ML052220544

Initial Operator Examination Submittal

ML052220544
Person / Time
Site:	Nine Mile Point
Issue date:	05/03/2005
From:	Godley R Constellation Energy Group
To:	Collins S Region 1 Administrator
Conte R
References
NMP-99412
Download: ML052220544 (12)

Text

P . 0 . Box 63 Lycoming, NY 13093 Constellation Energy.

Nine Mile Point Nuclear Station NMP-994 12 May 3,2005 Mr. Samuel J. Collins Regional Administrator USNRC Region I 475 Allendale Road King of Prussia, PA 19406 - 1415 ATTENTION: Mr. Steven Barr, Senior Examiner/Inspector

SUBJECT:

NINE MILE POINT UNIT 1 INITIAL OPERATOR EXAMINATION SUBMITTAL

Dear Mr. Collins:

In response to the NRC Letter of April 2 1, 2005 entitled REACTOR OPERATOR RETAKE EXAMINATION - NINE MILE POINT NUCLEAR STATION, UNIT 1, arrangements have been made for the administration of licensing examinations at Nine Mile Point, Unit 1 during the week of 17 June 2005. The examinations have been prepared based on the guidelines in Revision 9 of NUREG 1021, "Operator Licensing Examination Standards for Power Reactors."

To meet the examination schedule, Nine Mile Point Nuclear Station was requested to furnish the examinations by May 5,2005.

Enclosed are the written examinations and supporting reference materials for the Reactor Operators. The enclosed materials have been approved for use by NMP in accordance with 10CFR55.40(b)(3).

Please withhold this examination material from public disclosure until after the examinations have been completed.

If you have any questions regarding the submittal, please contact Robert Brown (General Supervisor Operations Training) at 3 15-349-4531, or Ralph Hoffman (Initial Operations Training Supervisor) at 3 15-349-2469.

Sincerelv. ,

kd&W Robert C. Godley Manager Nuclear Training RCGkcm Enc .

UNIT 1 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 1 Date of Exam: June 17,2005 Note 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each KIA 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 by +I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

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

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

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

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

7.*The generic ( G ) WAS in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the K/A numbers, descriptions, IRs, and point totals on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43 ES 401, Page 1 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29, 2005

UNIT 1 NRC (RO)

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

E/APE # / Name / Safety Function 295001 Partial or Complete Loss of Forced GI WA Topic(s)

AA1.06 Ability to operate and/or monitor the Core Flow Circulation / 1 & 4 following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Neutron monitoring system.

295003 Partial or Complete Loss of AC / 6 AK2.02 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF A.C. POWER and the following: Emergency Generators.

295004 Partial or Total Loss of DC Pwr / 6 AA2.02 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Extent of partial or complete loss of D.C. power.

295005 Main Turbine Generator Trip I 3 AA2.04 Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: Reactor pressure.

295006 SCRAM I 1 AK3.04 Knowledge of the reasons for the following responses as they apply to SCRAM: Reactor water level setpoint setdown.

295016 Control Room Abandonment / 7 AK2.02 Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following: Local control stations.

295016 Control Room Abandonment / 7 AA1.09 Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: Isolation/emergency condenser(s).

295018 Partial or Total Loss of CCW / 8 AA1.02 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

System loads.

295019 Partial or Total Loss of Inst. Air / 8 X

• 1 2.4.31 Knowledge of annunciators alarms and indications / and use of the response instructions.

295021 Loss of Shutdown Cooling I 4 AK1.02 Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING: Thermal stratification.

295023 Refueling Acc Cooling Mode / 8 2.1 14 Knowledge of system status criteria which require the notificabon of plant personnel 295024 High Drywell Pressure / 5 EK2.07 Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:

PCISINSSSS.

295025 High Reactor Pressure / 3 EA2.01 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor pressure.

(Repeat WA from 2002 NRC RO Written exam).

295026 Suppression Pool High Water Temp. 2.1.33 Ability to recognize indications for system 15 operating parameters which are entry-level conditions for technical specifications.

295028 High Drywell Temperature / 5 EAl.01 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell spray.

295030 Low Suppression Pool Wtr Lvl / 5 EK3.01 Knowledge of the reasons for the following responses as they apply to LOW SUPPRESSION POOL WATER LEVEL: Emergency depressurization.

ES 401, Page 2 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29, 2005

UNIT 1 NRC (RO)

EA2.01 Ability to determine and/or interpret the 4.6 1 17 following as they apply to REACTOR LOW WATER LEVEL: Reactor water level.

EK2.06 Knowledge of the interrelations between 3.5 1 18 SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following: CRD mechanisms.

EK1.02 Knowledge of the operational implications of 4.2 1 19 the following concepts as they apply to HIGH OFF-SITE RELEASE RATE: Protection of the general Dublic.

to PLANT FIRE ON SITE.

abnormal procedure for 1 WA Category Totals: 1 2 1 4 1 31 41 4 ES 401, Page 3 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29, 2005

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UNIT 1 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1

.-- Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO) 1 E/APE # / Name / Safety Function I: I I I I I K

2 K

3 A

1 A

2 G WA Topic(s) P T

I 295002 Loss of Main Condenser Vacuum / I AA2.01 Ability to determine andlor interpret the 2.9 1 21 following as they apply to LOSS OF MAIN CONDENSER VACUUM Condenser vacuurdabsolute pressure.

295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 I: AKI .05 Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTIVITY ADDITION: Fuel thermal limits.

3.7 1 1

22 23 295022 Loss of CRD Pumps / 1 1 24 295032 High Secondary Containment Area 2.4.6 Knowledge symptom based EOP mitigabon 1 25 Temperature / 9 295035 Secondary Containment High 0 EK1.O1 Knowledge of the operational irnplicabons of 39 1 26 Differential Pressure / 5 1 the following concepts as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE Secondary containment integrity 500000 High CTMT Hydrogen Conc. / 5 0 EK2.07 Knowledge of the interrelations between HIGH 3.2 1 27 7 CONTAINMENT HYDROGEN CONCENTRATIONS the following: Drywell vent system I

8 , .

K A Category Point Totals 2 1 0 1 2 1 Grohp*oal: 7 ES 401, Page 4 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29, 2005

UNIT 1 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Emerl and Abnormal Plant Evolutions - Tier 2IGroup 1 (RO)

T I System # / Name K/A Topic@) PT #

IR 205000 Shutdown Cooling A2.06 Ability to (a) predict the impacts of the 3.4 1 28 following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: SDC pump trips.

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206000 HPCl K4.07 Knowledge of HIGH PRESSURE 4.3 1 29 COOLANT INJECTION SYSTEM design feature@)and/or interlocks which provide for I

the following: Automatic system initiation:

207000 Isolation (Emergency)

Condenser 207000 Isolation (Emergency) 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

A4.03 Ability to manually operate andlor I 3.4 1

1 30 31 Condenser monitor in the control room: Primary and shell side temperatures.

209001 LPCS 2.1.32 Ability to explain and apply system 1 32 limits and precautions.

K1.02 Knowledge of the physical connections 3.4 1 33 l2 and/or cause-effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the following: Toruskuppression pool.

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21 1000 SLC A3.08 Ability to monitor automatic operations 4.2 1 34 of the STANDBY LIQUID CONTROL SYSTEM including: System initiation.

212000 RPS K4.08 Knowledge of REACTOR 4.2 1 35 PROTECTION SYSTEM design feature@)

and/or interlocks which provide for the following: Complete control rod insertion following SCRAM signal generation.

215003 IRM A4.07 Ability to manually operate and/or 3.6 1 36 monitor in the control room: Verification of proper functioning/ operability.

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215004 Source Range Monitor K2.01 Knowledge of electrical power supplies 2.6 1 37 to the following: SRM channels/detectors.

21 5005 APRM / LPRM A I .07 Ability to predict and/or monitor 3.0 1 38 changes in parameters associated with operating the AVERAGE POWER RANGE MONITOR / LOCAL POWER RANGE MONITOR SYSTEM controls including: APRM gain adjustment factor.

215005 APRM / LPRM K6.07 Knowledge of the effect that a loss or 3.2 1 39 malfunction of the following will have on the AVERAGE POWER RANGE MONlTORlLOCAL POWER RANGE MONITOR SYSTEM: Flow converterlcomparator network:

218000 ADS I A3.01 Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION 4.2 1 40 SYSTEM including: ADS valve operation.

ES 401, Page 5 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29, 2005

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UNIT 1 NRC (RO)

A3.01 Ability to monitor automatic operations 3.4 1 of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF including: System indicating lights, alarms.

K5.02 Knowledge of the operational 3.7 1 implications of the following concepts as they apply to RELIEFSAFETY VALVES: Safety function of SRV operation.

259002 Reactor Water Level I 1 1 K6.05 Knowledge of the effect that a loss or 3.5 1 malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM: Reactor water level input.

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Al.04 Ability to predict and/or monitor 3.0 1 changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including: Secondary containment differential pressure.

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A2.11 Ability to (a) predict the impacts of the 3.2 1 following on the A.C. ELECT DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Degraded system voltages.

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K1.03 Knowledge of the physical connections 3.4 1 and/or cause-effect relationships between A.C. ELECTRICAL DISTRIBUTION and the following: Off-site power sources.

A3.01 Ability to monitor automatic operations 2.8 1 of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) including: Transfer from preferred to alternate source.

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A2.01 Ability to (a) predict the impacts of the 2.8 1 following on the D.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Grounds.

A4.01 Ability to manually operate and/or 3.3 1 monitor in the control room: Adjustment of exciter voltage.

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K1.06 Knowledge of the physical connections 3.2 1 and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEL/JET) and the following: Starting system.

K2.01 Knowledge of electrical power supplies 2.8 1 to the following: Instrument air compressor.

400000 Component Cooling Water Ill A2.03 Ability to (a) predict the impacts of the following on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Highllow 2.9 1 CCW temp.

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Al.03 Ability to predict and/or monitor 2.7 1 changes in parameters associated with operating the CCWS controls including: CCW KIA Category Point Totals: 3 2 0 pressure.

Group Point Total:

-- 26

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ES 401, Page 6 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29. 2005

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UNIT 1 NRC (RO)

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ES-401 BWR Examination Outline Form E S 4 z - 1 Emergency and Abnormal Plant Evolutions - Tier 2IGroup 2 (RO)

- -

System # / Name A G KIA Topic(s) IR #

4 201001 CRD Hydraulic K5.08 Knowledge of the operational 2.5 54 implications of the following concepts as they apply to CONTROL ROD DRIVE HYDRAULIC SYSTEM: Solenoid operated valves.

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202001 Recirculation Al.09 Ability to predict and/or monitor 3.3 55 changes in parameters associated with operating the RECIRCULATION SYSTEM controls including: Recirculation pump seal pressures.

204000 RWCU 2.1.2 Knowledge of operator 3.0 56 responsibiltbes during all modes of plant operation.

216000 Nuclear Boiler lnst K5.07 Knowledge of the operational 3.6 57 implications of the following concepts as they apply to NUCLEAR BOILER INSTRUMENTATION: Elevated containment temperature effects on level Indication.

219000 TorusiPool Cooling Mode A I .08 Ability to predict andlor monitor 3.7 58 changes in parameters associated with operating the TORUS/SUPPRESSION POOL COOLING MODE controls including: System lineup.

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226001 RHRILPCI: CTMT Spray Al.06 Ability to predict andlor monitor 3.2 59 Mode changes in parameters associated with operating the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE controls including: System flow.

234000 Fuel Handling Equipment K6.04 Knowledge of the effect that a loss 2.9 60 or malfunction of the following will have on the FUEL HANDLING EQUIPMENT:

Refueling platform air system.

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245000 Main Turbine Gen. / Aux. K5.07 Knowledge of the operational 2.6 61 implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: Generator operations and limitations.

259001 Reactor Feedwater K3.12 Knowledge of the effect that a loss 3.8 62 or malfunction of the REACTOR FEEDWATER SYSTEM will have on following: Reactor power.

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i 288000 Plant Ventilation A4.01 Ability to manually operate and/or 3.1 63 monitor in the control room: Start and stop fans.

290003 Control Room HVAC A201 Ability to (a) predict the impacts of 3.1 64 the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Initiation/recontiguration.

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ES 401, Page 7 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29, 2005

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UNIT INRC (RO)

ES 401, Page 8 of 8 05 NMP UNIT 1 (NRC) - RO Written Exam Outline Friday, April 29, 2005

UNIT 2 NRC (RO)

ES-40 1 Geneic Knowledge and Abilities Outline vier 3) (RO) F OES-401-3

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Category WA # Topic RO IR 1.

Conduct of Operations I 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

[ Knowledge of shift turnover practices.

3.0 3.0 I 2.1.8 Ability to coordinate personnel activities outside the control room.

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3.8

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2 2.2.1 Ability to perform pre-startup procedures for 3.7 the facility I including operating those controls Equipment associated with plant equipment that could Control affect reactivity.

Knowledge of RO duties in the control room 3.5 during fuel handling such as alarms from fuel handling area / communication with fuel storage facility I systems operated from the control room in support of fueling operations /

and supporting instrumentation.

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3. 2.3.10 Ability to perform procedures to reduce 2.9 excessive levels of radiation and guard Radiation against personnel exposure.

Control (Repeat K/A from 2004 NRC RO Written Exam) 2.3.11 Ability to control radiation releases. 2.7 Subtotal

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4. 2.4.12 Knowledge of general operating crew 3.4 responsibiIities during emergency operations.

Emergency Knowledge of facility protection requirements 2.4.26 2.9 Procedures / including fire brigade and portable fire fighting Plan equipment usage.

2.4.29 Knowledge of the emergency plan. 2.6 1 Subtotal I Tier 3 Point Total -

1 ES 401, Page 1 of 1 05 N M P UNIT 1 (NRC) - RO Written Exam Outline Tier 3 Friday, April 29, 2005

UNIT 1 NRC (RO)

Facility: Nine Mile Point Unit 1 Date of Exam: June 17,2005

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ES-401 Record ofRejected WAS (RO) Form ES-401-4 I Tier / Group I Randomly Selected WA I Reason for Rejectton KAs, or equivalent. They are:

design.

TIGI 600000 AK.3 Selected AK3.04 because it is the only WA in this area with an importance rating at 2.5 or above.

AK3.01 (IR 2.0), AK3.02 (IR 2.2), AK3.03 (IR 2.0) rejected based on IR ~ 2 . 5 .

T2G1 206000 K4.05 Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Preventing water hammer in turbine exhaust line (procedural control). Not applicable to facility design (no turbine).

I T2G1 206000 K4.14 Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Control oil to turbine speed controls. Not applicable to facility design (no turbine).

T2G1 209001 K1.04 Knowledge of the physical connections and/or cause-effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the following: condensate transfer system (IR 2.3) is <2.5.

T2G 1 215004 K2 Selected K2.01 because it is the only WA in this area with an importance rating at 2.5 or above. K2.02 (IR 2.1). K2.03 ( IR 2.0) rejected based on IR ~ 2 . 5 .

T2G1 223002 K2.01 Knowledge of electrical power supplies to the following: Logic power supplies.

Only WA is K2.01 whose IR (2.4) is <2.5. Randomly selected WA A3.01.

T2G1 262002 K2 KA listed as none. Randomly selected WA A3.01.

T2G2 201001 K5.04 Knowledge of the operational implications of the following concepts as they apply to CONTROL ROD DRIVE HYDRAULIC SYSTEM: Indications of pump cavitation.

IR (2.4) is ~ 2 . 5 .

T2G2 201001 K5.07 Knowledge of the operational implications of the following concepts as they apply to CONTROL ROD DRIVE HYDRAULIC SYSTEM: Air operated control valves.

IR (2.3) is <2.5.

T2G2 216000 K5.05 Knowledge of the operational implications of the following concepts as they apply to NUCLEAR BOILER INSTRUMENTATION:Vessel vibration measurement (loose parts monitor). IR (2.3) is <2.5.

T2G2 290002 A3 KA listed as none. Randomly selected A4; WA listed as none. Randomly selected K3.07.

T3 2.1 Rejected WAS with IR <2.5 from selection: 2.1.4 (IR 2.3). 2.1.5 (IR 2.3), 2.1.6 (IR 2.1),2.1.13(IR2.0),2.1.15(2.3),2.1.26(IR2.2),2.1.34(lR2.3). Nosite-specific priorities related to WAS with IR e2.5.

T3 2.1.16 Ability to operate plant phone / paging system / and two-way radio. Better evaluated during the operating test (simulator scenarios).

T3 2.1.21 Ability to obtain and verify controlled procedure copy. Better evaluated during the operating test (simulator JPMs).

1 of2 NUREG-1021, Draft Revision 9

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UNIT 1 NRC (RO)

Facility: Nine Mile Point Unit 1 Date of Exam: June 17,2005 T3 2.1.22 Ability to determine Mode of Operation. This WA was on the 2004 Audit Exam.

Rejected to avoid any overlap between the Audit exam and the NRC re-exam.

T3 2.1.27 Knowledge of system purpose and or function. LOD = 1. Low cognitive level.

T3 2.1.30 Ability to locate and operate components I including local controls. Better evaluated during the walkthrough examination (JPMs).

T3 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. Rejected to avoid over sampling . - Tech Specs. See 295026 2.1.33 and 207000 2.1.33.-

T3 2.2 Rejected WAS with IR <2.5 from selection: 2.2.5 (IR 1.6), 2.2.6 (IR 2.3). 2.2.7 (IR 2.0). 2.2.8 (IR 1.8), 2.2.9 (IR 2.0). 2.2.10 (IR 1.9), 2.2.14 (IR 2.1), 2.2.15 (IR 2.2).

2.2.16 (IR 1.9), 2.2.17 (IR 2.3), 2.2.18 (IR 2.3), 2.2.19 (IR 2.1), 2.2.20 (IR 2.2).

2.2.21 (IR 2.3). 2.2.29 (IR 1.61, 2.2.31 (IR 2.2). 2.2.32 (IR 2.3). No site-specific priorities related to WAS with IR <2.5.

T3 2.2.23 Ability to track limiting conditions for operations. Rejected based on SRO Only.

T3 2.2.27 Knowledge of the refueling process. Rejected to avoid over sampling in the Refueling area. See 234000 K6.04 and G 2.2.30.

T3 2.3 Rejected WAS with IR ~ 2 . 5from selection: 2.3.3 (IR 1.8). 2.3.5 (IR 2.3). 2.3.6 (2.1),

2.3.7 (2.0), 2.3.8 (2.3). No site-specific priorities related to WAS with IR <2.5.

T3 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

This WA was on the 2004 Audit Exam. Rejected to avoid any overlap between the Audit exam and the NRC re-exam.

T4 2.4 Rejected WAS with IR <2.5from selection: 2.4.28 (IR). 2.4.30 (IR), 2.4.33 (IR),

2.4.36 (IR), 2.4.37 (IR), 2.4.38 (IR), 2.4.40 (IR). 2.4.41 (IR), 2.4.42 (IR). 2.4.44 (IR).

No site-specific priorities related to WAS with IR ~ 2 . 5 .

T3 2.4.34

.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications. Better evaluated during the walkthrough examination (In Plant JPMs).

T3 2.4.39 Knowledge of the R O s responsibilities in emergency plan implementation. This K/A was on the 2004 Audit Exam. Rejected to avoid any overlap between the Audit exam and the NRC re-exam.

T3 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. Better evaluated during the operating test (simulator scenarios).

T1, T2. T3 NONE No change required since each applicable WA category is sampled at least twice within each of the three tiers.

V I CHANGES

-- Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF A.C.

POWER and the following: A.C. electrical distribution system. Rejected based on double jeopardy with 262001 K1.03. 262001 K1.03 is Knowledge of the physical connections and/or cause-effect relationships between A.C. ELECTRICAL DISTRIBUTION and the following: Off-site power sources. Randomly selected which of the two WAS to be changed which was 295003, then randomly selected a new WA in the K2 category.

Ability to predict and/or monitor changes in parameters associated with operating the CCWS controls including: CCW temperature. Rejected based on double jeopardy with 400000 A2.03. 400000 A2.03 is Ability to (a) predict the impacts of the following on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Highnow CCW temperature. Randomly selected Al.03. CCW Pressure.

POST NRC OUTLINE REVIEW CHANGE 1

POST NRC EXAM REVIEW CHANGES I I 2of2 NUREG-1021, Draft Revision 9