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 *I from that specified in the table based on NRC revisions The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. 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.

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.

9 ES 401, Page 1 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 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 R 0 4 9 295003 Partial or Complete Loss of AC 16 RO 50 295004 Partial or Total Loss of DC Pwr / 6 RO 51 295005 Main Turbine Generator Trip / 3 RO 52 295006 SCRAM / 1 1 ~ 0 5 3 295016 Control Room Abandonment / 7 1 RO54 295018 Partial or Total Loss of CCW 18 RO 55 295019 Partial or Total Loss of Inst. Air 18 RO 56 295021 Loss of Shutdown Cooling / 4 RO 57 295023 Refueling Acc Cooling Mode / 8 RO 58 295024 High Drywell Pressure / 5 1 R 0 5 9 295025 High Reactor Pressure / 3 1 R 0 6 0 295026 Suppression Pool High Water Temp.

15 R 0 6 1 295028 High Drywell Temperature / 5 RO 62 295030 Low Suppression Pool Wtr Lvl / 5 RO 63 AAI.02 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER:

Systems necessary to assure safe plant shutdown I

AA2 06 Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP Feedwater temperature AK2.04 Knowledge of the interrelations between SCRAM and the following I Turbine Trip Logic I

AA2 02 Ability to determine and/or interpret the AAI 07 Ability to operate and/or monitor the nd/or monitor the UPPRESSION POOL 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)

EA1.07 Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL:

Safetyhelief valves EK1.O1 Knowledge of the operational implications of the following concepts as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

Reactor pressure effects on reactor power EK3.07 Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

Various alternate methods of control rod insertion 295031 Reactor Low Water Level / 2 170 64 3.7 1

4.1 1

4.2 1

295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown 1 1 RO65 3.5 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown

/I RO66 1

295038 High Off-site Release Rate I 9 RO 67 AK2.01 Knowledge of the interrelations between PLANT FIRE ON SITE and the following:

Sensors / detectors and valves 600000 Plant Fire On Site / 8 RO 68 2.6 1

KIA Category Totals:

Group Point Total:

20 EA1.06 Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE:

Plant ventilation 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 295008 High Reactor Water Level RO 69 29501 2 High Drywell Temperature15 RO 70 29501 3 High Suppression Pool Temperature15 RO 71 295014 Inadvertent Reactivity Addition/l RO 72 295015 Incomplete SCRAMII RO 73 295029 High Suppression Pool Water Level/!?

RO 74 295033 High Secondary Containment Area Radiation Levels/9 RO 75 KIA Category Point Totals:

WA Topic@)

AK3.04 Knowledge of the reasons for the following responses as they apply to HIGH REACTOR WATER LEVEL:

Reactor feed pump trip AK2.02 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following:

Drywell cooling 2.1.30 Ability to locate and operate components /

including local controls AA1.05 Ability to operate and / or monitor the following as they apply to INADVERTENT REACTIVITY ADDITION:

Neutron monitoring system AKI.03 Knowledge of the operational implications of the following concepts as they apply to INCOMPLETE SCRAM:

Reactivity effects EK3.01 Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL:

Emergency depressurization EA2.01 Ability to determine andlor interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area radiation levels Group Point Total:

IR 3.3 3.6 3.9 3.9 3.8 3.5 3.8 1

1 1

1 1

1 1

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 Form ES-401-1 Plant Svstems - Tier 2IGroup 1 (RO)

IR I

System # / Name WA Topic(s)

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

3ecirculation system 3.1 1

1 205000 Shutdown Cooling 4.0 3.7 1

1 (3.01 Knowledge of the effect that a loss or nalfunction of HIGH PRESSURE COOLANT NJECTION SYSTEM will have the following:

ieactor water level control 206000 HPCl RO 12 206000 HPCl 1 R 0 1 3 44.04 Ability to manually operate and/or nonitor in the control room:

Major system valves 66.07 Knowledge of the effect that a loss or malfunction of the following will have on the ISOLATION (EMERGENCY) CONDENSER:

4.C. Dower 1

1 3.0 4.2 2.5 3.1 207000 Isolation (Emergency)

Condenser RO 14 144.07 Ability to manually operate and/or monitor in the control room: Manually initiate the isolation condenser K5.05 Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM:

System venting 207000 Isolation (Emergency)

Condenser RO 15 1

1 1 209001 LPCS K2.02 Knowledge of electrical power supplies to the following:

Explosive valves 21 1000 SLC 21 2000 RPS 3.5 1

1 1 -

1 1

K6.03 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR PROTECTION SYSTEM:

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

RPS status 2.1.32 Ability to explain and apply system limits and precautions 3.6 3.4 3.1 1 215003 IRM 215003 IRM 1 R 0 2 0 K6.02 Knowledge of the effect that a loss or malfunction of the following will have on the SOURCE RANGE MONITOR (SRM)

SYSTEM:

24/48 volt DC power 215004 SRM RO 21 K4.07 Knowledge of AVERAGE POWER RANGE MONlTORlLOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following:

Flow biased trip setpoints 3.7 21 5005 APRM/LPRM RO 22 A3.08 Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:

Reactor pressure 4.2 1

21 8000 ADS RO 23 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 Supply Shutoff RO 24 223002 PClSiNuclear Steam Supply Shutoff RO 25 239002 SRVs I R026 239002 SRVs RO 27 259002 Reactor Water Level Control RO 28 I

261000 SGTS RO 29 262001 AC Electrical Distribution RO 30 262002 UPS (ACIDC)

RO 31 263000 DC Electrical Distribution RO 32 264000 EDGs 1 ~ 0 3 3 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water KIA Category Point Totals:

K3.11 Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:

Plant ventilation 42.09 Ability to (a) predict the impacts of the ollowing on the PRIMARY CONTAINMENT SOLATION SYSTEMlNUCLEAR STEAM

$UPPLY SHUT-OFF; and (b) based on those iredictions, use procedures to correct, control, ir mitigate the consequences of those abnormal conditions or operations:

System initiation (2.01 Knowledge of electrical power supplies o the following: SRV solenoids

.(3.02 Knowledge of effect that a loss or nalfunction of the RELIEFKAFETY VALVES Nil1 have on the following: Reactor over xessurization 61.04 Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following:

Reactor feedwater flow A I.01 Ability to predict andlor monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including:

System flow A2.03 Ability to (a) predict the impacts of the following A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of offsite power K3.14 Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following:

Rx power A3.01 Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including:

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

Air temperature K1.01 Knowledge of the physical connections and /or cause-effect relationships between CCWS and the following:

Service water system Group Point Total:

2.8 3.6 2.8 4.2 3.5 2.9 3.9 2.e 3.2 3.2 3.:

2.s 3.:

ES 401, Page 6 of 9 1

1 1

1 1

1 1

1 1

1 1

1 -

1 26 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 Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

KIA Topic(s) 1 1

IR -

3.4 3.0 3.2 4.0 2.9 3.0 2.5 2.9 2.9 2.7 System # / Name I 201002 RMCS

<I

.05 Knowledge of the physical

onnections and/or cause-effect

.elationships between REACTOR MANUAL CONTROL SYSTEM and the

'ollowing:

3od worth minimizer 42.06 Ability to (a) predict the impacts of

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 201003 Control Rod Drive Mechanism 41.01 Ability to predict and/or monitor shanges in parameters associated with 3perating the RECIRCULATION FLOW CONTROL SYSTEM controls including:

Recirculation pump speed 1

202002 Recirculation Flow Control RO 39 1

2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls AI.03 Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:

TORUSiSUPPRESSlON POOL COOLING MODE controls including:

System pressure A1.10 Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:

CONTAINMENT SPRAY SYSTEM MODE controls including:

Emergency generator loading 215001 Traversing In-core Probe RO 40 1

1 219000 RHRILPCI: TorusIPool Cooling Mode RO 41 I

226001 RHRILPCI: CTMT Spray Mode RO 42 233000 Fuel Pool Cooling/Cleanup 1

1 1

A2.05 Ability to (a) predict the impacts of 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 A3.07 Ability to monitor automatic operations of the REACTOR CONDENSATE SYSTEM including:

Feedwater heater level 256000 Reactor Condensate RO 44 I 259001 Reactor Feedwater K1.07 Knowledge of the physical connections and/or cause-effect relationships between REACTOR FEEDWATER SYSTEM and the following: A.C. electrical power K5.06 Knowledge of the operational implications of the following concepts as they apply to OFFGAS SYSTEM:

Catalytic recombination 1

271 000 Offgas RO 46 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 RO 47 288000 Plant Ventilation RO 48 KIA Category Point Totals:

A2.09 Ability to (d) predict the impacts of the following on the RADIATION 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 A2.03 Ability to (a) predict the impacts of the following on the PLANT 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 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

KIA #

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

1.

Conduct of 0 pe ra t ions 2.1.29 RO 2 Knowledge of how to conduct and verify valve lineups.

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

2.2.1 RO 4

2.

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

Knowledge of process for controlling temporary changes.

2.2.1 1 RO 5 2.2.25 RO 6 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

2.3.1 RO 7 Knowledge of 10CFR20 and related facility radiation control requirements.

3.

Radiation Con t ro I 2.3.1 1 RO 8 Ability to control radiation releases.

I

4.

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

Emergency Procedures /

Plan 2.4.48 RO 10 Ability to interpret control room indications to verify status and operation of system/ and understand 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 T I G I T I G2 ES-401 Record of Reiected K/As (RO)

Form ES-401-4 NA NA 295027 High Containment Temperature (Mark 111 Containment Only). Not applicable to facility.

29501 1 High Containment Temperature (Mark 111 Containment Only). Not applicable I

I Tier / Group I Randomly Selected WA I Reason for Rejection T2G1 T2G1 to facility.

203000 RHRILPCI: Injection Mode (Plant Specific).

Not applicable to facility design.

209002 Hiah Pressure Core SDrav Svstem (HPCS).

NA NA T2G1 T2G2 T2G2 T2G2 T2G2 T2G2 Not applicable to facility design.

217000 Reactor Core Isolation Cooling System (RCIC).

Not applicable to facility design.

201 004 Rod Sequence Control System (Plant Specific).

Not applicable to facility design.

201005 Rod Control and Information System (RCIS).

Not applicable to facility design.

215002 Rod Block Monitor System.

Not applicable to facility design.

230000 RHRILPCI: Torus/Suppression Pool Spray Mode.

Not applicable to facility design.

239003 MSlV Leakage Control System.

NA NA NA NA NA NA T I GI T I GI T I G2 T2G1 T2G1 T3 T3 T3 T3 T l G l I selected G 2.4.49 (genericj topic. (7/6/06)

T I G I I 295019 2.1.28 I Randomly selected then rejected because the statement is not applicable to the 29501 9 A I 295024 AI 295013 AI 223002 K2 262001 K2 2.1 2 1 2.1.17 2.1.20 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)

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)

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

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)

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)

Randomly selected then rejected due to inability to develop discriminating written question. 2.1.I 7 randomly selected. (715106)

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

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)

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)

Randomlv selected then reiected because there are no K1 tooics. Randomlv 2.4.7 295016 K1 T I G2 T2G1 T2G2 emergency event. Randomly selected G 2.2.22. (7/6/06).

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)

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)

Randomlv selected then reiected because both statements are below 2.5.

295033 2.2.22 262002 K3.04 201 002 K2 T2G2 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 Randomly selected K1 and statement K1.05 (7/6/06)

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.

215001 K3 ES 401, Page 1 of 2 2007 NRC - RO Written Record of Rejected KAs Final Friday, February 16, 2007 T2IG1 T2IG1 Randomly selecfed G 2.4.49 (7/6/06)

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

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) 209001 K5.04 218000 K1.05

TliGl 295001 AA2.01 T l i G l 295006 AK2.06 Changes made after draft submittal and I\\

T2iG1 1 264000 K4.03 (R033)

T2iG2 259001 A1.O1 (RO 45)

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

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)

TliGl TliGl T l i G l TlIG2 T3 er outline submittal and NRC review. (9/27/06-10/25/06)

Rejected during question development due to overlap (double jeopardy) with RO 28.

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

Rejected during question development due to overlap (double jeopardy) with RO 47.

295023 AA1.04 (RO 58) 295019 G2.2.22 (RO

56) 295024 G2.2.25 (R059) 295033 G2.4.49 (RO

75)

G2.4.23 (RO 9)

Randomly selected 295023 AAI.07. (9128i06)

Rejected during question development due to KA statement is not applicable to topic area. No LCO or safety limit associated with loss of air. Randomly selected AK2.01, (9/28/06)

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)

Rejected during question development. Any acceptable question that could be 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 T2iG2 tested in other parts of the exam Randomly selected EA2.01 (10/6/06)

Reiected durina auestion develoDment dde 10 inabilitv to deve OD an acceDtable RO 201003 K4.08 (R038) job related question that matches the statement. Statkment IS primarily an' SRO topic. Randomly selected G2.4.13 (1 0/7/06) 2 review. (1 0/27/06-)

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)

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 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 9

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)

AA2.03 Ability to determine and/or interpret the 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 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER:

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

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

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

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

Group Point Total:

IR -

3.3 3.7 4.1 3.5 3.9 3.9 4.0 1

1 1

1 1

1 1 -

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/Grou~ 1 (SRO)

WA Topic(s)

~~

A2 10 Ability to (a) predict the impacts of the 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 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 2.4.1 1 Knowledge of abnormal conditions procedures 2.2.24 Ability to analyze the affect of maintenance activities on LCO status A2.05 Ability to (a) predict the impacts of the 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:

IR -

3.4 3.7 3.6 3.8 3.4 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 Plant Systems - Tier 2/Group 2 (SRO)

I WA Topic(s)

A2.12 Ability to (a) predict the impacts 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 mitigation strategies.

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

Group Point Total:

IR -

2.9 4.0 3.7 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 1.

Conduct of 0 pera t ions

2.

Equipment Control 3

Radiation Control

4.

E merge n cy Procedures I Plan Tier 3 Point Tota KIA #

2.1.6 SRO 1 2.1.7 SRO 2 Subtotal 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 T I G I T I G2 Tier / Group I Randomlv Selected WA I Reason for Reiection NA NA 295027 High Containment Temperature (Mark 111 Containment Only). Not applicable to facility.

29501 1 High Containment Temperature (Mark 111 Containment Only). Not applicable T I G I T l G l T I G2 T2G1 T l G l T l G l T I G2 T I G2 T2G1 T2G2 295019 AI 295024 AI 29501 3 AI 218000 G 2.1.21 295023 G 2.1.24,2.4.42 295031 G 2.3.5 295022 G 2.4.36, 2.3.9 295036 G 2.2.27, 2.4.3 218000 G 2.1.21 223001 G2.1.24 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)

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)

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)

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

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

Randomly selected, then rejected because they are not linked to 10CFR55.43(b).

Randomly selected 2.2.28. (7/6/06)

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

Randomly selected, then rejected because the statements are not applicable to this topic. Randomly selected 2.2.17 (7/6/06)

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)

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

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 T2/G 1 T2iG2 TIIG2 Changes mad TI/GI T2/G2 T2/G 1 during draft development i 261000 A2.12 223001 G2.2.26 295035 EA2.02 after exam suumitta, for NI 295031 G2.4.49 234000 A2.02 21 1000 G2.2.25 er outline submittal and NRC review.

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 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 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) 1011 3/06 review and aonroval 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).

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).

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 Conduct of Operations Shift Turnover RO ADMIN 2 Eq u i pmen t Control Use of Electrical Prints RO ADMIN 3 RO ADMIN 2 Eq u i pmen t Control Use of Electrical Prints RO ADMIN 3 Radiation Control Radiation Hazards RO ADMIN 4 TY Pe Code*

D N

N D, p NRC 2004 Date of Examination:

December 11,2006 Operating Test Number:

NA Describe activity to be performed Facility: Nine Mile Point 1 Examination Level: RO Administrative Topic (see Note)

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

2.1.I8 (2.9) Ability to make accurate 1 clear and concise logs /

records I status boards 1 and reports.

Perform Control Room System Lineup Verification Evaluate conditions provided in S-PM-DO01 Control Room System Lineup Verification for Control Room Ventilation System and determine the required actions for out of position 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 Identify and locate electrical drawings related to RPS circuits.

Use the drawings to describe the effect of installing RPS jumpers on how scram signal is reset prior to initiating another 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 Of Rad And High Rad Areas.

Given radiological conditions and a survey map related to an area to be inspected, ensure the appropriate radiological 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-OPS-01; 3.10, N1-ST-DO; 7.0 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 2006 Unit 1 NRC RO Admin Outline Submittal 1 of1

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point 1 Administrative Topic (see Note)

Conduct of Operations SRO ADMIN 2 Equipment Control SRO ADMIN 3 Radiation Control SRO ADMIN 4 Emergency Plan SRO ADMIN 5 TY Pe Code*

N D

N D

Date of Examination:

Operating Test Number:

NA December 11, 2006 Describe activity to be performed Assess Reportability Requirements For Maintenance Activity 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 Actions In Response To The Event Given plant conditions determine the reactivity event severity level 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; 3.1 3 Review Reactor Engineering Thermal Limit Surveillance Given daily surveillance procedure with thermal limits exceeded, 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 Monitor Given plant conditions, determine operability of an effluent radiation monitor and apply action statements contained in the station ODCM.

2.3.1 1 (3.2) Ability to control radiation releases.

ODCM (CR NM-2004-976)

Classify Emergency Event and Perform PARs Given plant conditions at an existing Site Area Emergency, 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 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 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 WL C to automatic control, level transmitter fails downscale, requiring RO Only. This JPM is not performed by SRO-I Proc N1-SOP-1 MSlVs at Power Proc NI-ST-Q26, Sections 8.2 and 8.3 LC1 05-01 NRC Exam 2006 Submittal 02/26/07 9:52 AM 1 of2 Type Code*

Safety Function 1

REACTIVITY CONTROL 4

I I HEAT REMOVAL REACTOR WATER INVENTORY CONTROL 7

INSTRUMENTATION I

3 REACTOR PRESSURE CONTROL

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

• lr' 5

e I,r d

j Y

3

. 82' JPM 10 UPS/ Transfer RPS Bus 11 from UPSI62A to 162B (RPS Bus 11 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 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 T ENGINE condition occurs, Proc N1-SOP-21.2 Control Room E Actions KA 29501 6 AAI.04 3 113 2 Bank 01-OPS-PJE-200-1-78 1

R, P, D, E, L REACTIVITY CONTROL 7

INSTRUMENTATION 6

ELECTRICAL

(@

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 2 o f 2 02/26/07 9:52 AM

RR27 C (ALL)

R (SRO RO)

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.

s ready to be placed in service, following maintenance.

Event Description PR is in service. EPF Turnover:

Event No.

1 FWO2C C (TS SRO)

Feedwater Booster Pump 13 auto trips. The pump is a HPCl component and must be declared inoperable. SRO enters TS 3.1.8 and the Dump must be restored within 15 days.

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

2 3

RP20B I (TS SRO)

Drywell High Pressure Transmitter 201.2-476A fails downscale.

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 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.

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%

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

MS05 6

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

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

Facility: Nine Mile Point 1 Scenario No.: NRC-01 TARGET QUANTITATIVE ATTRIBUTES I

ACTUAL

3. Abnormal events (2-4)

4. Major transients (1 -2)

Event 6 SOP-I.5 and Event 7 SOP-25.1 Event 7 Loss of Vacuum (PER SCENARIO; SEE SECTION D.5.d)

I ATTRIBUTES 2

1

1. Total malfunctions (5-8)

Events 4,5,6,8,9,10 SRO ATC RO BOP RO 6

SRO 2 Driscoll R2 Hibbert R4 Revelle R5 DeGroot R1 French R3 OBrien SRO 1 Minnick

2. Malfunctions after EOP entry (1-2)

Events 9 and 10 2

5. EOPs entered/requiring substantive Event 6 EOP-2 RPV; EOP-4 Pri actions (1 -2)

Containment 2

6. EOP contingencies requiring substantive Event 9 EOP-7 RPV Flooding actions (0-2) 1

7. Critical tasks (2-3)

I 2

Op-Test No.: NRC Total Malfunction Count:

Major not included in this count.

Didnt count Event 1 and 3, because these only require SRO tech spec use.

Abnormal Events Count:

Does not include the SRO related events. These are considered separately.

S SRO TS Events Event 1 and 3 are SRO Tech Spec evaluation events.

Operators 2/22/2007 10:20:41 AM NRC Exam Submittal 2 o f 8

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Malf. No.

ECO9B AD05 RR28 ECO6A MS12 TU02 RD33 MSO 1 LPOIA RD35B CTO 1 A Event Type*

N C (TS SRO)

C (BOP)

(TS SRO)

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 No.

1 2

3 4

5 6

7 8

9 10 C (BOP)

M (ALL)

C (ALL)

C (BOP)

Event Description Crew performs N1 -ST-Q4, Reactor Coolant System Isolation Valve Operability Test for EC Loop 12 IVs per Section 8.2.

Steam IV 39-08R fails to fully close during testing. Valve must be 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)

ERVI 11 inadvertently opens. The crew enters SOP-I.4. An emergency power reduction to 85% is performed. The ERV will close after the fuses are pulled. Tech Spec 3.1.5 must be entered because the valve is now inoperable. TS 3.2.9 may also require entry.

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.

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.

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

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

Control Rod Drive Pump 12 trips during the scram transient.

Starting CRD Pump 11 is necessary for driving control rods.

Containment Spray Pump 11 1 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.

Event is classified as SAE 2.2.2 (R)eactivity, (I)nstrument, (Qomponent, (M)aior 2/22/2007 10:20:41 AM NRC Exam Submittal 3 o f 8

Facilitv: Nine Mile Point I Op-Test No.: NRC ATC RO BOP RO TARGET QUANTITATIVE ATTRIBUTES ACTUAL I

(PER SCENARIO: SEE SECTION D.5.d)

I ATTRIBUTES R1 French R3 O'Brien SRO 2 Driscoll R2 Hibbert R4 Revelle R5 DeGroot

1. Total malfunctions (5-8)

2. Malfunctions after EOP entry (1-2)

Event 8 CRD Pump Trip Event 9 Containment Spray Pump Trip

3. Abnormal events (2-4)

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

2

4. Major transients (1 -2)

Event 6 Turbine High Vibration and Steam Leak into the Turbine buildina 1

5. EOPs enteredirequiring substantive EOP-4 Primary Containment actions (1 -2) 1

6. EOP contingencies requiring substantive EOP-3 Failure To Scram actions (0-2) 1 I 7. Critical tasks (2-3)

I 3

Operators Total Malfunction Count:

Major is not included in this count.

Abnormal Events Count:

Does not include the SRO related events. These are considered separately.

'S SRO TS Events Event 2,3 and 5 are SRO Tech Spec evaluation events.

I SRO I SRO 1 Minnick I 2/22/2007 10:20:41 AM NRC Exam Submittal 4 of 8

Facility: Nine Mile Point 1 Scenario No.: NRC-03 TARGET Q U A N T ITAT IVE ATTR I B UTES (PER SCENARIO; SEE SECTION D.5.d)

ACTUAL ATTRIBUTES

1. Total malfunctions (5-8) 7 Events 3,4,6,7,9,10,1 I

~

3 Event 9 RPS failure Event 10 RB Ventilation failure and Event 1 I Loss of FW

3. Abnormal events (2-4) 2 Event 6 Rod Drift Event 7 FWLC

4. Major transients (1 -2) 1 Event 8 EC Steam Leak with Isolation

2. Malfunctions after EOP entry (1-2)

~

Fai I u re actions (1 -2)

~

5. EOPs enteredlrequiring substantive 2

EOP-2 RPV and EOP-5 Sec Cont

6. EOP contingencies requiring substantive 2

actions (0-2)

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

7. Critical tasks (2-3) 4 2/22/2007 10:20:41 AM NRC Exam Submittal Op-Test No.: NRC 2 and 3 AND 4 and 5 events can be run simultaneously, to improve efficiency.

Total Malfunction Count:

Major not included in this count.

Abnormal Events Count:

Does not include the SRO TS related events. These are considered separately.

SRO TS Events Event 3 and 5 are SRO Tech Spec evaluation events.

6 of 8

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 Event Malf No L I E 1

2 3

NM19C 4

RROGA RRO7A Overrides 5

TC06 6

TC08 7

ED07 8

FW03B 9

RR29 10 CSOI B CS05D 11

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Event Type*

R N

(BOP)

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

Switch CRD Stabilizing Valves from A and B to E and F per NI-OP-5, Section F.4.1 I (BOP)

TS (SRO)

APRM 13 fails upscale resulting in half scram and Tech Spec entry.

Bypassing channel and resetting half scram is required.

C (BOP)

TS (SRO)

Recirc Pump 11 seal leakage requires pump removal from service.

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

C (RO)

Electrical Pressure Regulator Failure Oscillations. The EPR is removed from service and the Mechanical Pressure Regulator (MPR) is placed in service I SRO Classify event as ALERT 3.1.I M (ALL) 2/22/2007 10:20:41 AM NRC Exam Submittal Mechanical Pressure Regulator Failure Low. The MPR fails low resulting in rapid pressure and power rise. An automatic reactor scram occurs.

7 of 8 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.

C (BOP)

C (RO)

C (BOP)

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

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.

Core Spray Pump 11 2 trips and Core Spray Pump 122 suction strainer becomes plugged. Injection can be restored using Feedwater Booster Pumps, after depressurizinq the RPV.

Facilitv: Nine Mile Point 1 Scenario No.: NRC 4 Op-Test No.: NRC 1, Total malfunctions (5-8)

Events 3,4,5,7,8,10 Event 7,8,9,10 Event 4.5

2. Malfunctions after EOP entry (1-2)

3. Abnormal events (2-4)

TARGET QUANTITATIVE ATTRIBUTES ACTUAL fPER SCENARIO: SEE SECTION D.5.d)

I ATTRIBUTES 6

4 2

4. Major transients (1 -2)

5. EOPs enteredlrequiring substantive Event 6 actions (1 -2)

EOP-2 RPV and EOP-4 Pri Cont

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

Alternate Level Control of EOP-2 EOP-8 RPV Blosdown 1

2 2

7. Critical tasks (2-3)

I 2

Total Malfunction Count:

Major not included in this count.

Abnormal Events Count:

Does not include the SRO TS related events. These are considered separately.

SRO TS Events Event 3 and 4 Operators 2/22/2007 1 1 :00:49 AM NRC Exam Submittal 8 of 8