ML023240407

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Final - Outlines (Change Summaries - Optional)
ML023240407
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 09/27/2002
From: Pisano L
Constellation Nuclear
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-220/02-303, ES-401, ES-401-1 50-220/02-303
Download: ML023240407 (25)
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Text

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~v7 Ae~CL ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, SI)

Facility: Nine Mile Point Unit I Date of Exam: 09/30102 Exam Level: SRO K/A Category Points Tier Group K K K K K K A A A A G Point 1 2 3 4 5 6 1 2 3 4 Total

1. 1 4 5 0 7 4 6 26 Emergency & 2 3 3 3 2 3 3 17 Abnormal P lant T otals Evolutions Totals 1 2 1 2 2 2 1 3 2 3 1 4 23
2. 2 1 1 1 1 1 2 1 1 1 1 2 13 Plant 3 1 0 0 1 0 0 1 0 0 0 1 4 Systems Tier 4 2 3 4 3 3 5 3 4 2 7 40 Totals Cat I Cat 2 Cat 3 Cat 4
3. Generic Knowledge and Abilities 5 4 4 4 17 Note: 1. Ensure that at least two topics from every KIA category are sampled within each tier (i.e., 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 +/-1 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 K/A 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 K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A 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. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

sVR SRO Examination OutlineForm ES-401-1 (R8, Sl)

Emergency and Abnormal Plant Evolutions - Tier I/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295003 Partial or Complete Loss of AC Pwr / 6 X X 2.4.41 - Knowledge of the emergency action level threshold and 4.1 1 classification SR0021 AA1.01 - Ability to operate and/or monitor the following as they apply to Partial or complete loss of AC power: AC electrical distribution system 3.8 1 RO026,SRO019 295006 Scram/!1 X AA2.02 - Ability to determine and/or interpret the following as they apply 4.4 1 to Scram: Control Rod position RO008,SRO017 295007 High Reactor Pressure 3 X X AK2.05 - Knowledge of the interrelations High Reactor Pressure and 3.1 1 the following: Shutdown cooling RO001,SRO002 2.1.33 -Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications 4.0 RO009,SRO001 295009 Low Reactor Water Level /2 X X AK1.05 - Knowledge of the operational applications of the following 3.4 1 concepts as they apply to the Low Reactor Water Level: Natural circulation R0002,SRO003 AA1.01 - Ability to operate and/or monitor the following as they apply to 3.9 Low Reactor Water Level: Reactor feedwater RO003,SRO004 295010 High Drywell Pressure /5 X AAI.03 - Ability to operate and/or monitor the following as they apply to 2.6 1 High Drywell Pressure: Nitrogen makeup RO004,SRO005 295013 High Suppression Pool Temp. 15 X X AK1.04 - Knowledge of the operational applications of the following 3.2 1 concepts as they apply to the High Suppression Pool Temp: Complete condensation R0020,SRO006 AK2.01 - Knowledge of the interrelations between High Suppression 3.7 1 Pool Temp and the following: Suppression pool cooling R0021,SRO007 295014 Inadvertent Reactivity Addition /I X AA1.07 - Ability to operate and/or monitor the following as they apply to 4.1 1 Inadvertent Reactivity Addition: Cold water injection R0005,SRO008 295015 Incomplete SCRAM/ 1X X AK2.04 - Knowledge of the interrelations between Incomplete SCRAM 4.1 1 and the following: RPS R0006,SRO009 AK1.04 - Knowledge of the operational implications of the following concepts as they apply to Incomplete SCRAM: Reactor pressure 3.8 RO0007,SRO010 295016 Control Room Abandonment /7 X X AA1.03 - Ability to operate and/or monitor the following as they apply to 3.1 1 Control Room Abandonment: RPIS RO022,SRO012 AA2.02 - Ability to determine and interpret the following as they apply to Control Room Abandonment: Reactor water level R0028,SRO011 4.3 1 295017 High Off-site Release Rate / 9 X X AA2.0t - Ability to determine and interpret the following as they apply to I High Off-site Release Rate: Off-site release rate SRO013 2.2.25 - Knowledge of bases in technical specifications for limiting

/.

UZ/,/IUIU  !:oo MlvI 1::-4U1-1 Page NM Log # 1-02-092

onditions for operations and safety limits SR0014

__ * +

295023 Refueling Accidents / 8 X IX AA1.06 - Ability to operate and/or monitor the following as they apply to 3I4; Refueling Accidents: Neutron monitoring R0034,SRO016 AA2.05 - Ability to determine and interpret the following as they apply to Refueling Accidents: Entry conditions of emergency plan SRO015 1 295024 High Drywell Pressure / 5 X 2.1.23 - Ability to perform specific system and integrated plant

  • 1 procedures during different modes of plant operation SR0024 295026 Suppression Pool High Water Temp. / 5 X EK2.03 - Knowledge of the interrelations between Suppression Pool 3.6 1 High Water Temp and the following: Suppression chamber pressure R0025,SRO0I18 295030 Low Suppression Pool Water Level / 5 X 2.1.32 -Ability to explain and apply system limits and precautions i I SRO020 295037 SCRAM Condition Present and Power X X EK2.13 - Knowledge of the interrelations between SCRAM Condition 4.1 1 Above APRM Downscale or Unknown /1 Present and Power Above APRM Downscale or Unknown and the following: Alternate boron injection methods R0011,SR0022 EAI.01 - Ability to operate and/or monitor the following as they apply to 4.6 1 SCRAM Condition Present and Power Above APRM Downscale or Unknown: RPS RO012,SR0023 295038 High Off-site Release Rate 19 X 2.3.9 - Knowledge of the process for performing a containment purge 3.4 1 R00311,SRO025 500000 High Containment Hydrogen Conc. /5 X EKI.01 - Knowledge of the operational applications of the following 3.9 1 concepts as they apply to the High Containment Hydrogen Conc:

Containment integrity R0013,SR0026 K/A Category Totals: T [ 5 110 i7 4 [F6 J Group PointTotal: ] 26 09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

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ES-401 ES-401 BWR SRO Examination OutlineForm ES-401-1 (R8, SI)

Emergency Emergency and Abnormal Plant Evolutions - Tier I/Group 2 E/APE # / Name / Safety Function K K K A A GK/A Topic(s) Imp. Points 1 2 3 1 2 295001 Partial or Complete Loss of Forced Core X X AA1.05 - Ability to operate and/or monitor the following as they apply to 3.3 1 Flow Circulation / 1 &4 Partial or Complete Loss of Forced Core Flow Circulation:

Recirculation flow control R0014,SR0028 AK2.01 - Knowledge of the interrelations between Partial or Complete 3.7 1 Loss of Forced Core Flow Circulation and the following: Recirculation System SR0027 295002 Loss of Main Condenser Vacuum 13 X AK3.02 - Knowledge of the reasons for the following responses as they 3.4 1 apply to Loss of Main Condenser Vacuum: Turbine trip ROO16,SR0029 295004 Partial or Total Loss of DC Pwr / 6 X AK2.01 - Knowledge of the interrelations between Partial or Total Loss 3.1 1 of DC Pwr and the following: Battery charger R0018,SRO031 295008 High Reactor Water Level/I 2 X AK1.02 - Knowledge of the operational implications of the following 2.8 1 concepts as they apply to High Reactor Water Level:

Component/erosion damage RO017,SRO030 295018 Partial or Total Loss of CCW / 8 X X AA1.01 - Ability to operate and/or monitor the following as they apply to 3.4 1 Partial or Total Loss of CCW: Backup systems R0023,SRO034 2.4.9 - Knowledge of low power/shutdown implications in accident (eg.

LOCA or loss of RHR) mitigation strategies SR0033 295022 Loss of CRD Pumps / I X AK2.07 - Knowledge of the interrelations between Loss of CRD Pumps 3.6 1 and the following: Reactor pressure (scram assist) R0024,SR0035 295028 High Drywell Temperature/ 5 X X X EK1.01 - Knowledge of the operational applications of the following 3.7 1 concepts as they apply to the High Drywell Temperature: Reactor Water level measurement RO019,SR0032 EK3.04 - Knowledge of the reasons for the following responses as they 3.8 1 apply to High Drywell Temperature: Increased drywell cooling R0027,SR0037 EA2.04 - Ability to determine and interpret the following as they apply to High Drywell Temperature: Drywell pressure SR0036 295032 High Secondary Containment Area X EK3.01 - Knowledge of the reasons for the following responses as they 3.8 1 Temperature / 5 apply to High Secondary Containment Area Temperature:

Emergency/normal depressurization RO035,SRO041 295033 High Secondary Containment Area X EK1.02 - Knowledge of the operational applications of the following 4.2 1 Radiation Levels 19 concepts as they apply to the High Secondary Containment Area Radiation Levels: Personnel protection R0029,SRO038 09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

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295034 Secondary Containment Ventilation High X X EA2.02 - Ability to determine and interpret the following as they apply to Radiation / 9 Secondary Containment Ventilation High Radiation: Cause of high radiation levels SR0039 2.4.18 - Knowledge of the specific bases for EOPs SR0040 600000 Plant Fire On Site / 8 X X AAI.05 - Ability to operate and/or monitor the following as they apply to 3.1 1 Plant Fire On Site: Plant and control room ventilation systems RO032,SRO043 2.4.30 - Knowledge of which events related to system operations/status

  • 1 should be reported to outside agencies SR0042 K/ACategoryUPoint Totals: 3 [3 3 1 3 2I3 1 Group Point Total: 1 17 09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

ES-4t,. R SRO Examination OutlineForm ES-401-1 (R8, SI)

Plant Systems - Tier 2/Group I System # / Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 206000 HPCI X X A2.05 - Ability to (a) predict the impacts of 3.8 1 the following on the HPCI and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: DC failures R0039,SRO044 A3.07 - Ability to monitor automatic 3.8 operations alarms of the HPCI including: Lights and R0040,SRO045 207000 Isolation (Emergency) Condenser X 2.1.12 -Ability to apply technical 1

.__specifications for a system SR0055 209001 LPCS X X A1.03 - Ability to predict and/or monitor 3.9 1 changes in parameters associated with operating the LPCS controls including:

Reactor water level R0041,SR0046 A4.09 - Ability to manually operate and/or 3.5 monitor in the control room: Suppression pool level R0042,SRO047 211000 Standby Liquid Control System X 2.1.33 -Ability to recognize indications for (Liquid Poison) system operating parameters which are entry level conditions for technical specifications SR0057 212000 RPS X 2.4.21 - Knowledge of the parameters and logic used to assess the status of safety functions including: SR0048 215004 Source Range Monitor X X K4.06 - Knowledge of Source Range 3.2 Monitor design feature(s) and or interlock(s) which provide for the following: IRM/SRM interlock R0044,SRO049 K5.03 - Knowledge of the operational 2.8 implications of the following concepts as they apply Changingto the Source Range Monitor:

detector position R0045,SRO050 215005 APRM / LPRM X X K2.02 - Knowledge of electrical power 2.8 supplies to the following: APRM channels R0046,SRO051 A1.03 - Ability to predict and/or monitor changes in parameters associated with 3.6 operating the APRM/LPRM controls including:

R0047,SR0052 Control rod block status

)49flAAf A ne X A3.03 - Ability to monitor automatic onnrafionn of the ADS. inrlHi. ,JýAr,%hI 3.8 I 09/20/02 9:56 AM nnArntion nfth. Afl inrliirin,, Afl 3.8 b-*.1u1-1 rage NM Log # 1-02-092

acoustical monitor noise ROO50.SRO053 f-I--I- 4 I- .1- l--l.--l-------J- acoustical monitor noise R0050.SR0053 I ______

223001 Primary CTMT and Auxiliaries X K1.10 - Knowledge of the physical 3.1 1 connections and/or cause-effect relationships between Primary CTMT and Auxiliaries and the following: Plant air systems RO052,SRO054 223002 PClSINuclear Steam Supply Shutoff X 2.4.6 - Knowledge of symptom based EOP 40. 1 strategies SR0056 226001 RHR/LPCI: CTMT Spray Mode X K5.06 - Knowledge of the operational 2.8 1 implications of the following concepts as they apply to the RHR/LPCI: CTMT Spray Mode:

Vacuum breaker operation R0071,SR0058 239002 SRVs X X K3.01 - Knowledge of the effect that a loss or 4.0 malfunction of the SRVs will have on the following: Reactor pressure control R0056,SRO060 A1.05 - Ability to predict and/or monitor 3.4 changes in parameters associated with operating the SRVs controls including:

Reactor Water level R0055,SR0059 241000 Reactor/Turbine Pressure Regulator X KI.01 - Knowledge of the physical 3.9 connections and/or cause-effect relationships between Reactor/Turbine Pressure Regulator and the following: Reactor power R0057,SR0061 259002 Reactor Water Level Control X X K4.13 - Knowledge of Reactor Water Level 3.6 Control design feature(s) and or interlock(s) which provide for the following: FWRV lockup R0059,SR0062 A2.03 - Ability to (a) predict the impacts of 3.7 the following on the Reactor Water Level Control and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of reactor water level input R0060,SR0063 261000 SGTS X K3.03 - Knowledge of the effect that a loss or 3.4 malfunction of the SGTS will have on the following: Primary containment pressure:

Mark I&ll R0061,SR0064 262001 AC Electrical Distribution x K6.03 - Knowledge of the effect that a loss or 3.7 malfunction of the following will have on the AC Electrical Distribution: Generator trip R0074,SR0065 264000 EDGs X A3.05 - Ability to monitor automatic 3.5 operations of the EDGs including: Load shedding and sequencing R0063,SR0066 K/A Category Point Totals: 2 J1 12 J2 12 i 13 I2 i3 11 J4 1Group Point Total: 23 09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

l ES-401BWR ES-401BWR SRO Examination OutlineForm ES-401-1 (R8, SI)

Plant Plant Systems - Tier 2/Group 2 System # / Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic X K6.03 - Knowledge of the effect that a loss or 2.9 1 malfunction of the following will have on the CRD Hydraulic: Plant air systems R0037,SRO067 201006 RWM X A4.03 - Ability to manually operate and/or 3.0 1 monitor inR0066,SRO068 indication the control room: Latched group 202001 Recirculation X X K3.08 - Knowledge of the effect that a loss 2.9 1 or malfunction of the Recirculation will have on the following: Shutdown cooling system R0067,SRO070 2.2.25 - Knowledge of the bases in technical specifications operations andfor limiting conditions for safety limits SR0069 204000 RWCU X 2.1.32 -Ability to explain and apply system 3.8 1 limits and precautions R0068,SRO071 219000 RHR/LPCI: Torus/Pool Cooling Mode X X K2.01 - Knowledge of electrical power 3.3 1 supplies to the following: Valves R0069,SRO072 A1.03 - Ability to predict and/or monitor 2.9 1 changes in parameters associated with operating the RHR/LPCI: Torus/Pool Cooling Mode controls including: System pressure R0070,SRO073 245000 Main Turbine Gen. and Auxiliaries X K5.02 - Knowledge of the operational 3.1 1 implications of the following concepts as they apply to the Main Turbine Gen. and Auxiliaries: Turbine operations and limitations R0072,SRO074 97nn i r- iff-*n X K4.08 - Knowledge of Offgas design 3.3 feature(s) and or interlock(s) which provide I for the following: Automatic system isolation RO076,SRO075 272000 Radiation Monitoring R0076,SR007 X A3.09 - Ability to monitor automatic 3.5 operations of the Radiation Monitoring I including: Containment isolation indications R0077,SR0076 290003 Control Room HVAC ______ 1 I---t I--p- I 4-.-I-X KI.01 - Knowledge of the physical 3.5 connections and/or cause-effect relationships I between Control Room HVAC and the 09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

/

I I . I following: Radiation monitors R0080,SR0077 2.9 1 K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the Control Room HVAC: Component cooling water systems RO081,SR0078 400000 Compon I -t T 1 1 r T --

x 1 1 t-t ________ ___________

.IlL %ootfUIlI VndWtr A2.02 - Ability to (a) predict the impacts of 3.0 1 the following on the Component Cooling Water and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High/low surne. tank level R0083 SR*nn-CA t K/A Category Point Totals: L~iliI 11 2Lt r1117t1 2 ~

GroupPoint TI ota.l:___

09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

K !i t ES-401BWR SRO Examination OutlineForm ES-401-1 (R8, SI)

Plant Systems - Tier 2/Group 3 System # / Name K K K K K K6 Al A2 A3 A4 G KJA Topic(s) Imp. Points 1 2 3 4 5 201003 Control Rod and Drive Mechanism X X K4.04 - Knowledge of Control Rod and 3.7 1 Drive Mechanism design feature(s) and or interlock(s) which provide for the following: the use of either accumulator or reactor water to SCRAM the control rod R0065,SRO80 2.1.14 - Knowledge of system status 1 I criteria which require the notification of plant personnel SR0081 215001 Traversing In-core Probe X A1.01 - Ability to predict and/or monitor 2.9 1 changes in parameters associated with operating the Traversing In-core Probe controls including: Radiation levels R0084,SRO082 233000 Fuel Pool Cooling and Cleanup X K1.14 - Knowledge of the physical 2.5 1 connections and/or cause-effect relationships between Fuel Pool Cooling and Cleanup and the following: Reactor building ventilation R0086,SRO083 K/A Category Point Totals: 1 0 0 1 0 0 1 0 0 0 1 Group Point Total: 4 Plant-Specific Priorities System / Topic Recommended Replacement for... Reason Points 295009 AA1.01 295009 AK3.02 Appropriate question could not be developed 1 295024 2.1.23 295038 EK1.03 Written as RO only but is better SRO only 1 question as written 295028 EKI.01 295012 AK1.02 Appropriate question could not be developed I to original KA without resulting In oversampling.

295018 AAI.01 295018 AAI.03 Appropriate question could not be developed 1 295006 AA2.02 295024 EA2.01 Appropriate question could not be developed I 239002 A1.05 239002 A1.01 Appropriate question could not be developed I Plant-Specific Priority Total (limit 10): 16 09/20/02 9:56 AM ES-401-1 Page NM Log # 1-02-092

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ES-401 BWR RO Examination Outline Form ES-401-2 (R8, SI)

Facility: Nine Mile Point Unit I Date of Exam: 09/30/02 Exam Level: RO K/A Category Points Point Tier Group K K K K K K A A AA G Total 1 3 3 0 4 2 1 13 Emergency& 2 4 4 2 5 2 2 19 Abnormal 3 0 0 2 1 0.. 1 4 Plant Tier 7 7 4 10 4 4 36 Evolutions Ttl Totals A 1 3 1 3 3 3 1 4 3 3 3 1 28

2. 2 2 2 2 2 2 2 2 2 1 1 1 19 Plant 3 1 0 0 0 0 1 1 1 0 0 0 4 Systems Tier 6 3 j 5 5 47 6 4 4 2 51 Totals
3. Generic Knowledge and Abilities f Cat 1

-C a 2 2

Cat32a 4 Cat4 13 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A 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 +/-1 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 K/A 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 K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A 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. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, S1)

Emergency and Abnormal Plant Evolutions - Tier l/Group I E/APE # / Name I Safety Function K/A Topic(s) Imp. Points 295006 Scram/!1 X AA2.02 - Ability to determine and/or interpret the following as they apply 4.3 1 to Scram: Control Rod position R0008,SR0017 295007 High Reactor Pressure 3 X X AK2.05 - Knowledge of the interrelations High Reactor Pressure and 2.9 1 the following: Shutdown cooling ROOO1,SR0002 2.1.33 - Ability to recognize indications for system operating parameters 3.4 1 which are entry-level conditions for technical specifications R0009,SR0001 295009 Low Reactor Water Level / 2 X X AK1.05 - Knowledge of the operational applications of the following 3.3 1 concepts as they apply to the Low Reactor Water Level: Natural circulation R0002,SRO003 AA1.01 - Ability to operate and/or monitor the following as they apply to 3.9 1 Low Reactor Water Level: Reactor feedwater R0003,SRO004 295010 High Drywell Pressure / 5 X AA1.03 - Ability to operate and/or monitor the following as they apply to 2.6 1 High Drywell Pressure: Nitrogen makeup R0004,SR0005 295014 Inadvertent Reactivity Addition 1 X AA1.07 - Ability to operate and/or monitor the following as they apply to 4.0 1 Inadvertent Reactivity Addition: Cold water injection R0005,SR0008 295015 Incomplete SCRAM / I X X AK2.04 - Knowledge of the interrelations between Incomplete SCRAM 4.0 1 and the following: RPS R0006,SR0009 AK1.04 - Knowledge of the operational implications of the following 3.8 1 R00007,SR0010 concepts as they apply to Incomplete SCRAM: Reactor pressure 295025 High Reactor Pressure / 3 X EA2.01 - Ability to determine and interpret the following as they apply to High Reactor Pressure: Reactor I1 pressure RO010 295037 SCRAM Condition Present and Power X X EK2.13 Present-and Knowledge of the interrelations between SCRAM Condition 3.4 Power Above APRM Downscale 1 or Unknown and the following: Alternate boron injection methods RO011,SR0022 EA1.01 - Ability to operate and/or monitor the following as they apply to 4.6 1 SCRAM Condition Present and Power Above APRM Downscale or Unknown: RPS R0012,SR0023 500000 High Containment Hydrogen Conc. 5 X EK1.01 - Knowledge of the operational applications of the following 3.3 1 concepts as they apply to the High Containment Hydrogen Conc:

Containment integrity R0013,SR0026 K/A Category Totals: [3 13 10 [4 [2 I ] Group Point Total: J 13 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name I Safety Function K K K A A G K/A Topic(s)

Imp. Points 1 2 3 1 2 295001 Partial or 4 Loss of Forced Core X X AAI.05 - Ability to operate and/or monitor the following as they apply to Partial or Complete Loss of Forced 3.3 1 Core Flow Circulation:

Recirculation flow control R0014,SR0028 AA2.02 - Ability to determine and interpret the following as they apply to Partial or Complete Loss of Forced Core Flow Circulation: Neutron 1 295002 Loss of Main Condenser Vacuum / 3

-- monitoring RO015 X AK3.02 - Knowledge of the reasons for the following responses as they 3.4 1 apply to Loss of Main Condenser Vacuum: Turbine trip RO16,SR0029 295003 Partial or Complete Loss of AC Pwr / 6 X AAI.01 - Ability to operate and/or monitor the following as they apply to 3.7 1 Partial or complete loss of AC power: AC electrical distribution system R0026,SRO019 295004 Partial or Complete Loss of DC Pwr / 6 X AK2.01 - Knowledge of the interrelations between Partial or Total Loss 3.1 1 of DC Pwr and the following: Battery charger R0018,SR0031 295008 High Reactor Water Level / 2 X AK1.02 - Knowledge of the operational applications of the following 2.8 1 concepts as they apply to the High Reactor Water Level:

Component/erosion damage R0017,SRO030 295013 High Suppression Pool Temp. 15 X X AKI.04 - Knowledge of the operational applications of the following 2.9 1 concepts as they apply to the High Suppression Pool Temp: Complete condensation R0020,SRO006 AK2.01 Pool - Knowledge Temp of the interrelations between High Suppression and the following: 3.6 1 Suppression pool cooling R0021,SR0007 295016 Control Room Abandonment / 7 X X AA1.03 - Ability to operate and/or monitor the following as they apply to 3.0 1 Control Room Abandonment: RPIS R0022,SRO012 AA2.02 - Ability to determine and interpret the following as they apply to 4.2 1 Control Room Abandonment: Reactor water level R0028,SRO01 1 295018 Partial or Complete Loss of CCW / 8 X AAI.01 - Ability to operate and/or monitor the following as they apply to 3.3 1 Partial or Total Loss of CCW: Backup systems R0023,SR0034 295022 Loss of CRD Pumps / 1 X AK2.07 - Knowledge of the interrelations between Loss of CRD Pumps 3.4 1 and the following: Reactor pressure (scram assist) R0024,SR0035 295026 High Suppression Pool Water Temp. / 5 X EK2.03 - Knowledge of the interrelations between Suppression Pool 3.2 1 High Water Temp and the following: Suppression chamber pressure I__I R0025,SRO018 295028 High Drywell Temperature / 5 X X EKI.01 - Knowledge of the operational applications of the following concepts as 3.5 1 I they apply to the High Drywell Temperature: Reactor Water level measurement I 09/20102 9:59 AM ES-401-2 Page NM Log # 1-02-093

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R0019,SR0032 EK3.04 - Knowledge of the reasons for the following responses as they apply to High Drywell Temperature: Increased drywell cooling R0027,SR0037 3.6 1 295029 High Suppression Pool Water Level / 5 X 2.1.30 Ability to locate and operate components/including local controls U 1 R0030 295033 High Sec. Cont. Area Rad. Levels 1 9 X EK1.02 - Knowledge of the operational applications of the following 3.9 1 concepts as they apply to the High Secondary Containment Area Radiation Levels: Personnel protection R0029,SRO038 295038 High Off-site Release Rate /9 X 2.3.9 - Knowledge of the process for performing a containment purge 2.5 1 RO031 ,SRO025 600000 Plant Fire On Site / 8 X AAt.05 - Ability to operate and/or monitor the following as they apply to 3.0 1 Plant Fire On Site: Plant and control room ventilation systems R0032,SRO043 K/A Category Point Totals: I4 [4 I 2 ] 5 12 2 J Group Point Total: ] 19 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)

Emergency and Abnormal Plant Evolutions - Tier l/Group 3 EIAPE # I Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295021 Loss of Shutdown Cooling 14 X AK3.01 - Knowledge of the reasons for the following responses as they Aga 1

_ apply to Loss of Shutdown Cooling: raising reactor water level R0033 295023 Refueling Accidents / 8 X AA1.06 - Ability to operate and/or monitor the following as they apply to 3.3 1 Refueling Accidents: Neutron monitoring R0034,SROOI6 95032 High Secondary Containment Area X EK3.01 - Knowledge of the reasons for the following responses as they Temperature / 5 3.5 1 apply to High Secondary Containment Area Temperature:

Emergency/normal depressurization R0035,SR0041 295036 Secondary Containment High X 2.4.50 -Ability to verify system alarm setpoints and operate controls Sump/Area Water Level / 6 identified in the alarm response manual R0036 K/A Category Point Totals: I [0I0 I2 1 _ I Group Point Total: - 4 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

t ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, S1)

Plant Systems - Tier 2/Group I System #/Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 201001 CRID Hydraulic X K6.03 - Knowledge of the effect that a loss or 3.0 malfunction of the following will have on the CRD Hydraulic: Plant air systems R0037,SR0067 202002 Recirculation Flow Control K5.02 - Knowledge of the operational 2&

implications of the following concepts as they apply to the Recirculation Flow Control:

Feedback signals R0038 206000 HPCI X A2.05 - Ability to (a) predict the impacts of 3.5 the following on the HPCI and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: DC failures R0039,SR0044 A3.07 - Ability to monitor automatic 3.9 operations of the HPCI including: Lights and alarms R0040,SR0045 209001 LPCS X X A1.03 - Ability to predict and/or monitor 3.8 changes in parameters associated with operating the LPCS controls including:

Reactor water level R0041,SR0046 A4.09 - Ability to manually operate and/or 3.6 monitor in the control room: Suppression pool level R0042,SR0047 212000 RPS X A1.09 -Ability to predict and/or monitor  ?

changes in parameters associated with operating the RPS controls including:

Individual relay status R0043 215004 SRM X X K4.06 - Knowledge of Source Range 3.2 Monitor design feature(s) and or interlock(s) which provide for the following: IRM/SRM interlock R0044,SR0049 K5.03 - Knowledge of the operational 2.8 implications of the following concepts as they apply to the Source Range Monitor:

Changing detector position R0045,SRO050 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

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215005 APRM / LPRM X X K2.02 - Knowledge of electrical power supplies to 2.6 the following: APRM channels R0046,SRO051 A1.03 - Ability to predict and/or monitor changes in parameters associated with operating the APRMILPRM controls including: Control rod block 3.6 status R0047,SR0052 216000 Nuclear Boiler Instrumentation X X K3.30 - Knowledge of the effect that a loss

  • or malfunction of the Nuclear Boiler Instrumentation will have on the following:

Recirculation system R0048 2.4.10 - Knowledge of annunciator response procedures R0049 218000 ADS X X K5.01 - Knowledge of the operational 1 implications of the following concepts as they apply to the ADS: ADS logic operation R0051 A3.03 - Ability to monitor automatic operations of the ADS including: ADS valve 3 acoustical monitor noise R0050,SR0053 223001 Primary CTMT and Auxiliaries K1.10 - Knowledge of the physical 3.0 connections and/or cause-effect relationships between Primary CTMT and Auxiliaries and the following: Plant air systems R0052,SR0054 K4.05 - Knowledge of Primary CTMT and Auxiliaries design feature(s) and or L, interlock(s) which provide for the following:

Maintains proper suppression pool to drywell differential pressure R0053 223002 PCIS/Nuclear Steam Supply Shutoff X A4.01 - Ability to manually operate and/or

  • monitor in the control room: Valve closures R0054 239002 SRVs XX K3.01 - Knowledge of the effect that a loss or 3.9 malfunction of the SRVs will have on the following: Reactor pressure control R0056,SR0060 3.7 A1.05 - Ability to predict and/or monitor changes in parameters associated with operating the SRVs controls including:

Reactor Water level R0055,SR0059

~* ~

-- * *Lli ~ zul . *rI ... us reU r eg ayl oLr A K1.01 - Knowledge of the physical 3.8 1 X connections and/or cause-effect relationships between Reactor/Turbine Pressure Regulator and the following: Reactor power R0057,SR0061 K1.09 - Knowledge of the physical I 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

1T-r 11rr,--1-T-r--, _________

connections and/or cause-effect relationships between Reactor/Turbine Pressure Regulator and the following: Combined intermediate valves R0058 259002 Reactor Water Level Control K4.13 - Knowledge of Reactor Water Level 3.5 Control design feature(s) and or interlock(s) which provide for the following: FWRV lockup R0059,SR0062 3.6 A2.03 - Ability to (a) predict the impacts of the following on the Reactor Water Level Control and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of reactor water level input R0060,SR0063 261000 SGTS - - K3.03 - Knowledge of the effect that a loss or 3.2 malfunction of the SGTS will have on the following: Primary containment pressure:

Mark I&lIR0061,SR0064 A4.09 - Ability to manually operate and/or monitor in the control room: Ventilation valves/dampers R0062 264000 EDGs A2.06 - Ability to (a) predict the impacts of *,<

the following on the EDGs and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

opening normal and/or alternate power to emergency bus R0064 A3.05 - Ability to monitor automatic 3.4 operations of the EDGs including: Load shedding and sequencing R0063,SR0066 K/A Category Point Totals: 3I 1 3 i3 I3 I1 4I 3 3 3 I Group Point Total: 28 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

fI 7E'S I

,VR RO Examination OutlineForm ES-401-2 (R8, S1)

Plant Systems - Tier 2/Group 2 System # / Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 201003 Control Rod and Drive Mechanism X K4.04 - Knowledge of Control Rod and 3.6 1 Drive Mechanism design feature(s) and or interlock(s) which provide for the following:

the use of either accumulator or reactor water to SCRAM the control rod I_ R0065,SRO80 201006 RWM X A4.03 - Ability to manually operate and/or 3.0 monitor in the control room: Latched group indication R0066,SR0068 202001 Recirculation X K3.08 - Knowledge of the effect that a loss 2.8 or malfunction of the Recirculation will have on the following: Shutdown cooling system R0067,SRO070 204000 RWCU X 2.1.32 -Ability to explain and apply system 3.4 1 limits and precautions R0068,SR0071 219000 RHR/LPCI: ToruslPool Cooling Mode X X K2.01 - Knowledge of electrical power 3.1 1 supplies to the following: Valves R0069,SR0072 A1.03 - Ability to predict and/or monitor 2.9 changes in parameters associated with operating the RHRJLPCI: Torus/Pool Cooling pressure Mode controls including: System R0070,SRO073 226001 RHR/LPCI: CTMT Spray Mode K5.06 - Knowledge of the operational 2.6 implications of the following concepts as they apply to the RHR/LPCI: CTMT Spray Mode:

Vacuum breaker operation R0071,SR0058 245000 Main Turbine Gen. and Auxiliaries X K5.02 - Knowledge of the operational 2.8 implications of the following concepts as they apply to the Main Turbine Gen. and Auxiliaries: Turbine operations and limitations R0072,SR0074 256000 Reactor Condensate X A1.03 - Ability to predict and/or monitor ZA changes in parameters associated with operating the Reactor Condensate controls including: System pressure R0073 262001 AC Electrical Distribution X K6.03 - Knowledge of the effect that a loss or 3.5 malfunction of the following will have on the AC Electrical Distribution: Generator trip R0074,SR0065 263000 DC Electrical Distribution X KI.01 - Knowledge of the physical connections and/or cause-effect relationships

_betweenDCElectrical Distribution and the 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

I I I I I I following: AC electrical distribution RO075

+/- F +I 271000 Offgas x K4.08 - Knowledge of Offgas design 3.1 _1_

feature(s) and or interlock(s) which provide for the following: Automatic system isolation RO076,SRO075

'117')RAA 0A;44 5 IonI;L ar,,a onV I IVUILoring x A3.09 - Ability to monitor automatic 3.6 I operations of the Radiation Monitoring including: Containment isolation indications RO077,SRO076 286000 Fire Protection X K2.02 - Knowledge of electrical power 1 supplies to the following: Pumps R0078 290001 Secondary CTMT X 290001 A2.01 - Ability to (a) predict the impacts of the following on the Secondary CTMT and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: personnel airlock failure R0079 290003 Control Room HVAC x X K11.01 - Knowledge of the physical 3.4 connections and/or cause-effect relationships between Control Room HVAC and the following: Radiation monitors R0080,SR0077 2.7 K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the Control Room HVAC: Component cooling water systems R0081,SR0078 300000 Instrument Air x K3.02 - Knowledge of the effect that a loss or malfunction of the Instrument Air will have on the following: systems having pneumatic valves and controls R0082 400000 Component Cooling Water X A2.02 - Ability to (a) predict the impacts of 2.8 the following on the Component Cooling Water and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High/low surge tank level R0083,SR0079 K/A Category Point Totals: 2 !2 12 i2 i2 j2 2 2 i 71 1I Group Point Total: 19 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

L---401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)

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Plant Systems - Tier 2/Group 3 System # / Name K K K K K K A A A A G 1 KIA Topic(s) Imp. Points 2 3 4 5 6 1 2 3 4 215001 Traversing In-core Probe X X K6.04 - Knowledge of the effect that a loss or 14 1 malfunction of the following will have on the Traversing In-core Probe: primary containment isolation system R0085 A1.01 - Ability to predict and/or monitor changes in parameters associated with 2.8 1 operating the Traversing In-core Probe controls including: Radiation levels R0084,SRO082 233000 Fuel Pool Cooling and Cleanup X K1.14 - Knowledge of the physical 2.5 connections and/or cause-effect relationships between Fuel Pool Cooling and Cleanup and the following: Reactor building ventilation R0086,SRO083 A2.15 - Ability to (a) predict the impacts of Z the following on the Fuel Pool Cooling and Cleanup and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High system temperature R0087 K/A Category Point Totals: I1 0 o0 f 0 0 1I1 1 I0 0 Group PointTotal: ' 4 Plant-Specific Priorities System I Topic Recommended Replacement Reason Points for...

295009 AA1.01 295009 AK3.02 Appropriate question could not be developed 1 295030 AA2.02 295030 EK3.02 Was SRO only KIA added to as a common 1 290001 A4.02 290001 A4.06 NMPCUI has a Reactor building not a Fuel 1 building swapped to applicable KIA 295028 EK1.01 295012 AK1.02 Appropriate question could not be developed to I original KA without resulting in oversampling.

295006 AA2.02 295024 EA2.01 Appropriate question could not be developed 1 295018 AA1.01 295018 AA1.03 Appropriate question could not be developed 1 239002 A1.05 239002 A1.01 Appropriate question could not be developed I Plant-Specific Priority Total: (limit 10) 7 09/20/02 9:59 AM ES-401-2 Page NM Log # 1-02-093

ES-401 Record of Rejected K/As Form ES-401-10 (i,-, SI)

Tier/ Randomly Selected Reason for Rejection Group K/A SRO Tier 1/Group 295009 AK3.02 Acceptable question could not be developed to original KA statement. Replaced with 295009 AA1.01 - Ability to operate and/or 1 monitor the following as they apply to Low Reactor Water Level: Reactor feedwater SRO Tier 1/Group 295038 EK1.03 Original K/A not appropriate for >LODI question replaced with 295024 2.1.23 - Ability to perform specific system and integrated plant 1 procedures during different modes of plant operation added as SRO only was RO only better SRO only as written SRO Tier 1/Group 295030 EK3.02 Original K/A not applicable to NMPCU1 design replaced with 295003 2.4.41 - Knowledge of the emergency action level threshold and 1 classification SRO Tier 1/Group 295038 2.1.32 Original K/A not appropriate for >LOD1 question replaced with 295038 2.3.9 - Knowledge of the process for performing a containment 1 purge SRO Tier 2/Group 223001 K6.10 Original K/A not applicable to NMPCU1 design replaced with 216000 2.4.6 - Knowledge of symptom based EOP strategies to SRO 1 exam only removed from RO exam better SRO only as written SRO Tier 2/Group 226001 K5.02 Original K/A not appropriate for >LOD1 question replaced with 226001 K5.06 - Knowledge of the operational implications of 1 the following concepts as they apply to the RHR/LPCI: CTMT Spray Mode: Vacuum breaker operation SRO Tier 2/Group 239002 K2.01 Original K/A not appropriate for >LOD1 question replaced with 239002 A1.01 - Ability to predict and/or monitor changes in parameters 1 associated with operating the SRVs controls including: Tail pipe temperature SRO Tier 2/Group 215001 A1.03 Original K/A double jeopardy with RO only question in same tier and system replaced with 215001 A1.01 - Ability to predict 3 and/or monitor changes in parameters associated with operating the Traversing In-core Probe controls including: Radiation levels SRO Tier 1/Group 295018 2.4.49 Original K/A not applicable to SRO only replaced with 2.4.9 - Knowledge of low power/shutdown implications in accident (eg. LOCA or 2 loss of RHR) mitigation strategies SRO Tier 1/Group 295034 2.4.49 Original K/A not applicable to SRO only replaced with 2.4.18 - Knowledge of the specific bases for EOPs 2

SRO Tier 2/Group 212000 2.4.49 Original K/A not applicable to SRO only replaced with 2.4.21 - Knowledge of the parameters and logic used to assess the status of 1 safety functions including:

SRO Tier 2/Group 226001 2.4.49 Original K/A not applicable to SRO only replaced with 2.4.22 - Knowledge of the bases for prioritizing safety functions during 1 abnormal/emergency operations RO Tier 1/Group 295009 AK3.02 Acceptable question could not be developed to original KA statement. Replaced with 295009 AA1.01 - Ability to operate and/or 1 monitor the following as they apply to Low Reactor Water Level: Reactor feedwater.

RO Tier 1/Group 295038 EK1.03 Original K/A not appropriate for >LOD1 question replaced with 295029 2.1.30 - Ability to locate and operate components/including 2 local controls RO Tier 1/Group 295030 EK3.02 Original K/A not applicable to NMPCU1 design replaced with 295030 AA2.02 - Ability to determine and interpret the following as they 2 apply to (nntrol Room Ahandonment. Reactnr water letvpl arddd to R0 as a both qgeqtion wag SRQ only K/A 09/20/02 9:56 AM ES-401-1O Page-i NM Log # 1-02-091 LI A 4d1 2 k*-,gj ci

ES-401 Record of Rejected K/As Form ES-401-10 (R8, SI)

RO Tier 1/Group 295038 2.1.32 Original K/A not appropriate for >LOD1 question replaced with 295038 2.3.9 - Knowledge of the process for performing a containment 2 purge RO Tier 2/Group 223001 K6.10 Original K/A not applicable to NMPCU1 design replaced with 223001 K4.05 - Knowledge of Primary CTMT 1 and Auxiliaries design feature(s) and or interlock(s) which provide for the following: Maintains proper suppression pool to drywell differential pressure RO Tier 2/Group 226001 K5.02 Original K/A not appropriate for >LOD1 question replaced with 226001 K5.06 - Knowledge of the operational 2 implications of the following concepts as they apply to the RHR/LPCI: CTMT Spray Mode: Vacuum breaker operation RO Tier 2/Group 239002 K2.01 Original K/A not appropriate for >LOD1 question replaced with 239002 A1.01 - Ability to predict and/or monitor 1 changes in parameters associated with operating the SRVs controls including: Tail pipe temperature RO Tier 2/Group 215001 A1.03 Original K/A double jeopardy with K6.04 question replaced with 215001 A1.01 - Ability to predict and/or monitor changes in parameters 3 associated with operating the Traversing In-core Probe controls including: Radiation levels RO Tier 1/Group 295024 2.1.23 Removed was RO only better SRO only as written replaced with 295005 2.1.33 - Ability to recognize indications for system operating 1 parameters which are entry-level conditions for technical specifications to RO exam RO Tier 2/Group 216000 2.4.6 Removed from RO exam better SRO only as written replaced with 216000 2.4.10 - Knowledge of annunciator response procedures 1

RO Tier 2/Group 202001 2.1.27 Original K/A not appropriate for >LOD1 question replaced with 204000 2.1.32 - Ability to explain and apply system limits and 2 precautions RO Tier 2/Group 290001 A4.06 NMPCU1 has RB not a Fuel Building replaced with 290001 A4.02 - Ability to manually operate and/or monitor in the control room:

2 Reactor building area temperatures RO Tier 3 2.2.3 Original K/A removed not applicable to NMPCU1 replaced with 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material RO Tier 3 2.3.11 Original 2.3.11 question written made better SRO only replaced with 2.3.4 - Knowledge of radiation exposure limits and contamination control/including permissible levels in excess of those authorized original added to SRO only L

09/20/02 9:56 AM ES-401-10 Page NM Log # 1-02-091

E.-401 Record u, Rejected K/As Form ES-401 -10 (rxd, SI)

The following changes were made after initial written outlines were submitted, during question development.

Tier I Randomly Selected Reason for Rejection Group K/A SRO Tier 1/Group 295026 EK3.03 Original K/A not applicable to NMPCU1 design replaced with 295003 AAt.01 - Ability 1 apply to Partial or complete loss of AC power: AC electrical distribution system to operate and/or monitor the following as they SRO Tier 1/Group 295036 EK2.02 Original K/A not applicable to NMPCU1 design replaced with 295036 EA2.01 - Ability 2 to determine and/or interpret the following as they apply to Secondary containment High sump/area water level: operability of components within the affected area RO Tier 1/Group 295026 EK3.03 Original K/A not applicable to NMPCU1 design replaced with 295003 AA1.01 - Ability to operate and/or monitor the following as they 2 apply to Partial or complete loss of AC power: AC electrical distribution system RO Tier 1/Group 295036 EK2.02 Original K/A not applicable to NMPCU1 design replaced with 295036 EA2.01 - Ability to determine and/or interpret the following as 3 they apply to Secondary containment High sump/area water level: operability of components within the affected area RO Tier 2/Group 290001 A4.02 Replaced with 290001 A2.01 - Ability to (a) predict the impacts of the following on the Secondary 2 CTMT and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: personnel airlock failure due to oversampling of system/topic RO Tier 2/Group 300000 K3.01 Original K/A not applicable to NMPCU1 design replaced with 300000 K3.02 - Knowledge of the effect that a loss or malfunction of the 2 Instrument Air System will have on the following: systems having pneumatic valves and RO SRO 295012 AK1.02 controls Question written to original KA results in over-sampling and double jeopardy. Replaced with 295028 EK1.01, which is a similar topic.

Tier l/Group2 RO SRO 295018 AA1.03 Appropriate question could not be developed. Replaced with 295018 AA1.01 Tier 1/Group 2

RO SRO 295024 EA2.01 Appropriate question could not be developed. Replaced with 295006 AA2.01 Tier 1/Group 1

RO SRO 239002 Al.01 Appropriate question could not be developed. Replaced with 295006 A1.05 Tier 2/

Group 1 RO Tier 219000 K2.02 Appropriate question could not be developed. Replaced with 219000 K2.01 2/Group2 SRO Tier 2/Group 1 ___________

SRO Tier 3 2.1.6 KA Statement is inappropriate for developing an acceptable written exam question at the SRO level. Replaced with 2.1.12 RO SRO 272000 K3.06 Due to system design, an applicable question could not be developed. Replaced with 272000 A3.09 Tier 2\Group 2

09/20/02 9:56 AM ES-401-10 Page NM Log # 1-02-091

L. 101 Record ,.. Aejected K/As Form ES-401-10 , Sl)

The following changes were made as a result of NRC exam review.

RO SRO 2.2.2 Appropriate Tier 3 generic question could not be developed to the original KA statement, which was system specific. Replaced with Tier 3 2.2.11 (RO 91 SRO 90)

RO SRO 2.4.24 Appropriate Tier 3 generic question could not be developed to the original KA statement, which was system specific. Replaced with Tier 3 2.1.10 (RO 97 SRO 97)

RO SRO 2.4.47 Appropriate Tier 3 generic question could not be developed to the original KA statement, which was system specific.. Replaced with Tier 3 2.4.32 (RO 94 SRO 96)

RO SRO 295004 AK1.04 Appropriate question could not be developed to the original KA statement. Replaced with 295008 AKI.02 Tier 1/Group (RO 17 SRO 30) 2 1 SRO 216000 2.4.6 Appropriate question could not be developed to the original KA statement. Replaced with 207000 2.1.12 Tier 2/Group (SRO 55) 1 SRO 226001 2.4.22 Eliminate overlap with other written questions and simulator scenarios. Replaced with 211000 2.1.33 Tier 2/Group (SRO 57) 1 SRO 295001 AA2.06 Eliminate overlap with operating test. Replaced with 295001 AK2.01 Tier 1/Group (SRO 27) 2 RO SRO 295015 AK3.01 Acceptable question could not be developed based on original KA statement. Unable to develop 3 plausible distractors. Replaced with Tier 1/Group 295015 AK1.04 (RO 07 SRO 10) 9/19/02.

1 i 1 r i i

___________________ L 09/20/02 9:56 AM ES-401-10 Page NM Log # 1-02-091

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