ML062510413

Final Ginna Exam Aug. 2006 - Outlines (Folder 3)

ML062510413
Person / Time
Site:	Ginna
Issue date:	09/27/2006
From:	Ginna
To:	Fish T H Operations Branch I
Sykes, Marvin D.
References
50-244/06-301 50-244/06-301
Download: ML062510413 (23)

Text

ES-401 PWR Examination Outline Fo~ ES-401-2 Facilitv:

R.E, Ginna Printed: 04/19/2006 Tier 1. nergenc & .bnormal Plant volutions - 2. Plant Systems Date Of Exam: 07/17/2006 RO WA Category Points SRO-Only Points 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 a1 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 faality should be deleted and justified; operationally important, site-specific systems that are not included on the 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 ewlution 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 I 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 KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) hr 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 topices from Section 2 of the WAcatalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to WAS that are linked to 10 CFR 55.43. 1 PWR RO Examination Outline Facility:

R.E, Ginna mp. I Points1 Printed 04/19/2006 i, ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 /Group 1 Form ES-401-2 ' '"/APE # I Name I Safety Function K1 3.3 I 1 X EK1.05 - Decay power as a function of I ltime .~0007 Reactor Trip - Stabilization - iecovery I 1 100009 Small Break LOCA 13 EK 1 .O 1 - Natural circulation and cooling, including reflux boiling AA2.01 - Cause of RCP failure AA 1 .OS - VCT level AK2.02 - LPI or Decay Heat RemovaVRHR pumps AK3.03 - Guidance actions contained in EOP for Loss of CCW x 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

L 4 300022 Loss of Rx Coolant Makeup 12 1 3.4* 1 ~ 300025 Loss of RHR System 14 000026 Loss of Component Cooling Water I 8 ~~ 000027 Pressurizer Pressure Control System Malfimction I 3 000029 ATWS I 1 EA2.05 - System component valve I position indications I 000054 Loss of Main Feedwater 14 cycling upon total feedwater loss ~~~ 000055 Station Blackout I 6 X - X 2.4.31 - Knowledge of annunciators alarms and indications, and use of the response instructions.

2.4.6 - Knowledge symptom based EOP mitigation strategies.

000056 Loss of Off-site Power 16 X AK1.O1 - Battery charger equipment ll and instrumentation 000058 Loss of DC Power I 6 1 000062 Loss of Nuclear Svc Water 14 AA1.07 - Flow rates to the components , and systems that are serviced by the SWS; interactions among the components 000065 Loss of Instrument Air I 8 AK3.03 - Knowing effects on plant operation of isolating certain equiprneni from instrument air i EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 EA1.1- Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 1 PWR RO Examination Outline Facility:

R.E, Ginna K3 A1 A2 G a Printed: 04/19/2006 EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 3.6 "/APE # / Name / Safety Function I. ,{/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 WA Category Totals: K1 - 3 K2 X KA Topic 1 Imp. 2

-~ ~ PWR RO Examination Outline Printed: 04/19/2006 Facility:

R.E, Ginna Imp. 4.4 3.9 4.2 2.6 3 .O 2.6 3.1 3.8 3.3 Points 1 1 1 1 1 1 1 1 1 Form ES-401-2 ES - 401 ' "/APE # / Name / Safety Function Emergency and Abnormal K1 K2 K3 A1 JOOO 1 Continuous Rod Withdrawal

/ 1 000003 Dropped Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction

/ 2 000036 Fuel Handling Accident 18 X X 000060 Accidental Gaseous Radwaste Rel. 1 9 000067 Plant Fire On-site / 9 WE06 Inad. Core Cooling / 4 X X E09 Natural Circ. / 4 X Plant Evolutions - Tier 1 /Group 2 A2 G KATopic X AA2.05 - Uncontrolled rod withdrawal, from available indications X 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

AK3.02 - Actions contained in EOP for emergency boration AK2.02 - Sensors and detectors X 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation.

AK2.01 - ARM system, including

!he normal radiation-level indications and the operability status AA2.04 - The fire's extent of potential operational damage to plant equipment EA 1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EKI .3 - Annunciators and conditions X indicating signals, and remedial actions associated with the Natural Circulation Operations 1

007 Pressurizer RelieWQuench 008 Component Cooling Water ES - 401 Imp. ".ys/Evol#

/ Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic 3.0 004 Chemical and Volume Control X K4.13 - Interlock between 3.2* X K1.10 - RCS Reactor Coolant Pump letdown isolation valve and flow control valve system and limits on flow -ge exchanger X K6.3 1 - Seal injection 3.1 004 Chemical and Volume Control 005 Residual Heat Removal X K6.03 - RHR heat 2.5 005 Residual Heat Removal , X ,2.1.32 - Ability to explain , 3.4 I/ 008 Component Cooling Water Points 1 1 1 1 , 1 0 10 Pressurizer Pressure Control X 006 Emergency Core Cooling X 2 Reactor Protection Ill r/ II 0 12 Reactor Protection - 1 I I 0 13 Engineered Safety Features I I and apply all system limits and precautions.

K4.17 - Safety Injection valve interlocks 022 Containment Cooling 3.8 1 X Y ~ 026 Containment Spray K5.02 - Method of forming a steam bubble in the PZR A2.02 - High/low surge tank level A4.10 - Conditions that require the operation of two CCW coolers K2.02 - Controller for PZR 059 Main Feedwater spray valve K5.02 - Power density 3.1* (interlock) limit A1.05 - RCS T-ave 3.2* 1 , 2.5 T 1 1 A4.02 - Components for individual channels 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant ooeration. - 3.9 - 3.6 - 1 I IK3.04-RCS I 3.6 I 1 X I I A4.12 - Initiation of I 3.4 I 1 1 Form Plant Systems - Tier 2 / Group 1 ES - 401 ' qys/Evol#

/ Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. automatic feedwater isolation and water hammer indicators and controls X K5.05 - Feed line voiding 2.7 X A3.05 - Safety-related 3.5 X A2.01 - Grounds 2.5 3.1 06 1 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator x K1.02 - ED/G cooling water system 073 Process Radiation Monitoring X A 1 .O 1 - Radiation levels 3.2 076 Service Water X A3.02 - Emergency heat 3.7 078 Instrument Air X K2.01- Instrument air 2.7 103 Containment X K3.02 - Loss of containment 3.8 103 Containment X 2.1.14 - Knowledge of 2.5 loads compressor integrity under normal operations system status criteria which require the notification of plant personnel.

2 ES-401-2 Points 1 1 1 1 1 1 1 1 1 WACategory Totals: 2 2 3 3 3 2 2 3 2 3 3 Group Point Total: 28 Facility:

R.E, Ginna L4 X ES - 401 ' ?ys/Evol#

I Name G KATopic Imp. Points A3.04 - Radial imbalance 3.5 1 K1.04 - RPS 3.8 1 A1.O1 - Core exit 3.7 1 temperature A4.0 1 - Radiation levels 3.3 1 . ,dl Control Rod Drive K5.06 - Effect of power change on fuel cladding K3.0 1 - Main condenser 0 1 1 Pressurizer Level Control 0 17 In-core Temperature Monitor 034 Fuel Handling Equipment 04 1 Steam Dump/Turbine Bypass Control 2.5 1 2.5 1 k5Condenser Air Removal X 11 068 Liquid Radwaste 072 Area Radiation Monitoring 079 Station Air 3.4 3.4 l 2.9 2.6 I 1 086 Fire Protection 1 1 1 1 WA Category Totals: PWR RO Examination Outline Plant Systems - Tier 2 I Group 2 Printed: 0411 912006 Form ES-401-2 11 I I I K4.01 - Safety and environmental precautions for handling hot, acidic, and radioactive liquids 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical sDecifications. ~~~ ~ ~ A2.0 1 - Cross-connection with IAS K6.04 - Fire, smoke, and heat detectors Group Poin 1 Generic Knowledge and Abilities Outline (Tier

3) PWR RO Examination Outline Conduct of Operations

2.1.3 Knowledge

of shift turnover practices.

3 .O 2.1.28 Knowledge of the purpose and function of major 3.2 system components and controls.

Facility:

R.E, Ginna 1 1 Printed 04/19/2006 Form ES-401-3 2.2.22 2.2.27 Knowledge of limiting conditions for operations 3.4 1 Knowledge of the refueling process. 2.6 1 and safety limits. Radiation Control k 2.2.34 Emergency Procedures/Plan Knowledge of the process for determining the 2.8 1 internal and external effects on core reactivity.

2.4.4 Ability

to recognize abnormal indications for 4.0 system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

2.4.22 Knowledge of the bases for prioritizing safety 3.0 2.4.24 Knowledge of loss of cooling water procedures.

3.3 functions

during abnormaVemergency operations.

1 1 1 Generic Total: 10 1 ES-401, Rev. 9 Record of Rejected WAS Form ES-401-4 ' Tier I Group 112 2 I2 Randomly Selected WA 067 AA2.05 Reason for Rejection 011 K2.02 ~ Replaced 067 AA2.05 could not write appropriate written exam question from KA based on Ginna procedures. Selected replacement (AA2.04) from same category using poker chip method. Developed In-Plant JPM to evaluate 067 AA2.05. Replaced 01 1 K2.02 since 010 K2.02 already selected which gives 2 power supply questions on PRZR control systems. Randomly selected replacement (K1.04) using poker chip method from K1 category since no K1 had been selected in this TierJGroup.

ES-401 PWR Examination Outline Form ES-401-2 Facility:

R.E, Ginna Printed: 08/03/2006

1. 2. 3. 4. 5. 6. 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). 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. 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 the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

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.

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. 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

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics' topics must be relevant to the applicable evolution or system. importance ratings (IRs) 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 topices from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43. 1 Facility:

R.E, Ginna ES - 401 PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Recovery / 1 II 000022 Loss of Rx Coolant Makeup

/ 2 000027 Pressurizer Pressure Control System Malfunction I3 ll 000038 Steam Gen. Tube Rupture 13 ~ 000054 Loss of Main Feedwater I4 II 000057 Loss of Vital AC Inst. Bus / 6 WA Category Totals: 0 0 Printed: 08/03/2006 Form ES-401-2 G 1 KA Topic Points X 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

AA2.01 - Whether charging line leak exists 4.0 3.8 1 1 AA2.06 - Conditions requiring plant shutdown 1 X 2.4.6 - Knowledge symptom based EOP 4.0 I mitigation strategies.

1 AA2.05 - Status of MFW pumps, regulating and stop valves 3.7 - 4.0 1 - 1 3 Group Point Total: 6 1 PWR SRO Examination Outline Printed: 08/03/2006 Facility:

R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 [mp. 3.9 4.0 3.9 3.6 ' -'APE #I Name f Safety Function Points 1 1 1 1 do024 Emergency Boration / 1 K1 000059 Accidental Liquid RadWaste Rel.

/ 9 K2 00 WE1 0 Natural Circ.

/ 4 41 W/E16 High Containment Radiation 19 A2 X X 02 WA Category Totals: X 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments achieve required SDM related to system operations/status 21 Group Point Total:

4 1 Facility:

R.E, Ginna Imp. 4.3 3.7 3.3* 2.6* 3.1 ES - 401 ' 'ys/Evol # / Name Points 1 1 1 1 1 ~105 Residual Heat Removal G X X 06 1 Auxiliary/Emergency Feedw ater KA Topic 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

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

A2.05 - Methods for 062 AC Electrical Distribution 2 064 Emergency Diesel Generator Group Point Total:

5 076 Service Water WA Category Totals:

PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Printed: 08/03/2006 Form ES-401-2 energizing a dead bus A2.17 - Consequences of not shedding loads during nonoperability test A2.02 - Service water header pressure 1

PWR SRO Examination Outline Facility:

R.E, Ginna ~~ KA Topic which events related to system operations/status should be reported to outside agencies.

2.4.30 - Knowledge of Plant Systems - Tier 2 I Group 2 ES - 401 ' "ys1Evol # t Name K1 K2 K3 Imp. Points 3.6 1 -- 29 Containment Purge :j_r A2.03 - Mispositioned fuel element A2.04 - Failure to actuate the FPS when required, resulting in fire damage 034 Fuel Handling Equipment 4.0 1 3.9 1 Printed: 08l03l2006 Form ES-401-2 1

Generic Knowledge and Abilities Outline (Tier

3) PWR SRO Examination Outline ~~ ~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Facility:

R.E, Ginna --. Generic Category 4.4 1 KA _. ~~ Knowledge of the process for making changes in the facility as described in the safety analysis reDort. Conduct of Operations 2.7 2.1.7 L Equipment Control Printed: 08/03/2006 Form ES-401-3 2.2.5 KA Topic Imp. Points Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. 3.7 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

2.2.25 L 3.1 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.

3.2 Category

Total: Emergency ProceduresPlan Radiation Control

2.4.1 Knowledge

of EOP entry conditions and 4.6 1 2.4.46 Ability to verify that the alarms are consistent 3.6 1 Category Total: 2 immediate action steps. with the plant conditions.

2.3.4 Generic

Total: 7 1

-- ES-401, Rev. 9 Record of Rejected WAS Form ES-401-4 Tier I Randomly Group Selected K/A 212 I 034 A1.02 1/1 038 G2.4.41 Reason for Rejection Randomly selected 034 A2.03 using poker chip method due to inamromiate selection of an A1 KA on original outline Replaced with 03 8 G2.4.6 due to NRC concern with over sampling of Emergency Plan KAs in the origimal outline.

- Form ES-301-1 ES-301, Rev. 9 Administrative Topics Outline :acility:

R.E. Ginna Ixamination Level: RO [XI Administrative Topic (see Note]

onduct of Operations

>onduct of Operations fquipment Control 'iadiation Control Emergency Plan SRO 0 TY Pe Code* Date of Examination:

7/17/2006 Operating Test Number: 06-1 Describe activity to be performed Perform a Plant Calorimetric JR015.004 (2.1.7) 0-6.13 Channel Checks JR341.002 (2.1.3

1) Control of LCO's for Equipment Out of Service JR343.005 (2.2.23)

Complete Plant Status Report from EPIP 1-5 with the PPCS Out of Service JC119.001 (2.4.39) 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, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 I) (P)revious 2 exams (5 1; randomly selected)

I ES-301, Rev. 9 Administrative Topics Outline Form ES-3014 Facility: R.E. Ginna Examination Level:

RO 0 SRO Date of Examination:

7/17/2006 Operating Test Number:

06-1 Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code* N, S P, R D, R Describe activity to be performed Implement the Hazardous Spill Response Plan JS345.001 (2.1.26) ~ ~ ~~ Loss of Safety Function Determination JS343.006 (2.1.12) Verify Equipment Tagout Boundary JS119.001 (2.2.13) Approve Liquid Release Form (CH-RETS-LIQ-REL, Figure V)

JS069.001 (2.3.6) Event Classification JS34 1.02 1 (2.4.4 1) 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, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (5 1; randomly selected)

ES-301. Rev. 9 Control Room/ln-Plant Svstems Outline Form ES-301-2 Type Code*

Safety Function a. Rod Control I Realign a Missaligned Rod JROOl.013

b. Chemical and Volume Control / Burp the VCT for H2 Removal JR004.012 Oution 2 ~ ~~ c. ECCS / Nitrogen Makeup to the Accumulators JR006.002 N, s 1 N, A7 s 2 d. Reactor Coolant Pump System / Start a RCP per Attachment RCP e. Containment System

/ Manually close Isolation Valves on a CI f. Emergency Diesel Generators

/ Start and Load the "A' DG per PT- 12.1 JR 064.002 Option 2 Start JR003.001 Option 3 Failure JR103.007 Option2 MA, s, L 4 5 N, A, s, L M, '47 s 6 j. Steam Generator System

/ Perform Attachment Ruptured Steam Generator Part B JC035.006 D7 s D, p, A, s g. Reactor Protection System

/ Defeat a Failed Pressurizer Pressure

h. Containment Purge System / Startup CNMT Mini-Purge System Channel JROI 2.001 JR029.001 Option 2 k. Waste Gas Disposal System

/ Release the A GDT per S-4.2.5 JN071.002 7 8 19 N, R7 E i. Plant Fire System / Secure Ventilation Systems During a Fire JN086.002 8 Type Codes (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator (A)lternate path Criteria for RO I SRO-I / SRO-U 4-6 I 4-6 I 2-3 5915a154 21 121 I2 1 21 I21 12 1 2212212 1 5 3 I5 3 15 2 (randomly selected) 21 121121 ES-301, Rev. 9 Control Room/ln-Plant Systems Outline Form ES-301-2 Type Code* a. Rod Control / Realign a Missaligned Rod JROOl.012 N, s Facility: R.

E. Ginna Exam Level: RO 0 SRO-I SRO-U Safety Function 1 Date of Examination:

7/17/2006 Operating Test No.: 06-1 b. Containment System / Manually close Isolation Valves on a CI c. Emergency Diesel Generators

/ Start and Load the "A" DG per PT- d. Failure JR103.007 Option 2 12.1 JR 064.002 Option 2 N, A, S, L M, A, S, ESF e. h. in-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Plant Fire System / Secure Ventilation Systems During a Fire JN086.002

j. Steam Generator System

/ Perform Attachment Ruptured Steam Generator Part B JC035.006 4 k. @I I I All RO and SRO-I control room (and in-plant) systems must be different and sewe different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator I Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 12-3 591S81S4 21 I2ll21 21 121 I2 1 22/22/21 5 3 / 5 3 I5 2 (randomly selected) 21 121121 Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

R. E. Ginna Examiners:

T. Fish G. Johnson -- D. Silk Scenario No.: Operators:

Op-Test No.: 06-1 Initial Conditions:

3% Power during a Startup , MOL, Auto SI Failure, "A" D/G Fails to Auto Starj Turnover:

3% Power during a startup.

0-1.2 complete up to step 5.4.3.17. MFW Pump A is ready to start and MFW Pump A Attachment of 0-1.2 has been completed through step 8. RCS Boron is 1335 ppm.

No equipment is 00s. Start MFW Pump A. transistion to MFW and prepare to roll the turbine.

Event Malf. Event 'T BOP (C) R0,SRO SRO (TS) RCS-12B SRO(C) EDS-6 IALL (M) GEN-08 IBOP (C) Event Descrintion Start "A" MFW Pump, Transition to MFW Increase Power in preparation to roll turbine ~ ~~~ ~~ Spray Valve Control PCV-43 1 A fails causing the spray valve to open "A" MFRV Fails open (Manual Control available)

Bus 16 Normal Feed Trips (Bus Fault) RCP High Vibration

("B" RCP) Rx Manual Trip required.

300 gprn LOCA from the "R" RCP Seal Package SI Fails to Actuate Loss of Offsite Power after SI Reset. (manually restart SI equipment) 8 9 10 "A" Diesel Generator Auto Start Failure requiring Manual Start Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

R. E. Ginna Examiners:

T. Fish G. Johnson D. Silk Scenario No.:

2 Operators:

Op-Test No.: 06-1 Initial Conditions:

70% Power. MOL, RCS Boron 900 ppm, "B" MDAFW pump is 00s for motor work. "B" SW Pump 00s for mc:or replacement.

Turnover:

70% Power, MOL, RCS Boron 900 ppm, 11,000 ppm in BASTS. "B" MFW Pump retruned to service 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago following repairs. Holding power at 70 % for secondary chemistry. Control Rods are in Manual. "B" MDAFW pump is 00s for motor work. The AFW Svstem valves aye not held. The "B" SW Pump is 00s for motor replacement.

A52-4 submitted for both.

Event CND-08F SR0,BOP R0,SRO (C) SRO (TS) 3 I RCS-16 I 5 1 lSRO(7.S)

Event Description - Condensate Pump Trips, Standby Pump fails to Auto Start Plant power redution to 50% due to report of MFW Pump "B" problems Fuel Cladding Failure Letdown Line 30 gpm Leak (Leak isolation is a Critical Task) Steam Leak on PT-479 causing low failure 300 gpm SGTR in "B" S/G (Rtiptured - Faulted SIC) Reactor Fails to Auto Trip (Manual Trip Available)

Loss of AFW (MDAFW Pump "A" Fails to Auto Start, TDAFW Pump Trips on start. Manual start "A" MDAFW Pump available) c (Njormal, (Rjeactivity, (I)nstrument, (Cjomponent, (M)ajor Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Event No. Facility: R. E. Ginna Scenario No.:

3 - (SPARE) Examiners:

Operators:

Op-Test No.: 06-1 Malf. Event No. Type* Initial Conditions:

100% Power. MOL, RCS Boron 845 ppm, "B" SIP fails to Auto Start. "A" SIP 00s for motor work. "B" Charging Pump 00s for Belt Replacement "B" SW Pump 00s for motor work Turnover:

100% Power, MOL, RCS Boron 845 ppm, Xenon equilibrium, "A" SIP 00s for motor work. "B" Charging Pump 00s for Belt Replacement. "B" SW Pump 00s for motor work SIS-1A RCS- 19D RPS-7B RO(C) i-l Event Description Loop B Thot fails high. Rods Step Out, manual rod control. Defeat channel per ER-INST. 1 CCW Seal Return cooler leak (20 gpm) Main Generator Isophase Bus Duct coolers fail requiring a rapid load reduction to 70% power Rod Lift Coil fails causing the rod not to move when called for during power reduction "D" SW Pump trip requiring manual start of "C" SW Pump - Entry into SW T.S, "C" SW Pump fails to start. Enter AP-SW.2, Loss of SW. Inadvertant SI with 853B check valve failure resulting a LOCA Outside CNMT "B" SIP fails to Auto Start * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor