ML062700254

Draft Ginna Exam Aug. 2006 - Outlines (Folder 2)

ML062700254
Person / Time
Site:	Ginna
Issue date:	08/03/2006
From:	Ginna
To:	Todd Fish Operations Branch I
Sykes, Marvin D.
References
ES-401, ES-401-2
Download: ML062700254 (23)

Text

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

R.E, Ginna Printed: 04/19/2006 Note:

1.

2.

3.

4.

5.

6.

7.*

Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (he., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA categoly 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 I and 2 from the shaded systems and WA categories.

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 (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 ES401 -3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1

PWR RO Examination Outline Printed: 0411 912006 Facility:

R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 EK1.05 - Decay power as a function of

~

1. /Name / Safety Function Points 1

Imp.

3.3 Ab007 Reactor Trip - Stabilization -

Recovery I I 3.O 1

000009 Small Break LOCA / 3 0000 1 1 Large Break LOCA I 3 4.1 3.O 3.4 3.2*

EK1.01 - Natural circulation and cooling, including reflux boiling AA2.0 1 - Cause of RCP failure AAl.08 - VCT level AK2.02 - LPI or Decay Heat RemovaVRHR pumps 000015/000017 RCP Malhctions I 4 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water I 8

4.0 3.9 AK3.03 - Guidance actions contained in EOP for Loss of CCW 000027 Pressurizer Pressure Control System Malfunction 1 3 000029 ATWS I 1 1 -

1 3.4*

4.6 EA2.05 - System component valve position indications AK3.05 - HPIPORV cycling upon total feedwater loss 000054 Loss of Main Feedwater 14 000055 Station Blackout I 6 3.3 3.1 X 2.4.3 1 - Knowledge of annunciators alarms and indications, and use of the response instructions.

000056 Loss of Off-site Power I 6 X 2.4.6 - Knowledge symptom based EOP I mitigation strategies.

000058 Loss of DC Power I 6 2.8 2.9 AK1.O1 - Battery charger equipment and instrumentation AA 1.07 - Flow rates to the components and systems that are serviced by the SWS; interactions among the components 000062 Loss of Nuclear Svc Water 14 000065 Loss of Instrument Air I 8 AK3.03 - Knowing effects on plant operation of isolating certain equipment from instrument air 2.9 3.7 WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments WE1 1 Loss of Emergency Coolant Recirc. I 4

EA 1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.9 1

1 I

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

R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2

/APE !# / Name / Safety Function I K1 IK2 I K3 IAllA2 G I KATopic

[Imp. I Points [

EK2.2 - Facilitys 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 3.6 1

3 1 Group Point Total:

18 1

2

PWR RO Examination Outline Facility:

R.E, Ginna E09 Natural Circ. 14 WACategory Totals:

Printed: 04/19/2006 X

EKl.3 - Annunciators and conditions indicating signals, and remedial actions associated with the Natural Circulation Operations 1

2 1 1 2 2

Group Poin ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 K2 K3 A1 TF

/APE # / Name / Safety Function I K1 Points 1

Imp.

4.4 KA Topic AA2.05 - Uncontrolled rod withdrawal, from available indications I

~ b 0 0 1 Continuous Rod Withdrawal / 1 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

1 3.9 4.2 000003 Dropped Control Rod I 1 000024 Emergency Boration I 1 AK3.02 - Actions contained in EOP for emergency boration 1

X X

X 000028 Pressurizer Level Malfunction 12 AK2.02 - Sensors and detectors 2.6 1

000036 Fuel Handling Accident I 8 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation.

3.0 1

X X

000060 Accidental Gaseous Radwaste Rel. I 9

2.6 1

AK2.01 - ARM system, including the normal radiation-level indications and the operability status AA2.04 - The fires extent of potential operational damage to plant equipment 000067 Plant Fire On-site I 9 3.1 1

WE06 Inad. Core Cooling 14

~~

EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.8 1

3.3 1

Total:

9 -

1

PWR RO Examination Outline Facility:

R.E, Ginna Printed: 04/19/2006 Form ES-401-2 KA Topic Imp.

K1.10 - RCS 3.O K4.13 - Interlock between 3.2*

letdown isolation valve and flow control valve K6.3 1 - Seal injection system and limits on flow range I

3.1 K6.03 - RHR heat exchanger 2.1.32 - Ability to explain and apply all system limits and vrecautions.

2.5 3.4 K4.17 - Safety Injection I 3.8 valve interlocks K5.02 - Method of forming a steam bubble in the PZR -

3.1 A2.02 - High/low surge tank level A4.10 - Conditions that require the operation of two CCW coolers 3.2 3.1*

K2.02 - Controller for PZR I 2.5 spray valve K5.02 - Power density A402 - Components for individual channels 3.1*

3.3 K3.01 - Fuel 4.4 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

K4.02 - Correlation of fan speed and flowpath changes with containment vressure 3.9 3.1*

A2.07 - Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding), or sump level below cutoff (interlock) limit A1.05 - RCS T-ave K3.04 - RCS A4.12 - Initiation of 3.6 3.2*

3.6 3.4

'oints 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1

2 PWR RO Examination Outline Facility:

R.E, Ginna ES - 401

' qys/Evol# / Name K1 K2 06 1 AuxiliaryEmergency Feedwater I

I

~

~~

062 AC Electrical Distribution 073 Process Radiation Monitoring I I

076 Service Water 078 Instrument Air X

103 Containment 103 Containment WA Category Totals:

2 2

Plant !

s ystems - Tier K5 K6 A1 X

X

!/G A2 roup 1 A3 A4 G X

Printed: 0411 912006 KA Topic automatic feedwater isolation K5.05 - Feed line voiding and water hammer A3.05 - Safety-related indicators and controls A2.0 1 - Grounds K1.02 - ED/G cooling wate system A1.O1 - Radiation levels

?orm ES-401-2 Imp. Points 2.7 1

3.5 1

2.5 1

3.1 1

3.2 1

3 3

3 2

2 3

2 3

3 Group Point Total:

28 2

PWR RO Examination Outline Facility:

R.E, Ginna KA Topic A3.04 - Radial imbalance K1.04 - IU'S A1.O1 - Core exit temperature A4.0 1 - Radiation levels K5.06 - Effect of power change on fuel cladding K3.O 1 - Main condenser K4.01 - Safety and environmental precautions for handling hot, acidic, and radioactive liquids indications for system operating parameters which are entry-level conditions 1 for technical specifications.

A2.01 - Cross-connection 1 with IAS K6.04 - Fire, smoke, and heat detectors 2.1.33 - Ability to recognize Printed: 0411 912006 Form ES-401-2 Imp. Points 3.5 1

3.8 1

3.7 1

3.3 1

2.5 1

2.5 1

3.4 1

3.4 1

2.9 1

2.6 1

1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Conduct of Operations 2.1.3 Knowledge of shift turnover practices.

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

Printed: 04/19/2006 3.0 1

3.2 1

Facility:

R.E, Ginna Form ES-401-3 Equipment Control Category Total:

2 2.2.22 Knowledge of limiting conditions for operations 3.4 1

2.2.27 Knowledge of the refueling process.

2.6 1

2.2.34 Knowledge of the process for determining the 2.8 1

Category Total:

3 and safety limits.

internal and external effects on core reactivity.

Radiation Control

\\

/

Category Total:

2 Emergency Procedures/Plan 2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating mocedures.

I Categorv Total:

3 1

Generic Total:

10 1

ES-401, Rev. 9 Record of Rejected WAS Form ESQOI-4 Tier I Group 1 / 2 2 /2 Randomly Selected K/A 067 AA2.05 01 1 K2.02 Reason for Rejection 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 Tier/Group.

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

R.E, Ginna Printed: 0411 912006 Date Of Exam:

0711 712006 I

RO wA Category Points I

SRO-Only Points Note:

1.

2.

3.

4.

5.

6.

7.*

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 +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.

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.

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 (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

PWR SRO Examination Outline Printed: 0411 912006 Facility:

R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 K3 I,,,#

I Name I Safety Function I K1 IK2 A1 0

0 d0007 Reactor Trip - Stabilization -

Recovery I 1

~

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

000022 Loss of Rx Coolant Makeup 12

~~

000027 Pressurizer Pressure Control System Malfunction 1 3 000038 Steam Gen. Tube Rupture I 3 000054 Loss of Main Feedwater 14 000057 Loss of Vital AC Inst. Bus 16 WACategory Totals: I 0 I 0 X

AA2.0 1 - Whether charging line leak I

(exists xlplAA2.06

- Conditions requiring plant I

Ishutdown X

X 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

AA2.05 - Status of MFW pumps, regulating and stop valves X 2.4.6 - Knowledge symptom based EOP I mitigation strategies.

I I

3 3

Group Point Total:

6 1

PWR SRO Examination Outline Facility:

R.E, Ginna WE16 High Containment Radiation / 9 Printed: 0411 912006 X

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 WA Category Totals:

G P E

1. / Name / Safety Function I K1 IK2 I K3IAllA2 I G 0

0 0

0 2

2 A6024 Emergency Boration / 1 000059 Accidental Liquid RadWaste Rel. / 9 W E 10 Natural Circ. I 4 I

I I

KA Topic I Imp. I Points AA2.05 - Amount of boron to add to achieve required SDM 1

~~

~

~~

~~

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

4.0 1

EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 2.4.30 - Knowledge of which events related to system operations/status should be reported to outside agencies.

3.9 3.6 1

1

~

Group Point Total:

4 1

PWR SRO Examination Outline Printed: 04/19/2006 ES - 401

' ".ys/Evol# / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp.

L d 5 Residual Heat Removal X 2.4.4 - Ability to recognize 4.3 abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

06 1 AuxiliarylEmergency X 2.2.25 - Knowledge of bases 3.7 Feedwater in technical specifications for limiting conditions for operations and safety limits.

energizing a dead bus not shedding loads during nonoperability test header pressure 062 AC Electrical Distribution X

A2.05 - Methods for 3.3*

064 Emergency Diesel Generator X

A2.17 - Consequences of 2.6*

076 Service Water X

A2.02 - Service water 3.1 Points 1

1 1

1 1

1 WACategoryTotals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

5

ES - 401

' ".ys/Evol# /Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic

-9 Containment Purge X 2.4.30 - Knowledge of which events related to system operations/status should be reported to outside agencies.

element the FPS when required, resulting in fire damage 034 Fuel Handling Equipment X

A2.03 - Mispositioned fuel 086 Fire Protection X

A2.04 - Failure to actuate 1

Imp. Points 3.6 1

4.0 1

3.9 1

WACategory Totals:

0 0

0 0

0 0

0 2

0 0

1 Group Point Total:

3

Generic Knowledge and Abilities Outline (Tier 3)

P W R SRO Examination Outline Conduct of Operations 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Facilitv:

R.E, Ginna i/ Generic Category 4.4 1

Printed: 04/19/2006 Equipment Control Form ES-401-3 Category Total:

1 2.2.5 Knowledge of the process for making changes in 2.7 1

the facility as described in the safety analysis report.

2.2.25 Knowledge of bases in technical specifications 3.7 1

for limiting conditions for operations and safety limits.

Category Total:

2 Radiation Control 2.3.4 Knowledge of radiation exposure limits and 3.1 contamination control, including permissible levels in excess of those authorized.

2.3.8 Knowledge of the process for performing a 3.2 planned gaseous radioactive release.

1 1

Emergency Proceduresmlan 2.4.1 2.4.46 Knowledge of EOP entry conditions and 4.6 1

Ability to verify that the alarms are consistent 3.6 1

immediate action steps.

with the plant conditions.

Generic Total:

7 1

ES-401, Rev. 9 Record of Rejected WAS Form ES-401-4 Tier 1 Randomly Reason for Rejection Group Selected WA 2 1 2 034 Al.02 Randomly selected 034 A2.03 using poker chip method due to inappropriate selection of an A1 KA on original outline

Administrative Topics Outline FOIIII ES-301-1 ES-301, Rev. 9 Facility: R.E. Ginna Examination Level: RO Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control

~

Emergency Plan SRO 0 TY Pe Code*

D, C 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 (2.1.31)

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 1)

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

ES-301, Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2

+-e Type Code*

a. Rod Control / Realign a Missaligned Rod JROOI.012 N, s Safety Function 1

b. Chemical and Volume Control / Burp the VCT for H2 Removal J R004.0 1 2

2. ECCS / Nitrogen Makeup to the Accumulators JR006.002 i Reactor Coolant Pump System / Start a RCP per Attachment RCP Start J R003.001 NY A, s 2

DY s 3

WAY SY L 4

NJ A, SY L MY A, s

1. Containment System / Manually close Isolation Valves on a CI Failure JR103.007

f.

Emergency Diesel Generators / Start and Load the A DG per PT-12.1 JR 064.002

i.

Plant Fire System / Secure Ventilation Systems During a Fire J N086.002 5

6

1.

Steam Generator System / Perform Attachment Ruptured Steam Generator Part B JC035.006 DY s DJ PJ A, s

3. Reactor Protection System / Defeat a Failed Pressurizer Pressure

h. Containment Purge System / Startup CNMT Mini-Purge System Channel JR012.001 J R029.001 4

7 8

k. Waste Gas Disposal System / Release the A GDT per S-4.2.5 JN071.002

• Type Codes 1

9 Criteria for RO I SRO-I I SRO-U (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 4-6 14-6 12-3 1911a114 2 I l 2 1 1 2 I 2 I l 2 I l 2 l 2 2 1 2 2 1 2 I S 3 IS 3 I I 2 (randomly selected) 2 1 I2 I 12 I

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: R.E. Ginna Examination Level: RO Ad minis trative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan SRO Date of Examination: 7/17/2006 Operating Test Number: 06-1 Type Code*

N, S Describe activity to be performed

~

Implement the Hazardous Spill Response Plan JS345.001 (2.1.26)

Loss of Safety Function Determination JS341.001 (2.1.12)

Verify Equipment Tagout Boundary JS119.001 (2.2.13)

~

~

Approve Liquid Release Form (CH-RETS-LIQ-EL, Figure V) JS069.001 (2.3.6)

Event Classification JS341.021 (2.4.41)

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;.s 4 for SROs & RO retakes)

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

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

ES-301, Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2

.d

• Type Codes Facility: R. E. Ginna Exam Level: RO 0 SRO-I 0 SRO-U Criteria for RO I SRO-I I SRO-U Date of Examination: 7/17/2006 Operating Test No.: 06-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

a. Rod Control / Realign a Missaligned Rod JROOI.012

b. Containment System / Manually close Isolation Valves on a CI Failure JRI 03.007

c. Emergency Diesel Generators / Start and Load the A DG per PT-

d.

12.1 JR 064.002

e.

f.

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

Type Code*

Safety Function I M, A, S, ESF

i. Plant Fire System / Secure Ventilation Systems During a Fire JN086.002 8

j.

Steam Generator System / Perform Attachment Ruptured Steam Generator Part B JC035.006

k.

All RO and SRO-I control room (and in-plant) systems must be different and serve 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.

(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 4-6 14-6 I 2-3 5 9 I S 8 1 5 4 24 121 I 2 1 21 I 2 4 I 2 4 2 2 / 2 2 / 2 4 5 3 I S 3 I S 2 (randomly selected) 2 1 I 2 1 I 2 1 I

Form ES-D-1 Appendix D, Rev. 9 Scenario Outline 9

10 Facility: R. E. Ginna Scenario No.: 1 Op-Test No.: 06-1 Examiners:

T. Fish Operators:

G. Johnson D. Silk EDS-6 ALL(M)

GEN-08 BOP (C)

Initial Conditions: 3% Power during a Startup. MOL, Auto SI Failure, "A" D/G Fails to Auto Start 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 comdeted 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 I

Malf.

I Event BOP (C)

SRO (C)

FDW-7A 4

SRO (TS)

Event Description Start "A" MFW Pump, Transition to MFW Increase Power in preparation to roll turbine

~

Spray Valve Control PCV-43 1A 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 gpm LOCA fkom the "B" RCP Seal Package SI Fails to Actuate Loss of Offsite Power after SI Reset. (manually restart SI equipment)

"A" Diesel Generator Auto Start Failure requiring Manual Start (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

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

CIND-4C END-08F Facility: R. E. Ginna Examiners:

T. Fish G. Johnson D. Silk Type*

Description Condensate Pump Trips, Standby Pump fails to Auto Start BOP(C)

SRO(C)

RO (R)

\\ ---

RCS-16 Scenario No.: 2 Operators:

0 RoysRo (')

Fuel Cladding Failure SRO (TS)

Op-Test No.: 06-1 cvc-2 Initial Conditions: 70% Power, MOL, RCS Boron 900 ppm, "B" MDAFW pump is 00s for motor work. "B" SW Pumu 00s for motor replacement.

Turnover:

70% Power. MOL. RCS Boron 900 upm. 11,000 ppm in BASTS. "B" MFW Pumu 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 System valves are not held. The 'IB" SW Pump is 00s for motor replacement. A52-4 submitted for both.

Ro SRO(C)

Letdown Line 30 gpm Leak (Leak isolation is a Critical Task) 1 Event i SGN-3D STM-2B SGN-4B t

SRO (TS)

ALL (M)

Steam Leak on PT-479 causing low failure 300 gpm SGTR in "B'l S/G (Ruptured - Faulted S/G)

Malf.

I Event I

Event RPS-7K FDW 30 BOP (C)

SRO (C)

Loss of AFW (MDAFW Pump "A" Fails to Auto Start, TDAFW Pump Trips on start. Manual start "A" MDAFW Pump available)

ISR0,BOP I Plant power redution to 50% due to report of MFW Pump "B" problems RPs-IRo 5A/B SRO (C)

I Reactor Fails to Auto Trip (Manual Trip Available) 8

Amendix D. Rev. 9 Scenario Outline Form ES-D-1 Facility: R. E. Ginna Examiners: T. Fish G. Johnson D. Silk Scenario No.: 3 - (SPARE)

Operators:

Op-Test No.: 06-1 Initial Conditions: 100% Power, MOL, RCS Boron 845 pum, "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 tm-n Xenon equilibrium, "A" SIP 00s for motor work. "B" Charging P u m ~

00s for Belt Redacement. 'IB" SW Pumu 00s for motor work Event No.

1 2

3 4

5 6

7 Malf.

Event r t

~~~

Event DescriDtion 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