ML072960498

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July-August Exam 50-325, 324/2007301 Draft Written Exam Quality Checklist (ES-401-6 & Written Exam Sample Plan
ML072960498
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 05/25/2007
From: Suzanne Dennis
Carolina Power & Light Co
To:
NRC/RGN-III/DRS/OLB
References
50-324/07-301, 50-325/07-301, ES-401-6 50-324/07-301, 50-325/07-301, NUREG-1021, Rev 9
Download: ML072960498 (13)
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Text

Draft Submittal (Pink Paper)

DRAFT Written Exam Quality Checklist (ES-401-6)

& Written Exam Sample Plan BRUNSWICK JULY-AUG EXAM - .325,324/2007-301 DRAFT WRITTEN EXAM QUALITY CHE~KLIST (ES-401-6) & SAMP~E PLAN

ES-401 Written Examination Quality Checklist Form ES-401-6 Facilit : Brunswick Date of Exam: Jul 2007 Exam Level: RO/SRO Item Descr; tion a ic::::a::..:.

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2. a. NRC KlAs referenced for all questions.
b. Facilit learnin ob'ectives referenced as available. SO
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4. The sampling process was random and systematic. (If more than 4 RO and 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL Pro ram Office so
5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

_X_ the audit exam was systematically and randomly developed the audit exam was completed before the license exam was started the examinations were developed independently the licensee certifies that there is no duplication other ex lain 5t>

Bank use meets limits (no more than 75 percent 6.

from the bank at least 1 percent new, and the rest ° Bank Modified New new or modified); enter the actual RO / SRO-only uestion distribution s at ri ht.

43 /15

°/° 32/10 so

7. Between 50 and 60 percent of the question on the Memo CIA RO exam are written at the comprehension/

analysis level; the SRO exam may exceed 60

~ I/tIv 32 / 7 43 / 18

( percent if the randomly selected KlAs support the higher cognitive levels; enter the actual RO / SRO 'f uestion distribution s at ri ht So

8. References/handouts provided do not give away answers or aid in the elimination of distractors. 50
9. Question content conforms with specific KIA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; 5(7 10.

deviations are *ustified.

Question psychometric quality and format meet the guidelines in ES Appendix B.

S9

11. The exam contains the required number of one-point, multiple choice items; the total is correct and a rees with value on cover sheet. sO Date
a. Author Steven Dennis / Sr'l..)r07
b. Facility Reviewer (*) p£;~D7
c. NRC Chief Examiner (#)
d. NRC Regional Supervisor Note:
  • The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
  1. Inde endent NRC reviewer initial items in Column "c"; chief examiner concurrence re uired.

NUREG-1021, Revision 9

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

acility: Brunswick NRC Date of Exam: JULY 2007 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Tot A2 G* Total 1 2 3 4 5 6 1 2 3 4
  • al 1.

Emergency 1 5" 4...- t- 2 4"..- 4. / 20 3,/' 4", 7/'

& 2 2 1 2 N/A 1 1, N/A 0 7 2 ".- 1.... 3"

,," .... . / /' v Abnormal "

Plant Evolutions Tier Totals 7 5 3 .... 3 5_ .

4 27 5" 5,...- 10

~.

~- .,/

1 4", 3/ 1" 5,..- 1", 2", 0" 2" 3,/ 2,.-, 3,.-- 26,..- 2.....- 3"", 5 ,.

2.

Plant 2 1/ 1,..- 1/ 1,.. 1 ,.. 1..... 3, 0/ 1,,- 2 r 0.,- 12/ 0 1 2 ....... 3.,..

Systems Tier Totals 5.... 4/ 2.,,- 6,/ 2"'" 3 01 3/ 2/ 4'" 4" 3" 38,,/ 3 .v 5 .v 8....

3. Generic Knowledge and 1 2 3 4 1 2 3 4 10 7 Abilities Categories 2/ 2"" 2....- 4", 2", 2...- 2 ....... 1~

Note: 1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO outline (Le., the "Tier Totals" in each KIA category shall not be less than two).

Refer to Section D.1.c for additional guidance regarding SRO sampling.

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 +/- 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. Select topics from many systems and evolutions; avoid selecting more than two KIA topics from a given system or evolution 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 (G) KlAs 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. The SRO KlAs must also be linked to 10 CFR 55.43 or an SRO-Ievel learning objective.

7. On the following pages, enter the KIA 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K" and "A". Use duplicate pages for RO and SRO-only exams.
8. For Tier 3, enter the KIA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.

NUREG-1021 1

ES-4~ Brun~ NRC Form E  :-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # I Name Safety Function ~ Number I KIA Topic(s) limp. [9#]1 Ability to determine and/or interpret the following as 295001 Partial or Complete Loss of Forced Core Flow they apply to PARTIAL OR COMPLETE LOSS OF X AA2.01 3.8 76 Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION: Power/flow map.............. .........................

295003 Partial or Complete Loss of AC / 6 Conduct of Operations: Knowledge of system status X 2.1.14 3.3 77 criteria which require notification of plant personnel.

Emergency Procedures / Plan Knowledge of 295024 High Drywell Pressure / 5 X 2.4.31 annunciators alarms and indications, and use of the 3.4 78 response instructions.

Conduct of Operations: Knowledge of system purpose 295025 High Reactor Pressure / 3 X 2.1.27 2.9 79 and or function.

295028 High Drywell Temperature / 5 Ability to determine and/or interpret the following as X EA2.01 they apply to HIGH DRYWELL TEMPERATURE: 4.1 80 Drywell Temperature Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER 295030 Low Suppression Pool Water Level / 5 X EA2.02 3.9 81 LEVEL: Suppression pool temperature..........................

Conduct of Operations: Ability to perform specific 295038 High Off-site Release Rate / 9 X 2.1.23 system and integrated plant procedures during all 4.0 82 modes of plant operation.

Ability to determine and/or interpret the following as 295001 Partial or Complete Loss of Forced Core Flow they apply to PARTIAL OR COMPLETE LOSS OF X AA2.05 3.1 39 Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION: Jet pump operability: Not-BWR-1 &2....................

Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR 295003 Partial or Complete Loss of AC / 6 X AK1.03 COMPLETE LOSS OF A.C. POWER: Under 2.9 40 voltage/degraded voltage effects on electrical loads................................

Conduct of Operations: Ability to locate and operate 295004 Partial or Total Loss of DC Pwr / 6 X 2.1.30 components, including local controls.

3.9 41 Knowledge of the interrelations between MAIN 295005 Main Turbine Generator Trip / 3 X AK2.01 TURBINE GENERATOR TRIP and the following: RPS 3.8 42 Ability to determine and/or interpret the following as 295006 SCRAM / 1 X AA2.01 they apply to SCRAM: Reactor 4.5 43 power. ........................................

NUREG-1021 2

l~\

ES-4~ BrunS. ~\lRC Form -1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # I Name Safety Function 1~INumberl KIA Topic(s) Ilmp*I~1 Knowledge of the interrelations between CONTROL 295016 Control Room Abandonment / 7 X AK2.01 ROOM ABANDONMENT and the following: Remote 4.4 44 shutdown panel: Plant-Specific................

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF 295018 Partial or Total Loss of CCW /8 X AA2.04 2.9 45 COMPONENT COOLING WATER: System flow...........................................

Ability to operate and/or monitor the following as they 295019 Partial or Total Loss of Inst. Air / 8 X AA1.01 apply to PARTIAL OR COMPLETE LOSS OF 3.5 46 INSTRUMENT AIR: Backup Air supply Knowledge of the interrelations between LOSS OF 295021 Loss of Shutdown Cooling /4 X AK2.03 SHUTDOWN COOLING and the following: 3.6 47 RHRlshutdown cooling ..................................

Knowledge of the interrelations between REFUELING 295023 Refueling Acc Cooling Mode / 8 X AK2.03 ACCIDENTS and the following: Radiation monitoring 3.4 48 equipment. .......................

Equipment Control Knowledge of bases in technical 295024 High Drywell Pressure / 5 X 2.2.25 specifications for limiting conditions for operations and 2.5 49 safety limits.

Conduct of Operations: Ability to perform specific 295025 High Reactor Pressure / 3 X 2.1.23 system and integrated plant procedures during 3.9 50 different modes of plant operation Conduct of Operations: Knowledge of operator 295026 Suppression Pool High Water Temp. / 5 X 2.1.2 3.0 51 responsibilities during all modes of plant operation.

295028 High Drywell Temperature / 5 Knowledge of the reasons for the following responses X EK3.01 as they apply to HIGH DRYWELL TEMPERATURE: 3.6 52 Emergency depressurization Ability to operate and/or monitor the following as they 295028 High Drywell Temperature / 5 X EA1.04 apply to HIGH DRYWELL TEMPERATURE: Drywell 3.9 53 pressure......................................

Knowledge of the operational implications of the following concepts as they apply to LOW 295030 Low Suppression Pool Water Level / 5 X EK1.01 3.8 54 SUPPRESSION POOL WATER LEVEL: Steam condensation ....................................

Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW 295031 Reactor Low Water Level / 2 X EK1.02 3.8 55 WATER LEVEL: Natural circulation: Plant-Specific..................

NUREG-1021 3

Bruns NRC Form -1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # I Name Safety Function KIA Topic(s) Ilmp*~1 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND 295037 SCRAM Condition Present and Power Above X EA2.06 REACTOR POWER ABOVE APRM DOWNSCALE 4.0 56 APRM Downscale or Unknown / 1 OR UNKNOWN: Reactor pressure......................................

Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE 295038 High Off-site Release Rate / 9 X EK1.01 2.5 57 RELEASE RATE: Biological effects of radioisotope ingestion..........

Knowledge of the operation applications of the 600000 Plant Fire On-site / 8 X AK1.02 following concepts as they apply to Plant Fire On Site: 2.9 58 Fire Fighting KIA Category Point Totals: 4/4 5 4 1 2 4/3 Group Point Total: I 20/7 NUREG-1021 4

ES-4~ Bruns j\JRC Form -1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # I Name Safety Function ~Numberl KIA Topic(s) Ilmp*I~1 Ability to determine andlor interpret the following as they 295008 High Reactor Water Levell 5 X AA2.02 apply to HIGH REACTOR WATER LEVEL: Steam Flo\i'JI 3.4 83 Feed Flow mismatch Conduct of Operations: Ability to explain and apply all 295029 High Suppression Pool Water Levell 5 X 2.1.32 3.8 84 system limits and preca'utions.

Ability to determine andlor interpret the following as they 295032 High Secondary Containment Area Temperature apply to HIGH SECONDARY CONTAINMENT AREA X EA2.02 3.5 85 15 TEMPERATURE: Equipment operability.................................

Knowledge of the interrelations between HIGH DRYWELL 295010 High Drywell Pressure / 5 X AK2.05 PRESSURE and the following: Drywell cooling and 3.7 59 ventilation .......................

Knowledge of the operational implications of the following concepts as they apply to INCOMPLETE SCRAM: (CFR 295015 Incomplete SCRAM / 1 X AK1.02 3.9 60 41.8 to 41.10) Cooldown effects on reactor power.....................

Knowledge of the operational implications of the following concepts as they apply to INADVERTENT 295020 Inadvertent Cont. Isolation / 5 & 7 X AK1.01 3.7 61 CONTAINMENT ISOLATION: Loss of normal heat sink..............................

Ability to operate and/or monitor the following as they 295022 Loss of CRD Pumps / 1 X AA1.01 3.1 62 apply to LOSS OF CRD PUMPS: CRD Hydraulic System Ability to determine and/or interpret the following as they 295029 High Suppression Pool Water Level / 5 X EA2.02 apply to HIGH SUPPRESSION POOL WATER LEVEL: 3.5 63 Reactor pressure......................................

Knowledge of the reasons for the following responses as 295033 High Secondary Containment Area Radiation they apply to HIGH SECONDARY CONTAINMENT AREA X EK3.04 4.0 64 Levels /9 RADIATION LEVELS: Personnel evacuation ..................................

Knowledge of the reasons for the following responses as 295035 Secondary Containment High Differential they apply to SECONDARY CONTAINMENT HIGH X EK3.01 2.8 65 Pressure / 5 DIFFERENTIAL PRESSURE: Blow-out panel operation:

Plant-Specific.............

KIA Category Point Total: 0/1 2 1 2 1 1/2 Group Point Total: I 7/3

/

NUREG-1021 5

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I ES-4~ Bruns NRC Form -1 Written Exarrllrlation Outline Plant Systems - Tier 2 Group 1 II System #/Name Number I KIA Topics I Imp. [3!]1 Conduct of Operations: Ability to perform specific 203000 RHR/LPCl: Injection X 2.1.23 system and integrated plant procedures during all 4.0 86 Mode modes of plant operation.

Ability to (a) predict the irnpacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use procedures to 212000 RPS X A2.02 3.9 87 correct control, or mitigate the consequences of those abnormal conditions or operations: RPS bus power supply failure Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM; and (b) based on those predictions, use 215003lRM X A2.02 3.7 88 procedures to correct, contrai, or mitigate the consequences of those abnormal conditions or operations: IRM lnop condition Emergency Procedures / Plan Knowledge of 215004 Source Range Monitor X 2.4.11 3.6 89 abnormal condition procedures Emergency Procedures I Plan Knowledge symptom 300000 Instrument Air X 2.4.6 4.0 90 based EOP mitigation strategies.

Ability to monitor automatic operations of the 203000 RHRlLPCI: Injection X A3.09 RHRlLPCI: INJECTION MODE (PLANT SPECIFIC) 3.6 1 Mode including: Emergency generator load sequencing Knowledge of electrical power supplies to the 205000 Shutdown Cooling X K2.02 2.5 2 following: Motor operated valves Ability to manually operate and/or monitor in the 205000 Shutdown Cooling X A4.05 3.2 3 control room: Minimum flow valves Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM design feature(s) and/or 206000 HPCI X K4.18 3.2 4 interlocks which provide for the following: Pump minimum flow: BWR-2,3,4 Knowledge of electrical power supplies to the 217000 RCIC X K2.02 2.8 5 following: RCIC initiation. signals (logic)

Knowledge of the physical connections and/or cause- effect relationships between LOW 209001 LPCS X K1.09 3.2 6 PRESSURE CORE SPRAY SYSTEM and the following: Nuclear boiler instrumentation Ability to manually operate and/or monitor in the 202002 Recirc Flow Control X A4.09 3.2 7 control room: Core Flow NUREG-1021 6

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ES-4( Brum. NRC Form E 1-1 Written Examination Outline Plant Systems - Tier 2 Group 1

! System #/Name Number I KIA Topics limp. ~I Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use procedures to 211000SLC X A2.04 3.1 8 correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow Knowledge of the effect that a loss or malfunction of 212000 RPS X K6.05 the following will have on the REACTOR 3.5 9 PROTECTION SYSTEM: RPS sensor inputs Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use procedures to 212000 RPS X A2.09 correct, control, or mitigate the consequences of 4.1 10 those abnormal conditions or operations: High containment /Drywell pressure Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE 2150031RM X K6.02 3.6 11 RANGE MONITOR (IRM) SYSTEM : ?~~_8v,0It D.C.

power: Plant-Specific Knowledge of the operational implications of the following concepts as they apply to SOURCE 215004 Source Range Monitor X K5.01 RANGE MONITOR (SRM) SYSTEM: Detector 2.6 12 operation Emergency Procedures / Plan: Ability to execute 215005 APRM / LPRM X 2.1.20 4.3 13 procedure steps.

Conduct of Operations: Ability to recognize 217000 RCIC X 2.1.33 indications for system operating parameters which 3.4 14 are entry-level conditions for technical specifications.

Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which 218000 ADS X K4.02 provide for the following: Allows manual initiation of 3.8 15 ADS logic Emergency Procedures / Plan Ability to perform without reference to procedures those actions that 218000 ADS X 2.4.49 4.0 16 require immediate operation of system components and controls.

Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY 223002 PCIS/Nuclear Steam X K4.05 SHUT-OFF design feature(s) and/or interlocks which 2.9 17 Supply Shutoff provide for the following: Single failures will not impair the function ability of the system NUREG-1021 7

I ES-4C Bruns l\JRC Form -1 Written Examination Outline Plant Systems - Tier 2 Group 1 II System #/Name Number I KIA Topics I Imp. [9!]!

Knowledge of the physical connections and/or cause- effect relationships between 239002 SRVs X K1.07 3.6 18 RELIEF/SAFETY VALVES and the following:

Suppression pool Knowledge of REACTOR WATER LEVEL 259002 Reactor Water Level CONTROL SYSTEM design feature(s) and/or X K4.10 3.4 19 Control interlocks which provide for the following: Three element control Knowledge of the physical connections and/or 261000 SGTS X K1.09 cause- effect relationships between SGTS and the 3.2 20 following: PCIS Ability to monitor automatic operations of the A.C.

262001 AC Electrical Distribution X A3.03 ELECTRICAL DISTRIBUTION including: Load 3.4 21 shedding Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C.lD.C.) design feature(s) and/or 262002 UPS (AC/DC) X K4.01 3.1 22 interlocks which provide for the following: Transfer from preferred power to alternate power supplies Knowledge of electrical power supplies to the 263000 DC Electrical Distribution X K2.01 3.1 23 following: Major D.C. loads Knowledge of the physical connections and/or cause- effect relationships between EMERGENCY 264000 EDGs X K1.07 3.9 24 GENERATORS (DIESEUJET) and the following:

Emergency core cooling systems Knowledge of the effect that a loss or malfunction of 300000 Instrument Air X K3.02 the Instrument Air System will have on the following: 3.3 25 Systems having pneumatic valves or controls.

Ability to monitor automatic operations of the CCWS 400000 Component Cooling including: Setpoints on instrument signal levels for X A3.01 3.0 26 Water normal operations, warnings, and trips that are applicable to the CCWS KIA Category Point Totals: 3/3 4 3 1 5 1 2 0 2/2 3 2 Group Point Total: I 26/5

/ ./ / .(' / / .,/ / ".- ,,,/ /'

NUREG-1021 8

ES-4G Brunsv~RC Form ES*

Written Examination Outline Plant Systems - Tier 2 Group 2 II System #/Name Number I KIA Topics limp. ~I Knowledge of event based EOP mitigation 206000 HPCI X 2.4.7 3.8 91 strategies Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to 290001 Secondary CTMT X A2.03 3.6 92 correct control, or mitigate the consequences of those abnormal conditions or operations: High area radiation 226001 RHRlLPCI Containment Conduct of Operations: Ability to apply tech specs X 2.1.9 for a system 4.0 93 Spray Mode Ability to manually operate and/or monitor in the 201002 RMCS X A4.02 3.5 27 control room: Emergency in/notch override switch Ability to predict and/or monitor changes in 201003 Control Rod and Drive parameters associated with operating the Control X A1.02 2.8 28 Mechanism Rod and Drive Mechanism controls including:

CRD Drive Pressure Knowledge of the effect that a loss or malfunction of the following will have on the ROD WORTH 201006 RWM X K6.01 2.8 29 MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC)

RWM power supply: P-Spec(Not-BWR6)

Knowledge of the effect that a loss or malfunction of the RECIRCULATION SYSTEM will have on 202001 Recirculation X K3.06 following: Low pressure coolant injection logic:

3.7 30 Plant-Specific Knowledge of RECIRCULATION FLOW 202002 Recirculation Flow CONTROL SYSTEM design feature(s) and/or X K4.02 interlocks which provide for the following:

3.0 31 Control Recirculation pump speed control: Plant-Specific Knowledge of the operational implications of the 204000 RWCU X K5.05 following concepts as they apply to RWCU: Flow 2.6 32 Controllers Ability to predict and/or monitor changes in parameters associated with operating the 241000 ReactorlTurbine Pressure X A1.14 REACTORITURBINE PRESSURE REGULATING 3.4 33 Regulator SYSTEM controls including: Pressure setpoint/pressure demand Ability to predict and/or monitor changes in parameters associated with operating the 256000 Reactor Condensate X A1.09 3.1 34 REACTOR CONDENSATE SYSTEM controls including: Feedwater temperature NUREG-1021 9

ES-4( Bruns\ JRC Form ES Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number KIA Topics Imp. Q#

Ability to manually operate and/or monitor in the 268000 Radwaste X A4.01 3.4 35 control room: Sump integrators Knowledge ofElt~£tQ.9~~LRP}~~r..§upplies to the 286000 Fire Protection X K2.03 2.5 36 following:~<;t~~~~!~~!",~~~~t~DJ) Plant-Specific Ability to monitor automatic operations of the 290001 Secondary CTMT X A3.02 SECONDARY CONTAINMENT including: Normal 3.5 37 building differential pressure: Plant-Specific Knowledge of the physical connections and/or cause- effect relationships between REACTOR 290002 Reactor Vessel Internals X K1.05 VESSEL INTERNALS and the following: RHR:

3.1 38 Plant-Specific KIA Category Point Totals:

/

0/2

/

1 1

/

1

/

1 1

~

1 3 0/1 1 2 Group Point Total: I 12/3 NUREG-1021 10

I ES-401 Generic Knowledge and Abilities Outline (Tier3) I Form ES-401-3 I Facility:

I Brunswick NRC I Date of Exam:

I 3/10/2007 RO SRO-Only Category KIA # Topic IR Q# IR Q#

2.1.12 Ability to apply technical specifications for a system. 4.0 94 Ability to obtain and interpret station reference 2.1.25 materials such as graphs, monographs, and tables 3.1 95 which contain performance data.

1.

Conduct of Operations Ability to explain and apply all system limits and 2.1.32 3.4 66 precautions.

2.1.1 Knowledge of conduct of operations requirements 3.7 67 Subtotal 2 2 Knowledge of the process for conducting tests or 2.2.7 experiments not described in the safety analysis 32 96 report Knowledge of bases in technical specifications for 2.2.25 3.7 97 limiting conditions for operations and safety limits.

2.

Equipment Control Knowledge of the process for determining the internal 2.2.34 2.8 68 and external effects on core reactivity.

(multi-unit) Knowledge of the design, procedural, and 2.2.3 3.1 69 operational differences between units.

Subtotal 2 2 Knowledge of SRO responsibilities for auxiliary 2.3.3 systems that are outside the control room (e.g .. waste 29 98 disposal and handlinq systems).

Knowledge of radiation exposure limits and 2.3.4 contamination control, including permissible levels in 31 99

3. excess of those authorized.

Radiation Control Ability to perform procedures to reduce excess levels 2.3.10 2.9 70 of radiation and guard against personnel exposure

( 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements 2.6 71 Subtotal 2 2 Ability to recognize abnormal indications for system 2.4.4 operating parameters which are entry-level conditions 4.3 100 for emergency and abnormal operating procedures.

2.4.27 Knowledge of fire in the plant procedure. 3.0 72 Knowledge of the parameters and logic used to assess the status of safety functions including: 1 Reactivity

4. 2.4.21 control 2. Core cooling and heat removal 3. Reactor 3.7 73 Emergency Procedures coolant system integrity 4. Containment conditions 5.

I Plan Radioactivitv release control.

Knowledge of the bases for prioritizing emergency 2.4.23 procedure implementation during emergency 2.8 74 operations.

Knowledge of communications procedures associated 2.4.15 3.0 75 with EOP implementation Subtotal 4 1 Tier 3 Point Total 10 7

(

NUREG-1021 11

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