ML070820469

Final Outlines (Folder 3)

ML070820469
Person / Time
Site:	Nine Mile Point
Issue date:	02/16/2007
From:	Shortell T Constellation Energy Group
To:	Caruso J Operations Branch I
Sykes, Marvin D.
Shared Package
ML060800077	List: IR 05000220/2007301 ML070610189 ML070820469 ML070820475 ML070820484 ML070820520 ML070820529 ML070820535 ML070820542 ML070820551 ML070820557 ML070820563 ML070820570 ML070820573 ML070871016 ML071030148 ML071340128
References
Download: ML070820469 (30)

Text

UNIT 1 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 1 Date of Exam: March 12, 2007 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 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 *Ifrom 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. Systems/evolutions 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 K/As 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 K/A categories.

7 *The generic (G) 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.

8. 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. Use duplicate pages for RO and SRO-only exams.

9 For Tier 3, select topics from Section 2 of the K/A catalog, and enter the KIA numbers, descriptions, IRs, and point totals on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES 401, Page 1 of 9 2007 NRC E S 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO)

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

EIAPE # / Name / Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 1 R049 295003 Partial or Complete Loss of AC 16 RO 50 295004 Partial or Total Loss of DC Pwr / 6 AAI .02 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE RO 51 LOSS OF D.C. POWER:

Systems necessary to assure safe plant shutdown 295005 Main Turbine Generator Trip / 3 AA2 06 Ability to determine and/or interpret the following as they apply to MAIN TURBINE RO 52 GENERATOR TRIP Feedwater temperature 1 295006 SCRAM / 1

~ 0 5 3 I AK2.04 Knowledge of the interrelations between SCRAM and the following Turbine Trip Logic I 1

I 295016 Control Room Abandonment / 7 RO54 295018 Partial or Total Loss of CCW 1 8 RO 55 295019 Partial or Total Loss of Inst. Air 1 8 RO 56 295021 Loss of Shutdown Cooling / 4 AA2 02 Ability to determine and/or interpret the RO 57 295023 Refueling Acc Cooling Mode / 8 AAI 07 Ability to operate and/or monitor the 1

RO 58 295024 High Drywell Pressure / 5 R059 295025 High Reactor Pressure / 3 1 R060 295026 Suppression Pool High Water Temp. nd/or monitor the 15 R 0 6 1 UPPRESSION POOL 295028 High Drywell Temperature / 5 RO 62 295030 Low Suppression Pool Wtr Lvl / 5 RO 63 ES 401, Page 2 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO) 295031 Reactor Low Water Level / 2 EA1.07 Ability to operate and/or monitor the 3.7 1 following as they apply to REACTOR LOW WATER 170 64 LEVEL:

Safetyhelief valves 295037 SCRAM Condition Present and EK1.O1 Knowledge of the operational implications of 4.1 1 Power Above APRM Downscale or Unknown the following concepts as they apply to SCRAM 1 1 RO65 CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

Reactor pressure effects on reactor power 295037 SCRAM Condition Present and EK3.07 Knowledge of the reasons for the following 4.2 1 Power Above APRM Downscale or Unknown responses as they apply to SCRAM CONDITION

/ I RO66 PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

Various alternate methods of control rod insertion 295038 High Off-site Release Rate I 9 EA1.06 Ability to operate and/or monitor the 3.5 1 following as they apply to HIGH OFF-SITE RO 67 RELEASE RATE:

Plant ventilation 600000 Plant Fire On Site / 8 AK2.01 Knowledge of the interrelations between 2.6 1 PLANT FIRE ON SITE and the following:

RO 68 Sensors / detectors and valves KIA Category Totals: Group Point Total: 20 ES 401, Page 3 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO)

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)

ElAPE ## / Name / Safety Function WA Topic@) IR #

295008 High Reactor Water Level AK3.04 Knowledge of the reasons for the following 3.3 1 responses as they apply to HIGH REACTOR WATER RO 69 LEVEL:

Reactor feed pump trip 295012 High Drywell Temperature15 AK2.02 Knowledge of the interrelations between HIGH 3.6 1 DRYWELL TEMPERATURE and the following:

RO 70 Drywell cooling 29501 3 High Suppression Pool 2.1.30 Ability to locate and operate components / 3.9 1 Temperature15 including local controls RO 71 295014 Inadvertent Reactivity Addition/l AA1.05 Ability to operate and / or monitor the following 3.9 1 as they apply to INADVERTENT REACTIVITY RO 72 ADDITION:

Neutron monitoring system 295015 Incomplete SCRAMII AKI .03 Knowledge of the operational implications of 3.8 1 the following concepts as they apply to INCOMPLETE RO 73 SCRAM:

Reactivity effects 295029 High Suppression Pool Water EK3.01 Knowledge of the reasons for the following 3.5 1 Level/!? responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL:

RO 74 Emergency depressurization 295033 High Secondary Containment Area EA2.01 Ability to determine andlor interpret the 3.8 1 Radiation Levels/9 following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area RO 75 radiation levels KIA Category Point Totals: Group Point Total: 7 ES 401, Page 4 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO)

I ES-401 BWR Examination Outline Plant Svstems - Tier 2IGroup 1 (RO)

Form ES-401-1 I System # / Name WA Topic(s) IR #

1 205000 Shutdown Cooling (6.03 Knowledge of the effect that a loss or nalfunction of the following will have on the 3.1 1 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE):

3ecirculation system 206000 HPCl (3.01 Knowledge of the effect that a loss or 4.0 1 nalfunction of HIGH PRESSURE COOLANT RO 12 NJECTION SYSTEM will have the following:

ieactor water level control 1

206000 HPCl 44.04 Ability to manually operate and/or 3.7 1 nonitor in the control room:

R013 Major system valves 207000 Isolation (Emergency) 66.07 Knowledge of the effect that a loss or 3.0 1 Condenser malfunction of the following will have on the ISOLATION (EMERGENCY) CONDENSER:

RO 14 4.C. Dower 207000 Isolation (Emergency) 144.07 Ability to manually operate and/or 4.2 1 Condenser monitor in the control room: Manually initiate the isolation condenser RO 15 1 209001 LPCS K5.05 Knowledge of the operational implications of the following concepts as they 2.5 1 apply to LOW PRESSURE CORE SPRAY SYSTEM:

System venting 21 1000 SLC K2.02 Knowledge of electrical power supplies 3.1 1 to the following:

Explosive valves 212000 RPS K6.03 Knowledge of the effect that a loss or 3.5 1 malfunction of the following will have on the REACTOR PROTECTION SYSTEM:

Nuclear boiler instrumentation 1 215003 IRM A I .03 Ability to predict and/or monitor changes in parameters associated with 3.6 1 operating the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including:

RPS status 1 215003 IRM R020 215004 SRM 2.1.32 Ability to explain and apply system limits and precautions K6.02 Knowledge of the effect that a loss or 3.4 3.1 1

1 malfunction of the following will have on the RO 21 SOURCE RANGE MONITOR (SRM)

SYSTEM:

24/48 volt DC power 215005 APRM/LPRM K4.07 Knowledge of AVERAGE POWER 3.7 1 RANGE MONlTORlLOCAL POWER RANGE RO 22 MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following:

Flow biased trip setpoints 218000 ADS A3.08 Ability to monitor automatic operations 4.2 1 of the AUTOMATIC DEPRESSURIZATION RO 23 SYSTEM including:

Reactor pressure ES 401, Page 5 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO) - -

223002 PClSiNuclear Steam K3.11 Knowledge of the effect that a loss or 2.8 1 Supply Shutoff malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM RO 24 SUPPLY SHUT-OFF will have on following:

Plant ventilation 223002 PClSiNuclear Steam 42.09 Ability to (a) predict the impacts of the 3.6 1 Supply Shutoff ollowing on the PRIMARY CONTAINMENT SOLATION SYSTEMlNUCLEAR STEAM RO 25 $UPPLY SHUT-OFF; and (b) based on those iredictions, use procedures to correct, control, i r mitigate the consequences of those abnormal conditions or operations:

System initiation I 239002 SRVs R026 239002 SRVs (2.01 Knowledge of electrical power supplies o the following: SRV solenoids

.(3.02 Knowledge of effect that a loss or 2.8 4.2 1

1 nalfunction of the RELIEFKAFETY VALVES RO 27 Nil1 have on the following: Reactor over xessurization 259002 Reactor Water Level 61.04 Knowledge of the physical connections 3.5 1 Control and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL RO 28 SYSTEM and the following:

Reactor feedwater flow I -

261000 SGTS A I .01 Ability to predict andlor monitor 2.9 1 changes in parameters associated with RO 29 operating the STANDBY GAS TREATMENT SYSTEM controls including:

System flow -

262001 AC Electrical A2.03 Ability to (a) predict the impacts of the 3.9 1 Distribution following A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use RO 30 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of offsite power - -

262002 UPS (ACIDC) K3.14 Knowledge of the effect that a loss or 2.e 1 malfunction of the UNINTERRUPTABLE RO 31 POWER SUPPLY (A.C./D.C.) will have on following:

Rx power 263000 DC Electrical A3.01 Ability to monitor automatic operations 3.2 1 Distribution of the D.C. ELECTRICAL DISTRIBUTION including:

RO 32 Meters, dials, recorders, alarms and indicating lights 264000 EDGs K4.05 Knowledge of EMERGENCY 3.2 1 GENERATORS (DIESELIJET) design 1 ~ 0 3 3 feature(s) andlor interlocks which provide for the following: Load shedding and sequencing 264000 EDGs 2.4.50 Ability to verify system alarm setpoints 3.: 1 and operate controls identified in the alarm response manual 300000 Instrument Air A3.02 Ability to monitor automatic operations 2.s 1 of the INSTRUMENT AIR SYSTEM including:

Air temperature 400000 Component Cooling K1.01 Knowledge of the physical connections 3.: 1 Water and / o r cause-effect relationships between CCWS and the following:

Service water system KIA Category Point Totals: Group Point Total: 26 ES 401, Page 6 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO)

I ES-401 System # / Name BWR Examination Outline Plant Systems - Tier 2/Group 2 (RO)

KIA Topic(s)

Form ES-401-1 IR #

I 201002 RMCS <I .05 Knowledge of the physical

onnections and/or cause-effect 3.4 1

.elationships between REACTOR MANUAL CONTROL SYSTEM and the

'ollowing:

3od worth minimizer 201003 Control Rod Drive 42.06 Ability to (a) predict the impacts of 3.0 1 Mechanism :he following on the CONTROL ROD 4ND DRIVE MECHANISM; and (b) lased on those predictions, use Jrocedures to correct, control, or mitigate the consequences of those abnormal zonditions or operations: Loss of CRD zooling water flow 202002 Recirculation Flow Control 41.01 Ability to predict and/or monitor 3.2 1 shanges in parameters associated with RO 39 3perating the RECIRCULATION FLOW CONTROL SYSTEM controls including:

Recirculation pump speed 215001 Traversing In-core Probe 2.4.49 Ability to perform without 4.0 1 reference to procedures those actions RO 40 that require immediate operation of system components and controls 219000 RHRILPCI: TorusIPool A I .03 Ability to predict and/or monitor 2.9 1 Cooling Mode changes in parameters associated with operating the RHR/LPCI:

RO 41 TORUSiSUPPRESSlON POOL COOLING MODE controls including:

System pressure I - -

226001 RHRILPCI: CTMT Spray A1.10 Ability to predict and/or monitor 3.0 1 Mode changes in parameters associated with operating the RHR/LPCI:

RO 42 CONTAINMENT SPRAY SYSTEM MODE controls including:

Emergency generator loading 233000 Fuel Pool Cooling/Cleanup A2.05 Ability to (a) predict the impacts of 2.5 1 the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Valve closures 256000 Reactor Condensate A3.07 Ability to monitor automatic 2.9 1 operations of the REACTOR RO 44 CONDENSATE SYSTEM including:

Feedwater heater level I 259001 Reactor Feedwater K1.07 Knowledge of the physical connections and/or cause-effect 2.9 1 relationships between REACTOR FEEDWATER SYSTEM and the following: A.C. electrical power 271000 Offgas K5.06 Knowledge of the operational 2.7 1 implications of the following concepts as RO 46 they apply to OFFGAS SYSTEM:

Catalytic recombination L -

ES 401, Page 7 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO) 272000 Radiation Monitoring A2.09 Ability to (d) predict the impacts of the following on the RADIATION RO 47 MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Low fuel pool level 288000 Plant Ventilation A2.03 Ability to (a) predict the impacts of the following on the PLANT RO 48 VENTILATION SYSTEMS ; and (b) based on those predictions, use procedures to correct, control, or mitigare the consequences of those abnormal conditions or operations:

Loss of coolant accident KIA Category Point Totals: Group Point Total:

ES 401, Page 8 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Friday, February 16, 2007

UNIT 1 NRC (RO)

I ES-401 Generic Knowledge and Abilities Outline (Tier 3) (RO) Form ES-401-3 I I Facility: Nine Mile Point Unit I Date of Exam: March 12,2007 I Category KIA # Topic

1. 2.1.2 Knowledge of operator responsibilities during all Conduct of RO 1 modes of plant operation.

0perat ions 2.1.29 Knowledge of how to conduct and verify valve RO 2 lineups.

2.1.33 Ability to recognize and indications for system RO 3 operating parameters which are entry level conditions for technical specifications.

2. 2.2.1 Ability to perform pre-startup procedures for the facility/ including operating those controls Equipment RO 4 associated with plant equipment that could affect Control reactivity.

2.2.1 1 Knowledge of process for controlling temporary changes.

RO 5 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

RO 6

3. 2.3.1 Knowledge of 10CFR20 and related facility radiation control requirements.

Radiation RO 7 Cont roI 2.3.1 1 Ability to control radiation releases.

RO 8 I 4.

Emergency 2.4.13 RO 9 Knowledge of crew roles and responsibilities during EOP flowchart use.

Procedures / 2.4.48 Ability to interpret control room indications to verify Plan status and operation of system/ and understand RO 10 how operator actions and directives affect plant and system conditions.

I Tier 3 Point Total ES 401, Page 9 of 9 2007 NRC ES 401-1 RO Written Exam Outline All Tiers Final Submittal Tuesday, February 20, 2007

UNIT 1 NRC (RO)

Faci I ity: Nine Mile Point Unit 1 Date of Exam:March 12,2007 ES-401 Record of Reiected K/As (RO) Form ES-401-4 I Tier / Group I Randomly Selected WA I Reason for Rejection I T IGI NA 295027 High Containment Temperature (Mark 111 Containment Only). Not applicable to facility.

T I G2 NA 29501 1 High Containment Temperature (Mark 111 Containment Only). Not applicable to facility.

T2G1 NA 203000 RHRILPCI: Injection Mode (Plant Specific).

Not applicable to facility design.

T2G1 NA 209002 Hiah Pressure Core SDrav , , Svstem

, (HPCS).

Not applicable to facility design.

T2G1 NA 217000 Reactor Core Isolation Cooling System (RCIC).

Not applicable to facility design.

T2G2 NA 201004 Rod Sequence Control System (Plant Specific).

Not applicable to facility design.

T2G2 NA 201005 Rod Control and Information System (RCIS).

Not applicable to facility design.

T2G2 NA 215002 Rod Block Monitor System.

Not applicable to facility design.

T2G2 NA 230000 RHRILPCI: Torus/Suppression Pool Spray Mode.

Not applicable to facility design.

T2G2 NA 239003 MSlV Leakage Control System.

T IGI 295019 A I Insufficient number of generic topics selected and excessive number of A I topics selected. Randomly deselected 295019 A I to become G. (7/5/06)

TIGI 295024 A I Insufficient number of generic topics selected and excessive number of A I topics selected. Randomly deselected 295024 A I to become G. (7/5/06)

T I G2 295013 A I Insufficient number of generic topics selected and excessive number of A I topics selected. Randomly deselected 295013 A I to become G. (7/5/06)

T2G1 223002 K2 Excessive numbers of K2 knowledge of power supply topics initially selected for T2 (5 total). Randomly deselected 223002 K2 and randomly selected A2 topic. (7/5/06)

T2G1 262001 K2 Excessive numbers of K2 knowledge of power supply topics initially selected for T2 (5 total). Randomly deselected 262001 K2 and randomly selected A2 topic. (7/5/06)

T3 2.1 2 1 Randomly selected then rejected due to inability to develop discriminating written question. 2.1.I7 randomly selected. (715106)

T3 2.1.17 Randomly selected then rejected due to inability to develop discriminating written question. 2.1.2 randomly selected. (7/5/06)

T3 2.1.20 Randomly selected then rejected due to inability to develop discriminating written question. Topic not appropriately tested on a written exam. 2.1.29 randomly selected. (7/5/06)

T3 2.4.7 Randomly selected then rejected as not applicable to the facility. EOPs are symptom based procedures, not event based. 2.4.48 randomly selected. (7/5/06)

TlGl 295016 K1 Randomlv selected then reiected because there are no K1 tooics. Randomlv I selected G 2.4.49 (genericj topic. (7/6/06)

T IGI I 295019 2.1.28 I Randomly selected then rejected because the statement is not applicable

.. to the emergency event. Randomly selected G 2.2.22. (7/6/06).

T I G2 295033 2.2.22 Randomly selected then rejected because the KA statement is not applicable to this topic (ie Secondary containment radiation levels does not have an LCO or safety limit. Randomly selected G 2.4.49. (7/6/06)

T2G1 262002 K3.04 Randomly selected then rejected because of low importance and inability to develop a discriminating question at the RO level. Randomly selected K3.14. (7/6/06)

T2G2 201002 K2 Randomlv selected then reiected because both statements are below 2.5.

Randomly selected K1 and statement K1.05 (7/6/06)

T2G2 215001 K3 Randomly selected then rejected because statements are below 2.5. Randomly selected, then reiected G 2.1.2 because statement is not aoolicable to svstem.

Randomly selecfed G 2.4.49 (7/6/06)

T2IG1 209001 K5.04 Rejected during overall outline review due to inability to develop an operationally oriented discriminating question. Randomly selected K5.05 (8/10/06)

T2IG1 218000 K1.05 Rejected during outline review because it is not applicable to the unit. There is no relationship between ADS valves and remote shutdown system. Randomly selected A3.08 (8/10/06)

I I Per ES-401 D . l .d: After completing the outline, check the selected WAS for balance of coverage within and across the three tiers.

Ensure that every applicable WA category is sampled at least twice within each of the three tiers.

NONE I NONE I NONE Facility Outline Review ES 401, Page 1 of 2 2007 NRC - RO Written Record of Rejected KAs Final Friday, February 16, 2007

UNIT 1 NRC (RO) t l Date of Exam:March 12,2007 TliGl 295001 AA2.01 Rejected during overall outline review due to overlap with Operating Test events in Scenario 1. Randomly selected AA2.06 (8/28/06)

TliGl 295006 AK2.06 Rejected during overall outline review due to overlap with other topic area (RO 22) and inability to develop an operationally oriented discriminating question. Randomly selected AK2.04 (8/28/06) er outline submittal and NRC review. (9/27/06- 10/25/06)

T2iG2 259001 A1.O1 (RO 45) Rejected during question development due to overlap (double jeopardy) with RO 28.

Randomly selected 259001 K1.07. (9/28/06)

TliGl 295023 AA1.04 (RO 58) Rejected during question development due to overlap (double jeopardy) with RO 47.

Randomly selected 295023 AAI .07. (9128i06)

TliGl 295019 G2.2.22 (RO Rejected during question development due to KA statement is not applicable to topic

56) area. No LCO or safety limit associated with loss of air. Randomly selected AK2.01, (9/28/06)

TliGl 295024 G2.2.25 (R059) Rejected during question development due to overlap (double jeopardy) with RO 6.

Both are tech spec bases topics. Randomly selected EK2.03 (10/3/06)

TlIG2 295033 G2.4.49 (RO Rejected during question development. Any acceptable question that could be

75) developed to address the statement would be related to reactor building ventilation.

This would result in over-sampling of the secondaryventilation system, as this is tested in other parts of the exam Randomly selected EA2.01 (10/6/06)

T3 G2.4.23 (RO 9) Reiected durina auestion develoDment dde 10 inabilitv to deve OD an acceDtable RO job related question that matches the statement. Statkment IS primarily an' SRO topic. Randomly selected G2.4.13 (10/7/06)

Changes made after draft submittal and I\ 2 review. (10/27/06-)

T2iG1 1 264000 K4.03 (R033) Rejected after draft exam submittal. Comment by Chief Examiner for the orighal question submitted was that topic is "simplistic" and "GFE knowledge level". In order to develop an acceptable question a new KA had to be selected. Randomly selected K4.05 (12/19/06)

T2iG2 201003 K4.08 (R038) Rejected after draft exam submittal. Comment by Chief Examiner for the original question submitted was that topic is "simplistic". In order to develop an acceptable question a new KA had to be selected. Randomly selected A2.06 (1/29/07)

ES 401, Page 2 of 2 2007 NRC - RO Written Record of Rejected KAs Final Friday, February 16, 2007

UN'IT 1 NRC (SRO)

ES-401 BWR Examination Outline Form ES-401-1 3 Systems/evolutions 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 KIA categories.

7 *The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR ES 401, Page 1 of 6 2007 U1 NRC ES 401-1 SRO Written Exam Outline All Tiers Final Submittal Outline Submittal Tuesday, February 20,2007

UNIT 1 NRC (SRO)

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

WA Topic(s) IR #

AA2.03 Ability to determine and/or interpret the 3.3 1 following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Actual core flow AA2.04 Ability to determine and/or interpret the 3.7 1 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER:

System lineups AA2.04 Ability to determine and/or interpret the 4.1 1 following as they apply to CONTROL ROOM ABANDONMENT:

Suppression pool temperature 2.2.28 Knowledge of new and spent fuel movement 3.5 1 procedures EA2.02 Ability to determine and/or interpret the 3.9 1 following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

Suppression pool level EA2.03 Ability to determine and/or interpret the 3.9 1 following as they apply to HIGH DRYWELL TEMPERATURE:

Reactor water level 2.4.6 Knowledge of symptom based EOP mitigation 4.0 1 strategies.

Group Point Total: 7 ES 401, Page 2 of 6 2007 U1 NRC ES 401-1 SRO Written Exam Outline All Tiers Final Submittal Outline Submittal Tuesday, February 20,2007

UNIT 1 NRC (SRO)

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier I/Group 2 (RO)

ES 401, Page 3 of 6 2007 U1 NRC ES 401-1 SRO Written Exam Outline All Tiers Final Submittal Outline Submittal Tuesday, February 20, 2007

UNIT 1 NRC (SRO)

__ . BWR Examination Outline Form ES-401-1 Plant Svstems -Tier 2 / G r o .u ~1 (SRO)

WA Topic(s) IR #

~~ -

A2 10 Ability to (a) predict the impacts of the 3.4 following on the LOW PRESSURE CORE SPRAY SYSTEM, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations High suppression pool temperature A2.02 Ability to (a) predict the impacts of the 3.7 following on the REACTOR PROTECTION SYSTEM : and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RPS bus power supply failure 2.4.11 Knowledge of abnormal conditions 3.6 procedures 2.2.24 Ability to analyze the affect of 3.8 maintenance activities on LCO status A2.05 Ability to (a) predict the impacts of the 3.4 following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Faulty or erratic operation of detectors/system Group Point Total: 5 ES 401, Page 4 of 6 2007 U1 NRC ES 401-1 SRO Written Exam Outline All Tiers Final Submittal Outline Submittal Tuesday, February 20, 2007

i UNIT 1 NRC (SRO) 1 I ES-401 BWR Examination Outline Form ES-401-1 I Plant Systems - Tier 2/Group 2 (SRO)

WA Topic(s) IR A2.12 Ability to (a) predict the impacts 2.9 of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Instrument isolation valve closures 2.4.6 Knowledge of symptom based EOP 4.0 mitigation strategies.

G2.2.25 Knowledge of bases in technical 3.7 specificafions for limiting conditions for operations and safety limits.

Group Point Total:

ES 401, Page 5 of 6 2007 U1 NRC ES 401-1 SRO Written Exam Outline All Tiers Final Submittal Outline Submittal Monday, February 26,2007

UNIT I NRC (SRO)

~

ES-401 Generic Knowledge and Abilities Outline (Tier 3) (SRO) Form ES-401-3 Facility: Nine Mile Point Unit 1 Date of Exam: March 12, 2007 Category KIA #

1. 2.1.6 Conduct of SRO 1 0perat ions 2.1.7 SRO 2 Subtotal 2.

Equipment Control 3

Radiation Control 4.

Emergency Procedures I Plan Tier 3 Point Tota ES 401, Page 6 of 6 2007 U1 NRC ES 401-1 SRO Written Exam Outline All Tiers Final Submittal Outline Submittal Tuesday, February 20,2007

f UNIT 1 NRC (SRO)

Facility: Nine Mile Point Unit I Date of Exam:March 12,2007 ES-401 Record of Reiected K/As (SRO) Form ES-401-4 Tier / Group I Randomlv Selected WA I Reason for Reiection T IGI NA 295027 High Containment Temperature (Mark 111 Containment Only). Not applicable to facility.

T I G2 NA 29501 1 High Containment Temperature (Mark 111 Containment Only). Not applicable TIGI 295019 A I Insufficient number of generic topics selected and excessive number of A I topics selected. Randomly deselected 295019 A I to become G. (7/5/06)

TlGl 295024 A I Insufficient number of generic topics selected and excessive number of A I topics selected. Randomly deselected 295024 A I to become G. (7/5/06)

T I G2 29501 3 A I Insufficient number of generic topics selected and excessive number of A I topics selected. Randomly deselected 295013 A I to become G. (7/5/06)

T2G1 218000 G 2.1.21 Randomly selected, then rejected because it is not linked to 10CFR55.43(b).

Randomly selected G 2.4.1 1. (7/6/06)

TlGl 295023 G 2.1.24,2.4.42 Randomly selected, then rejected because they are not linked to 10CFR55.43(b).

Randomly selected 2.2.28. (7/6/06)

TlGl 295031 G 2.3.5 Randomly selected, then rejected because the statement is not applicable to this topic. Randomly selected 2.4.49 (7/6/06)

T I G2 295022 G 2.4.36, 2.3.9 Randomly selected, then rejected because the statements are not applicable to this topic. Randomly selected 2.2.17 (7/6/06)

T I G2 295036 G 2.2.27, 2.4.3 Randomly selected, then rejected. 2.2.27 statement is not applicable to this topic.

2.4.3 is not linked to 10CFR55.43(b). Randomly selected 2.1.25 (7/6/06)

T2G1 218000 G 2.1.21 Randomly selected, then rejected because the statement is not applicable to this topic. Randomly selected 2.4.1 1. (7/6/06)

T2G2 223001 G2.1.24 Randomly selected, then rejected because it is not linked to 10CFR55.43(b).

Randomly selected G 2.2.26. (7/6/06)

I I Per ES-401 D . l .d: After completing the outline, check the selected WAS for balance of coverage within and across the three tiers.

Ensure that every applicable WA category is sampled at least twice within each of the three tiers.

NONE I NONE . .-. .-

Changes mad during draft development i er outline submittal and NRC review.

T2/G 1 261000 A2.12 Rejected during question development because when considerina the RO written exam and other portions of the exam, Standby Gas Treatment (RBEVS) is over-sampled. RO written exam has (RO 24 29 48 58) currently testing RBEVS related knowledge. Randomly selected 215003 A2.05 (SRO 12) 10/10/06 T2iG2 223001 G2.2.26 Rejected during question development because the statement regarding refuel administrative requirements does not apply to the topic area of Primary Containment. Question matching the KA statement cannot be developed.

Randomly selected 223001 2.4.6 (SRO 14) 10/13/06 TIIG2 295035 EA2.02 Rejected during question development because when considering the RO written, SRO Admin test and the simulator operating test, the topics related to SECONDARY CONTAINMENT will be over-sampled. Randomly selected 295020 AA2.06 (SRO

24) 10113/06 Changes mad after exam suumitta, for NI ;review and aonroval TI/GI 295031 G2.4.49 Rejected after initial exam submittal. Question developed could not be developed to SRO level. Original question rejected by NRC as not an SRO level question.

Randomly selected 295031 G2.4.6 (SRO 22) and developed new question (2/19/07).

T2/G2 234000 A2.02 Rejected after initial exam submittal. Question developed could not be raised to SRO level. Chief Examiner determined the topic to be simplistic. Original question rejected by NRC as not an SRO level question. Refuel topics in this category were also simplistic. Randomly selected 226001 G2.2.25 (SRO 15) and developed new question (2/19/07).

T2/G 1 21 1000 G2.2.25 Rejected after initial exam submittal. Question difficulty could not be raised to a level acceptable by the Chief Examiner because it only tested a single tech spec. Original question rejected by NRC as low level of difficulty. Randomly selected 212000 A2.02 (SRO 9) and developed new question (2/20/07).

ES 401, Page 1 of 1 2007 U1 NRC - SRO Written Record of Rejected KAs Final Tuesday, February 20,2007

e s Outline Form ES-301-1

-- Facility: Nine Mile Point 1 Date of Examination: December 11,2006 Examination Level: RO Operating Test Number: NA Administrative Topic TY Pe Describe activity to be performed (see Note) Code*

Perform RPV Level Instrument Checks per N1-ST-DO, Daily Conduct of Operations Checks Plant parameter Given control room reactor water level instrument readings for Verification D various daily checks required by Technical Specifications (readings may be taken in the simulator), enter the instrument RO ADMIN 1 readings into the applicable sections of the Daily Checks and take appropriate actions based on those checks.

2.1. I 8 (2.9) Ability to make accurate 1 clear and concise logs /

records I status boards 1 and reports.

GAP-OPS-01; 3.10, N1-ST-DO; 7.0 Perform Control Room System Lineup Verification Evaluate conditions provided in S-PM-DO01 Control Room Conduct of Operations N System Lineup Verification for Control Room Ventilation System Shift Turnover and determine the required actions for out of position RO ADMIN 2 components. [Panel walkdown is performed in simulator).

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

S-PM-DO01 Attachment 2 2.24 RPS Logic Operation with EOP-3.1 RPS Jumpers Installed N Identify and locate electrical drawings related to RPS circuits.

Equ i pment Control Use the drawings to describe the effect of installing RPS Use of Electrical Prints jumpers on how scram signal is reset prior to initiating another RO ADMIN 3 manual scram, with the jumpers installed under failure to scram conditions. (Perform in simulator and supply with copies for candidate to mark-up).

2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.

N1-EOP-3.1; Drawing C-19859-C SH 4 and 7 Radiological Requirements Related To Operator Inspection Radiation Control Of Rad And High Rad Areas.

Radiation Hazards D, p Given radiological conditions and a survey map related to an NRC 2004 area to be inspected, ensure the appropriate radiological RO ADMIN 4 aspects of the job are met prior to performance of the inspection.

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

GAP-RPP-01; 3.5, 3.6, 3.7, GAP-RPP-02; 3.1, 3,3, GAP-RPP-08; 3.2, 3.3, NI-PM-M5; 6.0, 8.0 N0TE:AII items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes 8, Criteria:(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( < 3 for ROs; I 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 2 1)

(P)revious 2 exams ( 5 1; randomly selected) 9/25/2006 7: 12:30 AM 1 of1 2006 Unit 1 NRC RO Admin Outline Submittal

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point 1 Date of Examination: December 11, 2006 Operating Test Number: NA Administrative Topic TY Pe Describe activity to be performed (see Note) Code*

Assess Reportability Requirements For Maintenance Activity N Given inaccurate log entries stating 10CFR50.72 and 73 requirements for a given maintenance activity, assess the log entries for accuracy and correctness and identify the correct reporting requirements. (CR NM-2006-4134) 2.1 .I8 (3.0) Ability to make accurate/ clear and concise logs/ records/

status boards/ and reports.

10CFR50.72 and 73, NUREG 1022 REV 2 Determine Reactivity Event Severity Level And Supporting Conduct of Operations D Actions In Response To The Event Given plant conditions determine the reactivity event severity level SRO ADMIN 2 and the appropriate compensatory actions and notifications.

2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation.

GAP-OPS-05; 3.13 Review Reactor Engineering Thermal Limit Surveillance Equipment Control N Given daily surveillance procedure with thermal limits exceeded, SRO ADMIN 3 identify the Tech Spec required compensatory actions.

2.2.22 (4.1) Knowledge of limiting conditions for operations and safety limits.

N1-RESP-1A and Tech Specs Determine Actions Required For an Inoperable Effluent Radiation Control D Radiation Monitor SRO ADMIN 4 Given plant conditions, determine operability of an effluent radiation monitor and apply action statements contained in the station ODCM.

(CR NM-2004-976) 2.3.11 (3.2) Ability to control radiation releases.

ODCM Classify Emergency Event and Perform PARs Emergency Plan Given plant conditions at an existing Site Area Emergency, SRO ADMIN 5 determine the plant conditions now meet General Emergency conditions. Reclassify the event and determine PARs, based on conditions provided. (Time Critical) NRC 2002 SRO JPM A4 2.4.44 (4.0) Knowledge of emergency plan protective action recommendations.

EAL Matrix N0TE:AII items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (L: 3 for ROs; s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 2 1)

(P)revious 2 exams (s 1; randomly selected) 9/21/2006 8:12:09 AM 1 of1 2006 Unit 1 NRC SRO Admin Outline Submittal

Form ES-301-2 Facility: Nine Mile Point Unit 1 Date of Examination: March 12, 2007 Exam Level: RO SRO-I Operating Test No.: NRC EXAMINATION Control Room Systems@(8 for RO); (7 for SRQ-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function 1

REACTIVITY CONTROL Restore Reacto Automatic Isolation Proc N1-OP-IO G.2.0 and E.l.O Proc N1-OP-4 E.3.0 KA 205000 A4.01 3.713.7 II 4 HEAT REMOVAL implementing SOP, an EDG trips and alternate SOP actions are taken to crosstie PB 176 with 17A).

Proc N 1-SOP-33A. 1 KA 262001 A2.03 3.914.3 F WLC to automatic control, level transmitter fails downscale, requiring REACTOR WATER INVENTORY CONTROL 7

RO Only. This JPM is not performed by SRO-I INSTRUMENTATION Proc N1-SOP-1 I

3 MSlVs at Power REACTOR Proc NI-ST-Q26, Sections 8.2 and 8.3 PRESSURE CONTROL LC1 05-01 NRC Exam 2006 Submittal 1 of2 02/26/07 9:52 AM

1

[JPM 9 Liquid Poison/ RPV Injection From LP Test Tank R, P, D, I Proc N1-EOP-1 Attachment 12 KA 295031 EA1.08 3.813.9 Bank/Previous Ol-OPS-PJE-1-21/NRC 2002 JPM 9

• lr' 5 E, L REACTIVITY CONTROL I ,r d j Y 3 82'

• e 7

JPM 10 UPS/ Transfer RPS Bus 11 from UPSI62A to 162B (RPS Bus 1 1 load will fail to transfer to UPS1625, resulting in Loss of RPS Bus 11. SOP-40. I is entered which directs entry into N1-OP-40 to transfer RPS Bus 11 to alternate INSTRUMENTATION supply, I&C Bus 130)

Proc N1-OP-40 F.1.0 and H . l .O and N1-SOP-40.1 KA 212000 A2.02 3.713.9 6

T ENGINE condition occurs, ELECTRICAL Proc N1-SOP-21.2 Control Room E Actions KA 29501 6 AAI .04 3 113 2 Bank 01-OPS-PJE-200-1-78

(@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control Planned Simulator JPM Combinations JPM 1 and 4 JPM 2 and 3 (May run with 7)

JPM 5 and 6 JPM 7 standalone (RO Only)

JPM 8 standalone LC1 05-01 NRC Exam 2006 Submittal 2of2 02/26/07 9:52 AM

Scenario Outline Form ES-D-1

=acility: NMPI Scenario No.: NRC 1 Op-Test No.: NRC nitial Conditions: IC236 Reactor Power is 90% with MPR in service.

Turnover: PR is in service. EPF s ready to be placed in service, following maintenance.

Event Event No. Description 1 FWO2C C (TS Feedwater Booster Pump 13 auto trips. The pump is a HPCl SRO) component and must be declared inoperable. SRO enters TS 3.1.8 and the Dump must be restored within 15 days.

2 I N Transfer pressure control from MPR to EPR per N1-OP-31, F.3.0.

3 RP20B I (TS Drywell High Pressure Transmitter 201.2-476A fails downscale.

SRO) Transmitter supplies input to RPS, Core Spray and Containment Spray Systems. SRO Tech Spec Entry into LCO 3.6.2 is required.

RRO9C C (BOP) Recirc Pump 13 Motor Generator Slot temperatures rise. Removal of the pump from service is required, which also requires a power reduction. Actions are taken for the Recirc Pump Trip per SOP-I .3 MS05 Steam Seal Regulator Failure. Power reduction reveals a pre-existing failure in the Steam Seal Regulator and results in degraded steam seal header pressure and increased condenser air in-leakage. Regulator Bypass must be manually opened to restore seal pressure.

6 RR27 C (ALL) Recirc Master Controller fails low resulting in Restricted Zone entry.

Entry into SOP-I 5.Flow drops to 21 Mlbm/hr and power is 45-50%

R (SRO on APRMs. Cram Rods must be inserted to exit the restricted RO) zone. Power must be reduced to about 30% power to exit region.

7 Override M Loss of Condenser Vacuum due to Steam Seal Regulator Bypass Valve Failure. Enter SOP-25.1. A turbine trip is required when condenser backpressure exceeds 5 inches with generator load

< I 90 MWe. Reactor scrams either manually or automatically.

8 MS04 C Steam Leak in Drywell 20% ramp time 1O:OO minutes. After the scram and initial actions are complete, the steam leak develops.

Drywell pressure exceeds 3.5 psig and EOP entry is required.

Drywell parameters will reach values that require use of Containment Spray.

9 RP26B C Drywell High Pressure Transmitter 201.2-476C fails downscale.

With the Atransmitter previously failed the high drywell pressure RPS scram signal, Core Spray and Containment Spray automatic initiation signals are prevented. Crew must take manual actions to initiate these functions.

10 RR99A RPV level instrument readings become erratic. Crew is required to perform RPV Flooding. Event is classified as SAE 2.1.2 RR87

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2/22/2007 10:20:41 AM 1 of8 NRC Exam Submittal

Facility: Nine Mile Point 1 Scenario No.: NRC-01 Op-Test No.: NRC TARGET QUANTITATIVE ATTRIBUTES I ACTUAL (PER SCENARIO; SEE SECTION D.5.d) I ATTRIBUTES Total Malfunction Count:

1. Total malfunctions (5-8) 6 Major not included in this count.

Events 4,5,6,8,9,10 Didnt count Event 1 and 3,

2. Malfunctions after EOP entry (1-2) 2 because these only require SRO Events 9 and 10 tech spec use.

3. Abnormal events (2-4) 2 Event 6 SOP-I .5 and Event 7 SOP-25.1 Abnormal Events Count:

4. Major transients (1-2) 1 Does not include the SRO S related events. These are Event 7 Loss of Vacuum considered separately.

5. EOPs entered/requiring substantive 2 actions (1-2)

SRO TS Events Event 6 EOP-2 RPV; EOP-4 Pri Containment Event 1 and 3 are SRO Tech Spec evaluation events.

6. EOP contingencies requiring substantive 1 actions (0-2)

Event 9 EOP-7 RPV Flooding

7. Critical tasks (2-3) I 2 Operators SRO SRO 2 Driscoll ATC RO R2 Hibbert R4 Revelle R 5 DeGroot BOP RO R1 French R3 OBrien SRO 1 Minnick 2/22/2007 10:20:41 AM 2of8 NRC Exam Submittal

Appendix D,Rev. 9 Scenario Outline Form ES-D-1 Facility: NMPI Scenario No.: NRC 2 Op-Test No.: NRC Initial Conditions: IC20 100% Reactor Power Turnover: Complete NI-ST-Q4 Section 8.2.39-13R, 39-14R,05-04R, and 05-12 testing is done. Test Steam IVs39-10R and 39-08R. LP Pump 12 is out of service since 0600 today. TS LCO 3.1.2 Event Malf. No. Event Event No. Type* Description 1 N Crew performs N1-ST-Q4, Reactor Coolant System Isolation Valve Operability Test for EC Loop 12 IVs per Section 8.2.

2 ECO9B C (TS Steam IV 39-08R fails to fully close during testing. Valve must be SRO) declared inoperable and isolated per Tech Spec 3.2.7. EC Loop 12 now remains inop and unavailable when the steam line is isolated (TS 3.1.3.b, 7 day) 3 AD05 C (BOP) ERVI 11 inadvertently opens. The crew enters SOP-I .4. An emergency power reduction to 85% is performed. The ERV will (TS close after the fuses are pulled. Tech Spec 3.1.5 must be entered SRO) because the valve is now inoperable. TS 3.2.9 may also require entry.

4 RR28 Recirc Flow Master Controller fails as-is, preventing the power reduction by normal methods. The crew will operate individual Recirc Flow controls at F panel or insert cram rods to complete the emergency power reduction.

5 ECO6A C (BOP) EC 11 tube leak (50% with 5 minute ramp time). EC 11 isolation is required. Both EC loops are now inoperable. Tech Spec 3.1.3 specification e now applies and an orderly shutdown is required.

6 MS12 M (ALL) A steam leak develops in the turbine building condenser area with severity at 15%. Turbine Vibration rises following the load TU02 reduction. The crew will initiate a manual scram due to degraded plant conditions or when turbine bearing vibration exceeds 12 mils.

7 RD33 C (ALL) ATWS. Following the scram control rods will not fully insert and power will remain within turbine bypass valve capability, at about MSO 1 25%. The MSIVs will close on high temperature and heat will be LPOIA rejected to the torus. Liquid Poison Pump 11 trips. Alternate Boron Injection is directed.

8 RD35B Control Rod Drive Pump 12 trips during the scram transient.

Starting CRD Pump 11 is necessary for driving control rods.

9 CTO 1A C (BOP) Containment Spray Pump 111 trips, after control rods are fully inserted. Pump is initially running in the Torus Cooling mode. Since Torus temperature is still high due to heat added during the event, the system must be realigned to start an alternate Containment Spray Pump.

10 Event is classified as SAE 2.2.2 (R)eactivity, (I)nstrument, (Qomponent, (M)aior 2/22/2007 10:20:41 AM 3of8 NRC Exam Submittal

Facilitv: Nine Mile Point I Op-Test No.: NRC I TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO: SEE SECTION D.5.d)

1. Total malfunctions (5-8)

I ACTUAL ATTRIBUTES Total Malfunction Count:

Major is not included in this count.

2.Malfunctions after EOP entry (1-2)

Event 8 CRD Pump Trip Event 9 Abnormal Events Count:

Containment Spray Pump Trip Does not include the SRO 'S 3.Abnormal events (2-4)

Event 3 SOP-I .4 Event 5 EC Tube Leak

4. Major transients (1 -2)

I 2 1

related events. These are considered separately.

Event 6 Turbine High Vibration and Steam SRO TS Events Leak into the Turbine buildina Event 2,3and 5 are SRO Tech

5. EOPs enteredirequiring substantive 1 Spec evaluation events.

actions (1 -2)

EOP-4 Primary Containment

6. EOP contingencies requiring substantive 1 actions (0-2)

EOP-3 Failure To Scram I 7. Critical tasks (2-3) I 3 Operators I SRO

- - I S- R O- 1 Minnick I ATC RO R1 French R3 O'Brien SRO 2 Driscoll BOP RO R2 Hibbert R4 Revelle R5 DeGroot 2/22/200710:20:41 AM 4 of 8 NRC Exam Submittal

Facility: Nine Mile Point 1 Scenario No.: NRC-03 Op-Test No.: NRC TARGET Q UA NT ITATIVE ATTR IBUTES ACTUAL 2 and 3 AND 4 and 5 events can (PER SCENARIO; SEE SECTION D.5.d) ATTRIBUTES be run simultaneously, to

1. Total malfunctions (5-8) 7 improve efficiency.

Events 3,4,6,7,9,10,1 I ~

2. Malfunctions after EOP entry (1-2) 3 Total Malfunction Count:

Event 9 RPS failure Event 10 RB Major not included in this count.

Ventilation failure and Event 1ILoss of FW ~

3. Abnormal events (2-4) 2 Abnormal Events Count:

Event 6 Rod Drift Event 7 FWLC Does not include the SRO TS

4. Major transients (1-2) 1 related events. These are Event 8 EC Steam Leak with Isolation considered separately.

FaiIu re ~

5. EOPs enteredlrequiring substantive 2 SRO TS Events actions (1-2) Event 3 and 5 are SRO Tech EOP-2 RPV and EOP-5 Sec Cont Spec evaluation events.

6. EOP contingencies requiring substantive 2 actions (0-2)

EOP-3 Failure To Scram; EOP-8 RPV Blowdown

7. Critical tasks (2-3) 4 2/22/2007 10:20:41 AM 6 of 8 NRC Exam Submittal

Form ES-D-1 Facility NMPI Scenario No NRC 4 Op-Test No NRC Initial Conditions IC20 Reduce Power to 95% wlth RCS Flow Turnover Feedwater Pump 11 IS out of service for repairs Red Clearance applied HPCl LCO in effect LIE 1

Event Malf No Event Type*

R Event Description Return power to 100°/o by raising Recirc Flow.

2 N Switch CRD Stabilizing Valves from A and B to E and F per NI-OP-(BOP) 5, Section F.4.1 3 NM19C I (BOP) APRM 13 fails upscale resulting in half scram and Tech Spec entry.

Bypassing channel and resetting half scram is required.

TS (SRO) 4 RROGA C Recirc Pump 11 seal leakage requires pump removal from service.

(BOP) Pump suction valves fail to fully close resulting in partial loop RRO7A isolation. Tech Spec 3.1.7.e is entered for 4 loop operation.

TS Overrides (SRO) 5 TC06 C (RO) Electrical Pressure Regulator Failure Oscillations. The EPR is removed from service and the Mechanical Pressure Regulator (MPR) is placed in service 6 TC08 M (ALL) Mechanical Pressure Regulator Failure Low. The MPR fails low resulting in rapid pressure and power rise. An automatic reactor scram occurs.

7 ED07 C (RO) Electric Fault on Emergency AC Powerboard PB102. Diesel Generator 102 automatically starts, but does not close in on the bus due to the fault. DG102 must be manually shutdown due to loss of power to the diesel auxiliaries. Downstream 600 VAC Powerboard PBI 6B must be re-energized from an alternate source.

8 FW03B C Motor Driven Feedwater Pump 12 trips resulting in a loss of high (BOP) pressure feed. Additional high pressure injection sources (CRD and Liquid Poison) must be started as directed from EOP.

9 RR29 C (RO) A small LOCA (approximately 14%) occurs which reduces vessel inventory and level lowers to top of active fuel. Containment Spray system operation is required due to elevated Drywell pressure.

10 CSOI B C Core Spray Pump 112 trips and Core Spray Pump 122 suction (BOP) strainer becomes plugged. Injection can be restored using CS05D Feedwater Booster Pumps, after depressurizinq the RPV.

11 I SRO Classify event as ALERT 3.1 .I

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2/22/2007 10:20:41 AM 7 of 8 NRC Exam Submittal

Facilitv: Nine Mile Point 1 Scenario No.: NRC 4 Op-Test No.: NRC TARGET QUANTITATIVE ATTRIBUTES fPER SCENARIO: SEE SECTION D.5.d) 1, Total malfunctions (5-8)

I ACTUAL ATTRIBUTES 6

Total Malfunction Count:

Major not included in this count.

Events 3,4,5,7,8,10

2. Malfunctions after EOP entry (1-2) 4 Event 7,8,9,10 Abnormal Events Count:

3. Abnormal events (2-4) 2 Does not include the SRO TS Event 4.5 related events. These are

4. Major transients (1-2) 1 considered separately.

Event 6 2 SRO TS Events

5. EOPs enteredlrequiring substantive actions (1-2) Event 3 and 4 EOP-2 RPV and EOP-4 Pri Cont

6. EOP contingencies requiring substantive 2 actions (0-2)

Alternate Level Control of EOP-2 EOP-8 RPV Blosdown

7. Critical tasks (2-3) I 2 Operators 2/22/2007 1 1:00:49 AM 8 of 8 NRC Exam Submittal