Examination Outline ES-401-2

'ier 2/Group 1 System Name K1 K21K31K4iK5lK6 A I A2/A31A4 G /KA Topic(s) 1 Imp. Pts.

216000 Nuclear Boiler Instrumentation i i i i x 1 1

- a

~Al.04System venting I

I

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C O TIsolation Cooling System lK5.02 Flow indication (RCIC)

_ _ _ _ ~

iK3.01 Reactor water level 1

lx lA4.02 ADS logic initiation I I

-v 218000 'Automatic Depressurization System lK4.02 Allows manual initiation of ADS logic 223001 Primary Containment System and Auxiliaries 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off 239002 Relief/Safety Valves I

~

-T- I K4.08 Manual defeating of selected isolations during specified emergency conditions A2.01 Stuck open vacuum breakers 1  ; __

239002 Relief/Safety Valves i ~ 2 . 0 4ADS actuation

__ _ p ~ _

Pressure Regulating Feedwater System I I iK5.04 Turbine inlet pressure vs. reactor pressure I

lA3.07 FWRV position 3.2 1 1 I 1

2 5 9 v ~ a t eLevel r Control System iK3.07 Reactor water level indication

_ _ _ _ _ p - ~ - -

Standby Gas Treatment System

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Emergency Generators (DieseVJet) lA3.04 Operation of the governor control system on frequency and voltage lcontrol -

I- i 264000 Emergency Generators (DieseVJet) IK6.01 Starting air Monday, June 02,20038:35:50AM Page 2

i ES-40 1 BWR RO Examination Outline ES-401-2 Plant Svt ms - Tier 2IGroup 2 System Name l2 K3 K4 K5 K6 A I 3 T ~ 4 I iw Totick) Imp. Pts.

201003 Control Rod and Drive Mechanism 201004 Rod Sequence Control System (Plant Specific)

I 201006 lRod Worth Minimizer System (RWM)

(Plant Specific) ~ - -

202001 IRecirculation System A2.03 Single recirculation pump trip 3.6 1

- ~

204000 IReactomater Cleanup System feedwater system , 3.1 1 205000 ishutdown Cooling System (RHR

/Shutdown Cooling Mode) ~ _ _ ~ ~

214000 ]Rod Position Information System

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215002 /Rod Block Monitor System 2.8 219000 IRHR/LPCI: Torus/Suppression FOG 2.5-

/Cooling Mode 219000 IRHR/LPCI: TohdSuppression Pool 1 3.0

/Cooling Mode -

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I-226001 RHR/LPCI: Containment Spray System 2.8 (Mode _____ I __

~~

226001 IRHRILPCI: Containment Spray System iK1.08 Nuclear boiler instrumentation 3.2 IMode

~-

230000 IRHRILPCI: Torus/Suppression Pool

/Spray Mode -

2 3 9 0 T E i n and Reheat Steam System

-t

~ 245000 IMainTurbine Generator and Aux- X T 5 . 0 3 Hydraulically operated valve operation 1 2.6 ISystems

-- - -~~

2.8 256000 IReactor Condensate System iK4.06 Control of extraction steam I 1 -

256000 jReactoFCondensate System IA2.06 Low hotwell level ~ 3.2

~ I -

262001 1A.C. Electrical Distribution ~

262002 IUninterruptablePower Supply (A.C.7D.C.) X iK1.01 Feedwater level c i % o l : Plant-Specific 2.8 263000 1D.C. Electrical Distribution X !AI.01 Battery charging/discharging rate 2.5 1 I

Monday, June 02,2003 8:35:50AM Page 3

S-401 BWR RO Examination Outline ES-401-2 iystems - Tier 2IGroup 2

~~

System /Name i 2 A3 A4 G IKA Topic(s) 'ti.

271000 Offgas System

~~~ ~-

272000 Radiation Monitoring System iK3.01 Station liquid effluent release monitoring 1 I

i

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I I

lA3.01 Secondary containment isolation /9 1 lK1.07 Turbine building ventilation (steam tunnel): Rant- Specific I 3.0 1 I ~

290003 Control Room HVAC iA3.01 Initiationheconfiguration 1 I

____ ~

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300000 InstrumentAir System (IAS) iK5.01 Air compressors ~ 2.5 I

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lK4.01 Automatic start of standby pump 3.4 1 lK3.01 Loads cooled by CCWS 2.9 1 Monday, June 02,2003 8:35:51AM Page 4

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ES-401 BWR RO Examination Outline ES-401-2 er 2lGroup 3 System TName K1 K2 K3lKL 5 /KA Topic(s) 215001 /Traversing In-Core Probe i I I

233000 /Fuel P o E o o l i n g and Clean-up /AI.01 Surge tank level t

I 1

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2 3 3 0 m o o l i n g and Clean-up K1.09 Component cooling water systems 2.6 234000 IFuel Handling Equipment Control System 268000 IRadwaste T -1

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288000 Plant Ventilation Systems Ability to verify system alarm setpoints and operate controls identified in 3.3 the alarm response manual.

290002 /ReactorVessel lnternals

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ES-401 Generic Knowledge and Abilities Outline (Tier 3) ES-401-5

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Facility: Hope Creek DateofExam 06/17/2003 ~- Exam Level: RO

_ ~ _ _ _ _ -- -_ _ - ._ ~ ~~ ~ _ _ _ _ _

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Cateaorv KA# I Topic ImD. ointsl Iconduct of Operations 2.12 8 Knowledge of the purpose and function of major system components 3.2 1 and controls.

2.1.I 1 Knowledge of less than one hour technical specification action Total 3

~~~~~

Equipment Control 2.2.35 IKnowledge of control rod programming. 2.5 1

~ 2.2.27 iKnowledge of the refueling process. 2.6 1 2.2.26 IKnowledgeof refueling administrative requirements. 2.5 1 2.2.22 IKnowledgeof limiting conditions for operations and safety limits. 3.4 1 Total 4 Radiological Controls 2.3.1 1 Ability to control radiation releases. I 2.7 1 2.4.4 Ability to recognize abnormal indications for system operating 4.0 1 I parameters which are entry-level conditions for emergency and ITotal 4

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Tier 3 Target PointTotal (RO/SRO) 13

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Monday, June 02,2003 8:35:57AM

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