ML051930213

From kanterella
Jump to navigation Jump to search
Final Outlines (Folder 3)
ML051930213
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/14/2005
From: Berry P
Entergy Nuclear Northeast
To: Suzanne Dennis
Operations Branch I
Conte R
References
Download: ML051930213 (46)
v • d • e


Text

ES-301 Transient and Event Checklist F o ES-301-5

~

J.A. FitzPatrick Date of Exam: May 16 - 20,2005 Operating Test No.: LOI-05-01 E

v SCENARIOS E

N 1 2 3 4 T M T

0 1 T CREW POSITION CREW POSITION CREW POSITION CREW POSITION I

Y P S A E R T 0 C RX NOR 496, IIC 7,9, 10 MAJ 8 MAJ 8 TS RX NOR 496, IIC 7,9, 10 MAJ 8 Page 1of 2

ES-301 Transient and Event Checklist Form ES-301-5 E I SCENARIOS Instructions:

1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (VC) malfunctions and one major transient, in the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author:

NRC Reviewer:

Page 2 of 2

ES-301 Competencies Checklist Form ES-301-6 APPLICANTS Competencies ae- Candidate 6 I Candidate 7 s w I - SI e a r 2 w 3 - S.

t SCENARIO SC ENARIO iNARIO SC 1 2 3 1 1 2 3 1 2 3 Interpret / Diagnose ALL ALL ALL ALL ALL ALL ALL ALL ALL Events and Conditions Comply With and ALL ALL ALL ALL ALL IALL ALL Use Procedures (1) 192, Operate Control 498, Boards (2) 9, 11 Communicate and ALL ALL Interact Demonstrate Supervisory Ability (3) 394, 697, 8,

49% I 10 Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions: Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Author:

NRC Reviewer:

LOI-05-01 NRC EXAM SCENARIO 3 NARRATIVE The scenario will begin with the reactor at 75% Core Thermal Power. A seismic event will result in several failures starting with a 'crywolf' RFP Turbine alarm on high vibration. Vibration will be slightly elevated and monitored by the crew.

The following event will be a HPCI power supply loss that will disable HPCI. The CRS will declare HPCI inoperable. The crew will then notice a slow loss of condenser vacuum and perform the AOP actions including a power reduction using recirculation flow. The major event will be a Main Steam Line Break in the Turbine Building that will fail to automatically isolate. A manual scram will be inserted followed by manually isolating the steam lines. During the scram, one control rod will fail to scram but will be inserted using RMCS. RCIC will be operated for Level Control and the SRVs will be operated in Pressure Control.

Several SRVs will fail to open forcing alternative SRV selection. The scenario will terminate upon stabilization of Pressure and Level Control.

Appendix D Scenario Outline F O ES-~-1

~

Facility: 3. A. FitzPatrick Scenario No.: 3-1 Op-Test No.: LOI-05-01

    • MODIFIED CONTINGENCY SCENARIO FROM LOI-03-01 EXAMINATION**

Conditions: 75% CTP Turnover: Alpha Circulating Water Pump Just Repaired and Returned to Service; Return Power to 92% Using Recirculation Flow; Hold at 92% for Reactor Engineers (Credited Position) I Event Description I I I Seismic Event (Cry Wolf RFP Turbine Vibration Alarm, RFP FW05:A Vibration)

I 2 1 RFI HP15 I C I (SNO) HPCI Power Supply Loss (Aux Oil Pump, MOV)

I ------ I ------ I TS I (CRS) HPCI Inoperable I 3 I MCOl I C I (SN0)Slow LossofCondenserVacuum I I ------ I I (SNO) AOP-Required Power Reduction I

4 5 1 RP13 MS05 I R M I (ALL) Main Steam Line Break in Turbine Building (w/ Failure to Auto-Isolate, Manual Scram); EOP-2 I 6 I RDl3(X) I C I (RO) One (1) Control Rod Fails to Scram I 7 I ------ I ------ I RCIC for Level Control; SRVs for Pressure Control (Note 1/21 8 AD07(X) I/C (SNO/RO) Several SRVs Fail to Open NOTE 1- RCIC is an IPE Risk-Reduction System NOTE 2 - Use of RCIC for Level Control Upon HPCI Failure is an IPE Key Operator Action (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 8.4.4 - ALERT

Amendix D Scenario Outline Form ES-D-1 Facility: 1. A. FibPatrick Scenario No.: 3-2 Op-Test No.: LOI-05-01 I Facility: 1. A. FitzPatrick Scenario No.: 3-3 Op-Test No.: LOI-05-01

LOI-05-01 NRC EXAM SCENARIO 2 NARRATIVE The scenario will begin with a reactor startup in progress at 3-5% Core Thermal Power. Turnover information will indicate that repairs to the 'A' Circulating Water Pump have just been completed. Crew will be directed to place the 'A' CW pump in service and secure 'B'. The "selected" Reactor Water Level Transmitter will fail downscale resulting in a slow rise in RPV Water Level. The crew will take manual control of RPV water level, swap level columns and return to automatic level control. The CRS will declare the failed transmitter inoperable. An individual Control Rod will Scram due to an airline rupture. The CRS will declare the Control Rod inoperable. SRV leakage will result in mechanical opening of the SRV (industry OE) requiring the crew to manually scram the reactor.

Additionally, this will result in actions to place Torus cooling in service and remove the SRV fuses. A 4160 VAC bus loss will remove / degrade the containment cooling functions of the loop in Torus Cooling. The crew will enter and perform EOP-2. The leaking SRV tailpipe will start leaking into the Torus air space resulting in EOP-4 entry. Torus spray will have to occur on the opposite RHR loop; and shortly after initiation, the only RHR pump in that loop will trip unexpectedly. This will force the crew to conclude that an Emergency Depressurization (contingency) is or will soon be required. The scenario will terminate upon the opening of 7 ADS valves.

Appendix D Scenario Outline Form ES-D-1 Facility: J. A. FitzPatrick Scenario No.: 2-1 Op-Test No.: LOI-05-01 Examhers: I SROI-1 SURROGATE Initial Conditions: 3% - 5% CTP, Reactor Startup In-Progress Turnover: Reactor Startup In-Progress at 3 - 5% CTP; Currently at OP-65, Step D.19; Reactor Mode Switch in Startup; Continue Power Ascent to 25% CTP Using Control Rods; Reactor Engineer is present in Control Room; Alpha Circulating Water Pump Has Just Been Repaired; Start Up Alpha CW Pump and Secure Bravo CW Pump for Inspection.

Event Event No. Malf. No. (Credited Position) I Event Description 1 ------ N (SNO) Swap Circulating Water Pumps 2 RR19(X) I (SNO) Selected Level Transmitter Fails Downscale 3 I ------ I TS I (CRS) Level Transmitter Inoperable 4 RD12:(XXW) I (SNO) Control Rod Scram 5 ------ TS (CRS) SRV Inoperable 6 ED18(X) C (SNO) 10500 / 10600 Bus Loss

------ ------ Degraded Containment Cooling on Operating Side AD05(X) 7 AD06(X) C (SNO) Leaking SRV Opens Mechanically AD08(X) 8 ------ M (ALL) Manual Scram; EOP-2 9 MS16(X) C (SNO) SRV Tailpipe Failure in Torus; EOP-4 10 I RHOl(X) I C I (SNO) RHR Pump Trip During Torus Spray 11 I ------ I M I (ALL) RPV Emergency Depressurization (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 3.1 .I - ALERT

Amendix D Scenario Outline Form ES-D-1 Facility: J. A. FitzPatrick Scenario No.: 2-2 Op-Test No.: LOI-05-01 I Facility: J. A. FitzPatrick Scenario No.: 2-3 Op-Test No.: LOI-05-01 ANTICIPATED EAL: 3.1 .I- ALERT

LOI-05-01 NRC EXAM SCENARIO 1NARRATIVE The scenario will begin with the plant operating normally at 100% Core Thermal Power. HPCI surveillance testing has just been completed and the Torus Cooling Mode of RHR is to be secured. During the shutdown of the Torus Cooling Mode, the "A" RHR/SW pump will trip. Dispatch of the NPO will produce a local report of "A" RHR/SW pump breaker charring. The CRS will declare the RHR/SW Subsystem inoperable. Per Reactor Engineer's guidance, a power reduction to 95% will then be commenced for performance of ST-20B. During the power reduction, "C" APRM will not respond as expected. The APRM will be declared inoperable and bypassed. An NPO performing rounds will report a sizable EHC leak in the running " A EHC pump discharge filter. The crew will swap the running EHC pumps isolating the leak. A rupture in the RHR suction piping will then start a slow reduction in Torus Water Level. AOP-9 may be entered momentarily resulting in immediate direction to enter EOP-4/EOP-5. EOP-4 will be entered on low Torus water level and EOP-5 will be entered on High Sump/Floor Water Level in the Crescent Area. Local investigation will reveal that the leak is isolable and isolation actions will commence. Before Torus Water Level reaches 10.75 feet, HPCI will be tripped and a manual scram inserted.

Shortly after the manual scram occurs, the leak will be reported isolated. The manual scram will result in a power reduction to 20-30% due to a blockage in the SDIV(s). EOP-2 will be entered then exited to EOP-3 resulting in a start of either SLC pump. SLC injection will fail resulting in a manual start of the other SLC pump which will also fail shortly after start. The Level/Power Control contingency will be exercised by first terminating and preventing injection sources followed by re-injection at a reduced RPV water level. A loss of the remaining EHC pump will result in a turbine trip and a loss of the bypass valves shortly thereafter. This will force transitioning pressure control to the SRV's and trending the approach to the Boron Injection Initiation Temperature (BIIT). I f BIIT is reached, another Terminate and Prevent will result in RPV water level control at an even lower level. Timely action to complete rod insertion may avoid exceeding BIIT. The control rod insertion success path will require resetting the scram signal, draining the SDIV(s) and re-inserting a manual scram.

Upon inserting the second manual scram, all control rods will be reported full-in and the scenario will be terminated.

Amendix D Scenario Outline F o ES-D-1

~

Facility: 1. A. FitzPatrick Scenario No.: 1-1 Op-Test No.: LOI-05-01 Initial Conditions: Operating normally at 100% U P Turnover: Operating normally at 100% CTP; RHR Loop Alpha in Torus Cooling Mode; HPCI Surveillance Testing recently completed successfully; Torus Cooling needs to be secured; Then, reduce power to 95% per Reactor Engineers guidance and perform ST-20B.

Event Event No. Malf. No. (Credited Position) / Event Description 1 I ------ I N I (SNO) Shut down Torus Cooling 2 I SW04:A I TS I (CRS) Running RHR/SW Pump Trip (Before S/D) 3 ------ R (SNO) Power Reduction to 95%

4 NMl4(X) I (RO) APRM Fails to Respond to Power Reduction

------ APRM Bypassed 5 I ------ I TS I (CRS) APRM Declared Inoperable 6 I ______ I C I (SNO) NPO Reports EHC Leak; Swap EHC Pumps 7 I RH10:A I C 1 (SNO) Torus Rupture in RHR Suction; Level Drops; EOP-5/4 8 I RD22(A/B) I M I (ALL) Manual Scram; ATWS; SDIV Blockage; EOP-3; LeveI/ Power Control 9 I SLOl:A/B I C I (RO) SLC Pump Start Failure (NOTE 1) 10 TCO2:B C (SNO) EHC Pump Trip; Turbine Trip; Bypass Valve Failure 11 ------ M (ALL) Level / Power Control NOTE 1- SLC initiation is related to the JAF IPE ATWS Dominant Accident Sequence

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 2.2.2 - SITE AREA

Amendix D Scenario Outline Form ES-D-1 Facility: 1. A. FitzPatrick Scenario No.: 1-2 Op-Test No.: LOI-05-01 I

Facility: J. A. FitzPatrick Scenario No.: 1-3 Op-Test No.: LOI-05-01 ANTICIPATED EAL: 2.2.2 - SITE AREA

ES-401 1 Form ES-401-I

(( Facility: I J.A. FitzPatrick Date of Exam: May 16 - 20,2005 I I I RO WA Category Points 1 SRO-Only Points Notes: 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 WA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by *1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted or justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

s P

Lr:

0 6

a z

0 d

h I

In 0

0 N

\

N d

\

h

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

ElAPE # I Name I Safety Function K/A Topic@) IR #

295001 Partial or Complete Loss of Forced AA1.07 Core Flow Circulation / 1 8 4 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLEE LOSS OF FORCED CORE FLOW CIRCULATION : 3.1 8

+ Nuclear Boiler InstrumentationSystem 295003 Partial or Complete Loss of AC / 6 62.1.7 Ability to evaluate plant performance and make operational judgments based on 3.7 14 operating characteristics / reactor behavior / and instrument interpretation.

62.1.8 (IOCFR 55.43.5 SRO Only)- 3.6 47 Ability to cmrdnate peEonnel activities outside the control room.

295004 Partial or Total Loss of DC Pwr / 6 AK2.03 Knowledge of the interrelations between PARTIAL OR COMPLRE LOSS OF D.C.

POWER and the following: 3.3 11

+ D.C. bus loads AA2.02 (WCFR 55#43.5 SUO Only] -

Ability to determine and/or interpret the following as they apply to PARTIAL OR 3.9 33 COMPLRE LOSS OF D.C. POWER:

+ Extent of partial or completeloss of D.C. power 295005 Main Turbine Generator Trip I 3 AK1.03 Knowledge of the operational implications of the following concepts as they 3.5 45 apply to MAIN TURBINE GENERATOR TRIP:

+ Pressure effects on reactor level 62.2.22 (IOCFR 55.43.2 SRO Only) - 4.1 31 Knowledge of Lmiting condtions for operationsand safety limits.

SRO onfy K/AS shown in i&fics 7/12/2005- 7:11:21AM Page 2

~~~

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

EIAPE # I Name I Safety Function KIA Topic(s) IR #

295006 SCRAM I 1 AK2.01 Knowledge of the interrelations between SCRAM and the following: 4.3 38

+ RPS 62.4.29 (A 4.0 6 Knowledge of the emergency plan.

295016 Control Room Abandonment I7 62.1.30 3.9 27 Ability to locate and operate components / including local controls.

295018 Partial or Total Loss of CCW / 8 AK2.01 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:

3.3 10

+ System loads AA2.05 Ability to determine and/or interpret the following as they apply to PARTIAL OR 2.9 37 COMPLI3-E LOSS OF COMPONENT COOLING WATER:

+ System pressure 295019 Partial or Total Loss of Inst. Air I 8 AA1.04 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:

3.3 13

+ Sewice air isolation valves: Plant-Specific 295021 Loss of Shutdown Cooling I4 AA1.06 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:

2.8 39

+ Containment / drywell temperature --

SRO only K/& shown in italics 7/12/2005 - 7:11:21 AM Page 3

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

Form ES-401-1 WAPE # IName I Safety Function KfA Topic(s) IR 295023 Refueling Acc Cooling Mode I 8 AK3.02 Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS :

3.4 12

+ Interlocks associated with fuel handling equipment 295024 High Drywell Pressure I5 EK3.05 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE: 3.5 15

+ RPVflooding 62.4.44 (IOCFR 55.432 5RO OMY] - 4.0 40 Knowledge of emergenq plan pmtective action recommendations.

295025 High Reactor Pressure I3 62.2.12 3.0 46 Knowledge of surveillance procedures.

62.1.18 Ability to make accurate / clear and concise lugs / records / status boards / and 2.9 76 reports.

EA2.01 (10CFR 55.43,2/5 SRO Only) -

Ability to determine and/or interpret the following as they apply to 4.2 98 SUPPRESSIONPOOL HIGH WA7ER EMPER4 RJRE

+ Suppression pa01 water temperature I__ --

SRO only K/As shown in its/ics 7/12/2005- 7:11:21 AM Page 4

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

Form ES-401-1 I

K K K A A G WAPE # I Name I Safety Function KIA Topic(s) IR #

1 2 3 1 2 295028 High Drywell Temperature I 5 I EK3.04 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE: 3.6 93

~~

+ Increased drywell cooling 295030 Low Suppression Pool Wtr Lvl I 5 1 EA1.06 Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: 3.4 79

+ Condensate storage and transfer (make-up to the suppression pool):

Plant-Specific 295031 Reactor Low Water Level I 2 1 EA2.02 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:

4.0 74

+ Reactor power 295037 SCRAM Condition Present and Power Above APRM Downscale or 1 EK3.01 Unknown I1 Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR 4.1 82 UNKNOWN:

+ Recirculation pump trip/runback: Plant-Specific 295038 High Off-site Release Rate I 9 1 EK2.03 Knowledge of the interrelations between HIGH OFF-SlTE RELEASE RATE and the following:

3.6 I 94

+ Plant ventilation svstems SRO only K/As shown in italics 7/12/2005- 7:11:21AM Page 5

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

EIAPE # I Name I Safety Function K K 3

A 1

KIA Topic(s) IR #

62.1.22 Ability to determine Mode of Operation.

2.8 75 AA2.09 AbiLly to determine and interpret the following as they apply to PLANTFIRE ON 2.8 57 S.:

+ mat a failled fire alarm detector ex&&

I I WA Category Totals: (RO) 11 Group Point Total: (RO) 20 I

K/A Category Totals: (SRO) Group Point Total: (SRO) 7 SRO only K/As shown in italics 7/12/2005- 7:11:21 AM Page 6

ES-401 3 Form ES-401-1 IIi BWR Examination Outline Emergency and Abnormal Plant Evolutions-Tier 1IGroup 2 (RO I SRO)

Form ES-401-1 1 UAPE # I Name I Safety Function IR #

Knowledge of the operational implications of the following concepts as they 2.9 84 apply to HIGH REACTOR PRESSURE:

295010 High Drywell Pressure I 5 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL 3.6 99 I I I I

+ Drywell floor and equipment drain sumps

- - N/A for JAF - K/A for Mark III Containments ONLY------

295012 High Drywell Temperature I 5 I AK2.02 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and 3.6 91 the following:

+ Drywell cooling 62.1.20 (IOCFR 55.43.5 SRO Only]- 4.2 Ability to executeprocedue steps.

SRO only K/As shown in italics 7/12/2005 - 7:11:21 AM Page 7

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier IIGroup 2 (RO I SRO)

KIA Topic(s) IR I #

295015 Incomplete SCRAM I 1 62.4.20 Knowledge of operational implications of EOP warnings / cautions / and notes.

3.3 I 92 EA1.O1 Ability to operate and/or monitor the following as they apply to HIGH 3.4 73 SUPPRESSION POOL WATER LEVEL:

+ HPCI: Plant-Specific I

62.4.8 (2 -

5 SRO Only]

3.7 59 Knowledge of how the event-bsed emergen~/abnorrnal operating prmdures 295034 Secondary Containment EK2.01 Ventilation High Radiation I 9 Knowledge of the interrelations between SECONDARY CONTAINMENT VENTIlATION HIGH RADIATION and the following:

3.9 54

+ Process radiation monitoring system 295035 Secondary Containment High Differential Pressure I 5 G2.1.21 Ability to obtain and verify controlled procedure copy.

3.1 I 67 SRO only K/As shown in italics 7/12/2005 - 7:11:21 AM Page 8

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 (RO ISRO)

EIAPE # I Name I Safety Function K K K A A I1 I 2 I 3 I1 I 2 GI KIA Topic(s) 500000 High CTMT Hydrogen Conc. I 5 I wing as they apply to HIGH PRIMARY CONTAINMENTHYDROGEN CONCENlR4 77ONS:

+ Oxygen monitoring system availabihw I 1 I I I I K/A Category Totals (RO) 1 2 0 2 0 Group Point Total: (RO) 1 2 Group Point Total (SRO) 3 SRO only K/AS shown in italics 7/12/2005- 7:11:21 AM Page 9

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO 1 SRO) i System # / Name G KIA Topic(s) IR #

203000 RHWLPCI: Injection 1 62.3.4 Mode Knowledge of radiation exposure limits and contamination control / 2.5 26 including permissible levels in excess of those authorized.

205000 Shutdown Cooling K2.02 Knowledge of electrical power supplies to the following: 2.5 1

+ Motor operated valves 206000 HPCl K5.05 Knowledge of the operational implications of the following concepts as they apply to HIGH PRESSURE COOLANT INJECIION S Y W M : 3.3 48

+ Turbine speed control: BWR-2,3,4 A1.07 Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM 3.7 43 controls including:

+ System discharge pressure: BWR-2,3,4

- - N/A for JAF - No IsolationCondenser(s)------------

209001 LPCS K6.03 Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY S Y W M :

3.3 29

+ Torus/suppression pool water level SRO only K/As shown in ihlics 7/12/2005 - 7:11:21 AM Page 10

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO I SRO)

System # I Name KIA Topic(s) IR #

21 1000 SLC A3.07 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including: 3.7

+ Lights and alarms: Plant-Specific 212000 RPS K3.12 Knowledge of the effect that a loss or malfunction of the REACTOR PROTECnON SYSTEM will have on the following:

3.2 32

+ Secondary containment integrity 215003 IRM K5.01 Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONlTOR (IRM) SYSTEM: 2.6 44

+ Detector operation K6.05 Knowledge of the effect that a loss or malfunction of the following will 3.1 25 have on the INTERMEDIATE RANGE MONlTOR (IRM) S Y m M :

+ Trip units SRO only K/As shown in italia 7/12/2005- 7:11:21 AM Page 11

ES-401 4 Form ES-401-I ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO I SRO)

K System # / Name KIA Topic@) IR #

1 4 215004 Source Range Monitor 1 K4.04 Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design 2.8 7 feature(s) and/or interlocks which provide for the following:

+ Changing detector position A4.05 Ability to manually operate and/or monitor in the control room:

3. I 34

+ SRM back panel switches, meters, and indicating lights 21 5005 APRM I LPRM A3.05 Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOFI/LOCALPOWER RANGE MONITOR SYSTEM 3.3 49 including:

+ Flow converter/comparator alarms -

SRO only K/As shown in italics 7/12/2005 - 7 ~ 1 1 ~ AM 21 Page 12

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline F O I ES-401-1

~

Plant Systems -Tier ZGroup 1 (RO I SRO)

K K System # / Name KIA Topic(s) IR #

5 6 21 7000 RCIC 1 K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR CORE ISOLATION COOLING S Y m M (RCIC): 3.5 41

+ Condensate storage and transfer system A2.01 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based on those 3.8 58 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

+ System initiation signal 62.4.16 ( I W R SJ.43.5 SRO Ody) 4.0 64 Knowledge of EOP implementationhierarchy and coordination with other supportprocedures.

~~

218000 ADS A4.02 Ability to manually operate and/or monitor in the control room: 4.2 97

+ ADS logic initiation SRO only K/AS shown in ihlics 7/12/2005- 7:11:21 AM Page 13

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO I SRO)

System # / Name A A A G KIA Topic@) IR #

1 2 3 223002 PClSlNuclear Steam Supply Shutoff 7 1 62.3.9 Knowledge of the process for performing a containment purge. 2.5 61 3.2 83 239002 SRVs I 7 K5.05 Knowledge of the operational implications of the following concepts as they apply to REUEF/SAFETY VALVES:

2.6 95

+ Discharge line quencher operation 62.1.11 ($ 43.

3.8 87 Knowledge of less than one hour twhniwl specification action statements for systems, 259002 Reactor Water Level A4.02 **Recent Plant Modification**

Control Ability to manually operate and/or monitor in the control room: 3.7 88

+ All individual component controllers in the automatic mode SRO only K/As shown in its/icf 7/12/2005 - 7:11:21 AM Page 14

ES-401 4 Form ES-401-1 I1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2lGroup 1 (RO / SRO)

K K 5 6 KIA Topic(s) IR #

A1.O1 Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls 2.9 56 including:

+ System flow 62.4.27 Knowledge of fire in the plant procedure. 3.0 77 AZ. 01 (ZOCTR 55.43.5 SRU Only]-

Ability to (a) predid the imp& of the following on the A. C ELECRIC4L DISlRIBlJ77ON; and (b) based on those predictionst use 3.6 60 procedures to corred, control, or mitigate the consequences of those abnormal condtions or operations:

+ Turbine/generator tr@

A4.01 Ability to manually operate and/or monitor in the control room: 2.8 87

+ Transfer from alternative source to preferred source SRO only K/As shown in iikilics 7/12/2005- 7:11:21 AM Page 15

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO I SRO)

System # I Name KIA Topic(s) IR #

263000 DC Electrical K1.04 Distribution Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and the 2.6 63 following:

+ Ground detection A3.01 Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including: 3.2 89

+ Meters, dials, recorders, alarms, and indicating lights A2.02 (2 WYl Ability to (a) pred,id the imp& of the following on the D.C.

ELEC7RIG4L DIS7W..U77ON; and (6) based on those predidions, use 2.9 62 proced,ures to corrd, contro4 or mitgate the wnsquences of those abnormal conditions or operations:

+ Loss of ventilation during charging 264000 EDGs K3.03 Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESELJJIT) will have on the following: 4.1 65

+ Major loads powered from electrical buses fed by the emergency generator(s) 300000 Instrument Air K2.01 Knowledge of electrical power supplies to the following: 2.8 90

+ Instrument air compressor SUO only K/AS shown in italics 7/12/2005- 7~11~21 AM Page 16

I ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier 2lGroup 1 (RO I SRO)

K A G KIA Topic(s) IR #

System # I Name 1 4 K4.01 Knowledge of CCWS design feature(s) and/or interlocks which provide for the following:

3.4 96

+ Automatic start of the standby pump K/A Category Point Totals:

(RO)

I Group Point Total: (RO) 26 (SRO)

WA Category Point Totals:

5 SRO only K/As shown in ihlics 7/12/2005- 7:11:21 AM Page 17

ES-401 5 Form ES-401-1 I

BWR Examination Outline Form ES-401-1 Plant S tems -Tier 2lGroup 2 (RO / SRO)

System # I Name KIA Topic(s) IR #

It 201002 RMCS A1.O1 Ability to predict and/or monitor changes in parameters associated with operating the REACTOR MANUAL CONTROL S Y m M controls 2.8 42 including:

+ CRD drive water flow K6.02 Knowledge of the effect that a loss or malfunction of the following will have on the CONTROL ROD AND DRIVE MECHANISM:

3.0 9 202002 Recirculation Flow Control K5.02 Knowledge of the operational implications of the following concepts as they apply to RECIRCULAllON FLOW CONTROL S Y m M : 2.6 17

+ Feedback signals 62.2.14 (IOCFR 55.43.3 5RO Only)

Knowledge of the process for making configuration changes. 3.0 30 NOT EtE -I SRO only K/As shown in italics 7/12/2005- 7~11~21 AM Page 18

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 System # I Name Plant S terns -Tier 2/Group 2 (RO / SRO)

IR #

214000 RPlS **PLANT OE*

  • 3.8 36 216000 Nuclear Boiler lnst wing on the NUCLEAR use procdures to corrd, control, or mitaate the consequences of 2.9 5 those abnormal mndittons or operations:

+ Recirculation flow: Des@k!5pecific 219000 RHWLPCI: ToruslPool K6.06 Cooling Mode Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPQ TORUS/SUPPRESSION POOL COOLING 3.7 28 MODE:

+ SuDDression mol 226001 RHWLPCI CTMT Spray 1 Mode Knowledge of the operational implications of the following concepts as they apply to RHR/LPCI CONTAINMENT SPRAY SYSTEM MODE:

2.6 68 SRO only K/As shown in italics 7/12/2005- 7:11:21AM Page 19

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems Tier 2/Group 2 (RO I SRO)

System # I Name KIA Topic@) IR #

268000 Radwaste K1.03 Knowledge of the physical connections and/or cause-effect relationships between RADWASE and the following:

2.6 2 4 Reactor building equipment drains: Plant-Specific 271000 Offgas A2.10 Ability to (a) predict the impacts of the following on the OFFGAS SYSEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 3.1 I9 conditions or operations:

4 Offgas system high flow 272000 Radiation Monitoring A2.16 Ability to (a) predict the impacts of the following on the RADIATION MONITORING S Y m M ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 2.7 66 those abnormal conditions or operations:

+ Instrument malfunctions SRO only K/As shown in italics 7/12/2005- 7:11:21AM Page 20

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 A

Plant S ,terns -Tier ZGroup 2 (RO I SRO)

A System # I Name KIA Topic(s) IR #

3 4 286000 Fire Protection K4.01 Knowledge of FIRE PROTECIION SYSTEM design feature(s) and/or interlocks which provide for the following:

3.4 20

+ Adequate supply of water for the fire protection system 290001 Secondary CTMT A2.01 Ability to (a) predict the impads of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 3.3 85 conditions or operations:

+ Personnel airlock failure 290003 Control Room HVAC A2.03 Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 3.4 71 conditions or operations:

+ Initiation/ reconfiguration failure 290002 Reactor Vessel lnternals K4.02 ** INDUSZRY OE**

Knowledge of REACTOR VESSEL INTERNALS design feature(s) and/or interlocks which provide for the following:

3.1 50

+ Separation of fluid flow paths within the vessel K/A Category Point Totals:

(RO)

Group Point Total: (RO) 12 WA Category Point Totals:

PRO)

Group Point Total: (SRO) 3 SRO only K/AS shown in its/ics 7/12/2005- 7~11~21 AM Page 21

ES-401 Record of Rejected WAS Form ES-401-4 Randomly Reason for Rejection Selected WA 295016 G2.1.5 RO WA < 2.5 (2.3), No Plant-Specific Priority 295023 AK3.05 Plant-Specific BWR-1 Only 295023 AK3.04 No Plant Procedures for Non-Coincident Scram No reasonable link between High Drywell Pressure Emergency 295024 G2.3.2 Procedures and the facility ALARA Program that is testable at the SRO level 295025 G2.2.5 RO WA < 2.5 (1.6), No Plant-Specific Priority 295026 G2.1.4 RO WA 2.5 (2.3), No Plant-Specific Priority 295038 EK2.12 Plant-Specific BWR-6 Only 600000 AA2.01 SRO WA < 2.5 (2.3), No Plant-Specific Priority 295015 G2.4.44 RO WA < 2.5 (2.1), No Plant-Specific Priority 295035 G2.1.34 RO WA < 2.5 (2.3), No Plant-Specific Priority 295035 G2.1.5 RO WA < 2.5 (2.3), No Plant-Specific Priority 203000 G2.3.7 RO WA < 2.5 (2.0), No Plant-Specific Priority 215003 K5.02 RO WA < 2.5 (2.2), No Plant-Specific Priority 215004 K4.03 RO WA < 2.5 (2.4), No Plant-Specific Priority

~

223002 G2.3.5 RO WA < 2.5 (2.3), No Plant-Specific Priority

~

No WAS > 2.5, No Plant-Specific Priority, Randomly Selected 262002 A1 Another Category No WAS In This Category, Randomly Selected Another 300000 A1 Category 300000 K5.03 RO WA < 2.5 (2.1), No Plant-Specific Priority 201004 N/A JAF - All WAS for BWRs-4&5 Only No Reasonable Link Between RPlS And Radioactive Control 214000 G3 Generic WAS 226001 K5.01 RO WA < 2.5 (2.2), No Plant-Specific Priority 7/12/2005 - 7:13107AM Page 1

ESQOI Record of Rejected WAS Form ES-4014 Tier I Randomly Reason for Rejection Group Selected KIA 212 268000 K1.15 RO KIA 2.5 (2.3), No Plant-Specific Priority No WAS In This Category, Randomly Selected Another 212 290001 K2 Category 3 G2.1.34 RO KIA 2.5 (2.3), No Plant-Specific Priority 3 G2.2.10 RO KIA 2.5 (1.9), No Plant-Specific Priority 3 G2.2.16 RO KIA 2.5 (1.9), No Plant-Specific Priority 3 G2.2.3 JAF Single Unit - KIA for Multi-Unit 3 G2.2.6 RO KIA 2.5 (2.3), No Plant-Specific Priority 3 G2.2.14 RO KIA 2.5 (2.1), No Plant-Specific Priority 3 G2.2.31 RO KIA 2.5 (2.2), No Plant-Specific Priority Rejected On Overlap With Questions 18 And 26. Randomly 111 295024 G.2.3.4 Selected Another Category KIA.

Rejected On No Reasonable Linkage Between High 112 500000 G.2.3.6 Containment H2 And Knowledge Of Requirements To Review And Approve Release Permits.

7/12/2005 - 7: 13107AM Page 2

ES-401 Generic Knowledne and Abilities Outline (Tier 3) Form ES-401-3 Facility: J.A. FitzPatrick Date of Exam: May 16 - 20,2005 RO SRO-Only KIA # Topic 62.1.20

- IR

-IR 2.1. 4.3 3 Ability to execute procedure steps.

G2.1.9 (IOCFR 5523.5 SRO Only)

Ability to direct personnel activities inside the 4.0 mntrol roam.

2.1. 62.1.27 2.8 4 Knowledge of system purpose and/or function.

I G2.1.20 4.2 Subtotal 2 2.2. 62.2.24 **Plant OE** 2.6 80 Ability to analyze the affect of maintenance activities on LCO status.

62.2.13 (d MtY) 3.8

    • Plant OE*
  • Knowledge of tagging and clearance procedures.

2.2. 62.2.1 3.7 55 Ability to perform pre-startup procedures for the facility / including operating those controls associated with plant equipment that could affect reactivity.

G2.2.29 (1 3.8 Knowledqe of SRO fuel handlim resmnsibilities.

2.2. 62.2.30 3.5 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area / communication with fuel storage facility / systems operated from the control room in support of fueling operations /

Subtotal SRO only K/As shown in ita/cs 7/12/2005 - 7:13:42 AM Page 22

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: J.A. FitzPatrick Date of Exam: May 16 - 20,2005 RO SRO-Only KIA # Topic 62.3.4

- IR

- # IR #

2.3 2.5 18 Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.

2.9 69 2.3 62.3.9 2.5 16 Knowledge of the process for performing a containment purge.

G2.3.7 (IOCFR Knowledge of the process for preparing a 3.3 70 radiaBon work pernit.

2.3 62.3.11 2.7 21 Subtotal

- 3 2.4. 62.4.2 3.9 100 Knowledge of system setpoints / interlocks and automatic actions associated with EOP entry conditions.

62.4.49 (IOCFR 4.0 22 Ability to pedorm without reference to procedures those actions that q u i m immedhte operation of system mmponenb and controls.

Knowledge of facility protection requirements including fire brigade and portable fire fighting Subtotal SRO only K/AS shown in italics 7/12/2005 - 7:13:42 AM Page 23

ES-301 Control Room/ln-Plant Systems Outline F o ES-301-2

~

Facility: J.A. FitzPatrick Date of Examination: May 16 - 20, 2005 Control Room Systems@(8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System I JPM Title I 1

Typecode* I I

Safety Function la., Verify HPCI Isolation lib, Reset PClS Group I Isolation IC. ,

~~

Re-open MSlVs Respond to CRD Pump Trip Id.

lei Swap RNLC, Single to 3-Element llf. A Swap Electrical Bus, Reserve to Normal Service

,g

.l( Perform APRM Gain Adjustments In-Plant Systems@(3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. J Remove a HCU from Service D, R 1 j.1 Start Up Main Steam Leakage Collection System N, E 9 Cross-tie Fire System to RHR Service Water Ilk.

All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams

( W A (S)imulator

LOI-05-01 Control Roomh-Plant Systems JPM Narrative Control Room Svstems:

a. Verify HPCI Isolation 0 New JPM - Simulator Alternate Path: 23MOV-15 will require operator closure; may require supervisory interface to close 0 OP-15, Section G.1 and Attachment 5 Operator must start Aux Oil Pump
b. Reset PCIS Group IIsolation Previous: From LOI-03-01 Exam (Simulator/ Low-Power/Direct from Bank)

AOP-15

c. Re-open MSIVs Previous: From LOI-03-01 Exam (Simulator/ Low-Power/Direct from Bank)

OP-1 / EP-9

d. Respond to CRD Pump Trip 0 New JPM - Simulator Set up with 1CRD Pump recently tripped (will not be returned) 0 Perform AOP-69, Section C.1.5 0 Second CRD Pump will not start 0 Alternate Path: Multiple Accumulator lights; Manual Scram
e. Swap FWLC, Single to 3-Element 0 New JPM - Simulator 0 OP-2A, Section G.34 Recent plant modification to return to service
f. Swap Electrical Bus (loloo), Reserve to Normal Service Modified from JPM 26201001A (Simulator) 0 Cannot match incoming and running voltmeters Alternate Path: match per single meter voltage method OP-46A, Section D.20 and then Section G.14

LO1-05-01 Control Roomlln-Plant Svstems JPM Narrative

g. Perform APRM Gain Adjustments Previous: From LOI-03-01 Exam (Simulator)

Alternate Path: One APRM will require adjustment ST-5D

h. N/ASRO In-Plant Svstems:
i. Remove a HCU from Service Direct from Bank (JPM 20101012) - RCA Entry Control Rod declared inoperable for maintenance on 03SOV-117/118 OP-25, Section G.1 Depressurizing N2 not required
j. Start Up Main Steam Leakage Collection System 0 New JPM - Emergency or Abnormal In-Plant I n AOP-40 due to Main Steam Line leak in Turbine Building MSIVs are closed Direction to place MSLCS "Alpha" in service per AOP-40 Standby Gas Treatment System is in service
k. Cross-tie Fire System to RHR Service Water 0 Direct from Bank (JPM 20505005) - Emergency or Abnormal In-Plant EP-8 Directed by EOP-2 Have Control Room start Electric Fire Pump

ES-301 Administrative ToDics Outline Form ES-301-1 Facility: J.A. FitzPatrick Date of Examination: May 16 - 20,2005 Examination Level (circle one): R8 Operating Test Number: LOI-05-01 Administrative Topic TY Pe Describe activity to be performed Code *

(see Note)

Conduct of Operations 62.1.7 (SRO UR:4.4) Ability to evaluateplant perlonnance and make operationaljudgmeqts &sed on operating characteristlcs / reactor behavior / and lnsfrument Interpretation.

Perform Core Thermal Heat Balance Verification (RAP-7.3.03, Section 9.2, Attachment 2)

Conduct of Operations N

Evaluate ST-23C Results (ST-23C)

Equipment Control lfing conditions for N Given a Chemistry Report, Evaluate Technical Specification Compliance (TS 3.4.6, TRM 3.4.B and Table 3.4.8-1)

Radiation Control N

Determine Visitor RCA Access Requirements (AP-07.05, Section 8.1 and Attachments 3 & 5)

Emergency Plan f the emergency ac Classify the Event Following NRC Exam Scenarios l(2) and Implement the E-Plan (IAP-1/2)

NOTE: All 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 (D)irect from bank 3 for ROs; 5 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (11)

(P)revious 2 exams (5 1; randomly selected)

(S)imulator

LOI-05-01 Administrative Topics Narrative Administrative T ~ icsD:

a. Perform Core Thermal Heat Balance Verification 0 Previous: From LOI-01-01 Exam 0 RAP-7.3.03, Section 9.2 and Attachment 2
b. Evaluate ST-23C Results /

0 NewJPM 0 Recently completed sT-23C containing errors to be identified during performance of Management SRO Review

c. Given a Chemistry Report, Evaluate Technical Specification Compliance 0 NewJPM 0 Selected steam flow rate, values for Iodine, chloride, and conductivity 0 TS 3.4.6, TRM 3.4.B and Table 3.4.B-1
d. Determine Visitor RCA Acce sdRequirements 0 NewJPM 0 AP-07.05, Section 8.1 and Attachments 3 & 5
e. Classify the Event Following NRC Exam Scenarios l ( 2 ) and Implement the E-plan 0 New JPM - Simulator IAP-1 IAP-2

Summarv of NRC Chancles to LOI-05-01License Exam Submittal Transient and Event Checklist (Form ES-301-5) revised to indicate that events are credited to the "At the Controls" operator position versus the "Balance of Plant" operator position. Revised Scenario template cover page to distinctly identify which JAF operator position would correspond to the Primary At The Controls operator position.

Transient and Event Checklist, along with Competencies Checklist (Form ES-301-6),

revised on two separate occasions to reflect attrition.

Control Room / In-Plant Systems Outline (Form ES-301-2) revised to remove Alternate Path designation from item Indigo "Remove a HCU From Service.

Scenario Outline (Form ES-D-1) Event 4 revised to remove inadvertent SRV opening and replace with control rod scram and Event 5 revised to reflect associated Technical Specification call.

NRC comments on exam submittal prior to site validation visit:

> Written Exam (RC ;at questions (6 R 0 / 1 SRO) needing revision to either th one major modification. Five other questions si ditorials. Four additional minor alterations to que: larified based on discussion with NRC: -L,Mh d=

N&L&F SRO# 23- y, L W lquired in stem SRO # 31 - ~ l l a l ootn" l ~ ~ to just "Safety Limit MCPR in distracter (d)

SRO # 47 - typo in correct response writeup (10112 versus 10312); also changed to Fundamental Knowledge.

SRO # 64 - not enough info in stem; add "required, procedurally-driven order" to stem SRO # 70 - too easy and questioned K/A match; substantial revision to more closely link to K/A and raise level of difficulty SRO # 83 - added reference to ARP 09-4-0-4 SRO # 98 - added "All other plant systems functioning normally" RO # 4 - edit stem to add "As reactor power" RO # 9 - edited stem and all four possible answers to eliminate "below" given pressures RO # 18 - questioned K/A match; restructured stem and four possible answers to address limits themselves in addition to previously existing authority to exceed.

RO # 19 - plausibility concern on Condenser Air Removal Pumps in distracters; reduced stem-provided power level from 100% to lO0/o to address concern.

RO # 48 - replaced NPSH distracter(s) with more plausible "HPCI Turbine Trip" RO # 77 - added reference to AOP-28 to better focus stem.

RO # 82 - replaced distracter (c) with more plausible "thermal hydraulic instabilities" versus "increased control rod scram times" 8 RO # 94 - edited stem to focus on EOP required actions 9 RO ## 95 - replaced distracter (c) with more plausible "HPCI isolation on high exhaust backpressure"

> Operating Exam: minor editorial corrections to two scenarios and two JPMs.

General comment on potential weaknesses of some Admin JPMs to be followed up on during the NRC's Site Validation Visit:

Scenario # 1- added "EPIC / SPDS alarm (page 9) associated with Torus Rupture; edited page 11to read "usinq either loop of RHR" and delineated OP-37 direction; edited critical task specifications on pages 16 through 19 to read with + or - designations where appropriate.

Scenario # 3 - edited critical task # 2 writeup to reflect why 200 degrees Fahrenheit was chosen as the standard.

JPM Group IReset - edited step 6 to incorporate Evaluator comment that cause of isolation was not Main Steam Hi Rad condition.

JPM Isolate and Disarm HCU - edited step 4 candidate standard/

Evaluator note to include discussion of hanging tag(s).

0 NRC comments during site validation:

> Written Exam (RO and SRO): One additional comment requiring a minor revision to question #12 to reflect "basis for restriction" statement. All previous comments resolved satisfactorily and/or changes accepted by NRC.

> Operating Exam: one minor editorial correction to one scenario as a result of validation. One Admin JPM rejected on level of difficulty and replaced with new JPM. Eight JPMs required editorial enhancements (additional information added to initiating cue, data benchmark ranges, additional performance steps):

Scenario # 1- minor editorial JPM Verify HPCI Isolation - add steps to include up to procedure step G.1.4 JPM CTP Verification - additional data (benchmark ranges) to be added; after subsequent discussion with NRC on value dependency, agreed to add "without mathematical error."

JPM Perform ST-5D - added to initiating cue that 3D Monicore is available and core power has changed 4% since last performance; also, generated acceptable 3D printout with correct MFLPD values to hand to candidate.

JPM Swap Electrical Busses - added direction to candidate to perform swap of 10100 bus and eliminated option of 10200 bus.

JPM Determine Visitor RCA Access Requirements - added general area dose rates of 0 to 5 mr/hr to cue and requirement to check Entering Radiation Area on form to standard.

9 JPM Determine HPCI Hi Level Trip - Rejected on level of difficulty; created new JPM to validate results (perform SRO review) of completed sT-23C, which has errors that will need to be identified for satisfactory

. performance.

Three JPMs for EAL Determinations associated with Simulator Scenarios -

added initiating cue and additional performance steps beyond EAL classification, but additional steps not identified as critical steps.

0 Changes as a result of final Ops Validation approved by NRC 5/3/05 (via phonecon):

9 Written Exam (RO and SRO):

RO # 3 - edit stem to remove first word "With", added a period and then "I&C is investigating" relative to the logic failure. Replaced "5%" with

7%" in correct answer (a) and distracter (b).

SRO # 22 - removed "of the 10300 and 10400 busses" from stem as window-dressing, put "immediately" in all caps, replaced (b) distracter with "Per AOP-11, Loss of RBCLC, align Emergency Service Water for Drywell Cooling", and added procedure titles to all four possible answers.

Also, replaced Explanation section for new distracter (b).

SRO # 23 - NRC rejected proposed change to re-order stem bullets.

RO # 25 - edited distracter (b) and correct answer (c) to re-order statements for readability (second half first and first half second in both cases); and removed word "also" from both.

SRO # 31 - revised first bullet of stem to replace "prior to taking manual control of feedwater" with "on the Narrow Range GEMAC Indicators."

SRO # 40 - revised stem conditions "RPV Pressure 600 psig, rising at 10 psig/min" to RPV Pressure 600 psig, lowering at 20 psig/min" and "Torus Water Temperature 180" F, Rising 1" F/min" to "Torus Water Temperature 180" F, Rising 0.5" F/min" to fix error in intent.

SRO # 51 - revised distracter (c) and correct answer (d) to remove specific timeframes "about 5/15 minutes" and replace with "for readings to stabilize."

SRO # 57 - NRC rejected proposed change to re-order stem.

SRO # 83 - NRC rejected proposed change to replace "returned to service" with "repaired" in correct answer (d)

RO # 89 - revised all four possible answers to replace "alarming" with "resulting in."

RO # 96 - added stem statement (previously existed in similar form) "The lowest NSW header pressure was 85 psig."

9 Operating Exam: Three EAL JPMs required editorial enhancements (additional information added for Evaluator to cue further candidate action subsequent to EAL Classification).

Retrieved from "https://kanterella.com/w/index.php?title=ML051930213&oldid=2592106"