ML062510413

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Final Ginna Exam Aug. 2006 - Outlines (Folder 3)
ML062510413
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/27/2006
From:
Ginna
To: Todd Fish
Operations Branch I
Sykes, Marvin D.
References
50-244/06-301 50-244/06-301
Download: ML062510413 (23)
v • d • e


Text

ES-401 PWR Examination Outline F o ES-401-2

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Facilitv: R.E, Ginna Printed: 04/19/2006 Date Of Exam: 07/17/2006 RO WA Category Points SRO-Only Points Tier 1.

nergenc

.bnormal Plant volutions 2.

Plant Systems

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 Iand 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) h r 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.

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PWR RO Examination Outline Printed 04/19/2006 Facility: R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / G r o u p 1 Form ES-401-2

' '"/APE # I Name I Safety Function K1 mp. I Points1 I

.~0007Reactor Trip - Stabilization -

iecovery I 1 X

I EK1.05 - Decay power as a function of ltime 3.3 1 100009 Small Break LOCA 1 3 300022 Loss of Rx Coolant Makeup 12

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300025 Loss of RHR System 1 4 1

4 L

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 i ,

RemovaVRHR pumps 000026 Loss of Component Cooling Water I AK3.03 - Guidance actions contained in 8 EOP for Loss of CCW

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000027 Pressurizer Pressure Control System x 2.1.23 - Ability to perform specific Malfimction I 3 system and integrated plant procedures during all modes of plant operation.

000029 ATWS I 1 I EA2.05 - System component valve position indications 3.4* 1 000054 Loss of Main Feedwater 1 4

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000055 Station Blackout I 6 I feedwater loss cycling upon total X 2.4.31 - Knowledge of annunciators alarms and indications, and use of the response instructions.

000056 Loss of Off-site Power 1 6 X 2.4.6 - Knowledge symptom based EOP mitigation strategies.

000058 Loss of DC Power I 6 1

X l l AK1.O1 - Battery charger equipment and instrumentation 000062 Loss of Nuclear Svc Water 1 4 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

WE05 Inadequate Heat Transfer - Loss of EA2.2 - Adherence to appropriate Secondary Heat Sink I 4 procedures and operation within the limitations in the facility's license and amendments 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 a

Printed: 04/19/2006 Facility: R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 1 Form ES-401-2 I . /APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic 1 Imp.

,{/E12 - Steam Line Rupture - Excessive X EK2.2 - Facilitys heat removal systems, 3.6 Heat Transfer / 4 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 WA Category Totals: 3 2

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PWR RO Examination Outline Printed: 04/19/2006 Facility: R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / G r o u p 2 Form ES-401-2

' "/APE # / Name / Safety Function JOOO 1 Continuous Rod Withdrawal / 1 K1 K2 K3 A1 A2 X

G KATopic AA2.05 - Uncontrolled rod withdrawal, Imp.

4.4 Points 1

from available indications 000003 Dropped Control Rod / 1 X 2.1.23 - Ability to perform specific 3.9 1 system and integrated plant procedures during all modes of plant operation.

000024 Emergency Boration / 1 X AK3.02 - Actions contained in EOP for 4.2 1 emergency boration 000028 Pressurizer Level Malfunction / 2 X AK2.02 - Sensors and detectors 2.6 1 000036 Fuel Handling Accident 1 8 X 2.1.2 - Knowledge of operator 3 .O 1 responsibilities during all modes of plant operation.

000060 Accidental Gaseous Radwaste Rel. 1 X AK2.01 - ARM system, including !he 2.6 1 9 normal radiation-level indications and the operability status 000067 Plant Fire On-site / 9 X AA2.04 - The fire's extent of potential 3.1 1 operational damage to plant equipment WE06 Inad. Core Cooling / 4 X EA 1.1 - Components, and functions of 3.8 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features E09 Natural Circ. / 4 X EKI .3 - Annunciators and conditions 3.3 1 indicating signals, and remedial actions associated with the Natural Circulation Operations 1

ES - 401

.ys/Evol# / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points Reactor Coolant Pump X K1.10 - RCS 3.0 1 004 Chemical and Volume Control X K4.13 - Interlock between 3.2* 1 letdown isolation valve and flow control valve 004 Chemical and Volume Control X K6.3 1 - Seal injection 3.1 1 system and limits on flow

-ge 005 Residual Heat Removal X K6.03 - RHR heat 2.5 1 exchanger 005 Residual Heat Removal , X ,2.1.32 - Ability to explain , 3.4 , 1 and apply all system limits and precautions.

r/

006 Emergency Core Cooling X K4.17 - Safety Injection 3.8 1 valve interlocks 007 Pressurizer RelieWQuench K5.02 - Method of forming a steam bubble in the PZR 008 Component Cooling Water A2.02 - High/low surge tank level A4.10 - Conditions that I /

008 Component Cooling Water Y require the operation of two CCW coolers -

0 10 Pressurizer Pressure Control X K2.02 - Controller for PZR , 2.5 1 spray valve 2 Reactor Protection I l l K5.02 - Power density 3.1* 1 T

A4.02 - Components for 0 12 Reactor Protection I I I I individual channels 0 13 Engineered Safety Features I I X 1

2.1.23 - Ability to perform 3.9 specific system and integrated plant procedures during all modes of plant ooeration.

022 Containment Cooling

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026 Containment Spray 3.6 1 (interlock) limit A1.05 - RCS T-ave 3.2* 1 059 Main Feedwater I IK3.04-RCS I 3.6 I 1 X I IA4.12 - Initiation of I 3.4 I 1 1

Plant Systems - Tier 2 / Group 1 Form ES-401-2

'ES - 401 qys/Evol# / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic automatic feedwater Imp. Points isolation 06 1 Auxiliary/Emergency X K5.05 - Feed line voiding 2.7 1 Feedwater and water hammer 062 AC Electrical Distribution X A3.05 - Safety-related 3.5 1 indicators and controls 063 DC Electrical Distribution X A2.01 - Grounds 2.5 1 064 Emergency Diesel Generator x K1.02 - ED/G cooling water 3.1 1 system 073 Process Radiation Monitoring X A 1.O 1 - Radiation levels 3.2 1 076 Service Water X A3.02 - Emergency heat 3.7 1 loads 078 Instrument Air X K2.01- Instrument air 2.7 1 compressor 103 Containment X K3.02 - Loss of containment 3.8 1 integrity under normal operations 103 Containment X 2.1.14 - Knowledge of 2.5 1 system status criteria which require the notification of plant personnel.

WACategory Totals: 2 2 3 3 3 2 2 3 2 3 3 Group Point Total: 28 2

PWR RO Examination Outline Printed: 0411912006 Facility: R.E, Ginna Plant Systems - Tier 2 I Group 2

' ES - 401 Form ES-401-2 1 1 I I I

?ys/Evol# I Name L4 G KATopic Imp. Points

. ,dl Control Rod Drive A3.04 - Radial imbalance 3.5 1 0 11 Pressurizer Level Control K1.04 - RPS 3.8 1 0 17 In-core Temperature Monitor A1.O1 - Core exit 3.7 1 temperature 034 Fuel Handling Equipment X A4.0 1 - Radiation levels 3.3 1 04 1 Steam Dump/Turbine Bypass K5.06 - Effect of power 2.5 1 Control change on fuel cladding k 5 C o n d e n s e r Air Removal K3.0 1 - Main condenser 2.5 1 068 Liquid Radwaste K4.01 - Safety and 3.4 1 environmental precautions for handling hot, acidic, and radioactive liquids 072 Area Radiation Monitoring X 2.1.33 - Ability to recognize 3.4 1 indications for system operating parameters which are entry-level conditions

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for technical sDecifications.

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079 Station Air A2.0 1 - Cross-connection l 2.9 1 with IAS 1 086 Fire Protection K6.04 - Fire, smoke, and heat detectors I 2.6 1 WA Category Totals: 1 1 Group Poin 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed 04/19/2006 Facility: R.E, Ginna Form ES-401-3 Conduct of Operations 2.1.3 Knowledge of shift turnover practices. 3 .O 1 2.1.28 Knowledge of the purpose and function of major 3.2 1 system components and controls.

2.2.22 Knowledge of limiting conditions for operations 3.4 1 and safety limits.

2.2.27 Knowledge of the refueling process. 2.6 1 2.2.34 Knowledge of the process for determining the 2.8 1 internal and external effects on core reactivity.

k Radiation Control Emergency Procedures/Plan 2.4.4 Ability to recognize abnormal indications for 4.0 1 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 1 functions during abnormaVemergencyoperations.

2.4.24 Knowledge of loss of cooling water procedures. 3.3 1 Generic Total: 10 1

ES-401,Rev. 9 Record of Rejected WAS Form ES-401-4

' Tier I Randomly Reason for Rejection Group Selected WA

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112 067 AA2.05 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.

2 I2 011 K2.02 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. 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 +I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the 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 (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. U s e 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: 08/03/2006 Facility: R.E, Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 G 1 KA Topic Points X 2.1.33 - Ability to recognize indications 4.0 1 Recovery / 1 for system operating parameters which are entry-level conditions for technical specifications.

000022 Loss of Rx Coolant Makeup / 2 I I AA2.01 - Whether charging line leak exists 3.8 1 000027 Pressurizer Pressure Control System AA2.06 - Conditions requiring plant 1 Malfunction I 3 shutdown 000038 Steam Gen. Tube Rupture 1 3

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l l X I 2.4.6 - Knowledge symptom based EOP mitigation strategies.

4.0 1 000054 Loss of Main Feedwater I 4 000057 Loss of Vital AC Inst. Bus / 6 I I AA2.05 - Status of MFW pumps, regulating and stop valves 3.7 4.0 1

1 W A Category Totals: 0 0 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

' -'APE # I Name f Safety Function K1 K2 41 A2 [mp.

3.9 Points 1

d o 0 2 4 Emergency Boration / 1 X achieve required SDM 000059 Accidental Liquid RadWaste Rel. / 9 X 2.1.33 - Ability to recognize indications 4.0 1 for system operating parameters which are entry-level conditions for technical specifications.

W E 1 0 Natural Circ. / 4 X EA2.2 - Adherence to appropriate 3.9 1 procedures and operation within the limitations in the facility's license and amendments W/E16 High Containment Radiation 1 9 3.6 1 related to system operations/status WA Category Totals: 0 0 0 2 21 Group Point Total: 4 1

PWR SRO Examination Outline Printed: 08/03/2006 Facility: R.E, Ginna Plant Systems - Tier 2 / Group 1 Form ES-401-2 ES - 401

' 'ys/Evol # / Name

~105Residual Heat Removal G KA Topic X 2.4.4 - Ability to recognize Imp. Points 4.3 1 abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

06 1 Auxiliary/Emergency X 2.2.25 - Knowledge of bases 3.7 1 Feedw ater in technical specifications for limiting conditions for operations and safety limits.

062 AC Electrical Distribution A2.05 - Methods for 3.3* 1 energizing a dead bus 064 Emergency Diesel Generator A2.17 - Consequences of 2.6* 1 not shedding loads during nonoperability test 076 Service Water A2.02 - Service water 3.1 1 header pressure WA Category Totals: 2 Group Point Total: 5 1

PWR SRO Examination Outline Printed: 08l03l2006 Facility: R.E, Ginna Plant Systems - Tier 2 I Group 2 Form ES-401-2 ES - 401 ~~

ys1Evol # t Name K1 K2 K3 KA Topic Imp. Points

-- 29 Containment Purge 2.4.30 - Knowledge of 3.6 1 which events related to

j _ system operations/status should be reported to outside agencies.

A2.03 - Mispositioned fuel 4.0 r

1 034 Fuel Handling Equipment element A2.04 - Failure to actuate 3.9 1 the FPS when required, resulting in fire damage 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 08/03/2006 Facility: R.E, Ginna Form ES-401-3

--. Generic Category KA KA Topic Imp. Points

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L Conduct of Operations 2.1.7 Ability to evaluate plant performance and make 4.4 1 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

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Equipment Control 2.2.5 Knowledge of the process for making changes in 2.7 the facility as described in the safety analysis L

reDort.

2.2.25 Knowledge of bases in technical specifications 3.7 for limiting conditions for operations and safety limits.

Category Total:

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.

Emergency ProceduresPlan 2.4.1 Knowledge of EOP entry conditions and 4.6 1 immediate action steps.

2.4.46 Ability to verify that the alarms are consistent 3.6 1 with the plant conditions.

Category Total: 2 Generic Total: 7 1

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

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

acility: R.E. Ginna Date of Examination: 7/17/2006 Ixamination Level: RO [XI SRO 0 Operating Test Number: 06-1 Administrative Topic TY Pe Describe activity to be performed (see Note] Code*

Perform a Plant Calorimetric

onduct of Operations JR015.004 (2.1.7) 0-6.13 Channel Checks

>onduct of Operations JR341.002 (2.1.3 1)

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

'iadiation Control Complete Plant Status Report from EPIP 1-5 with the Emergency Plan 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 Date of Examination: 7/17/2006 Examination Level: RO 0 SRO Operating Test Number: 06-1 Administrative Topic TY Pe Describe activity to be performed (see Note) Code*

Implement the Hazardous Spill Response Plan Conduct of Operations N,S JS345.001 (2.1.26)

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Loss of Safety Function Determination Conduct of Operations P, R JS343.006 (2.1.12)

Verify Equipment Tagout Boundary Equipment Control D, R JS119.001 (2.2.13)

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

Event Classification Emergency Plan JS34 1.021 (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 N,s 1
b. Chemical and Volume Control / Burp the VCT for H2 Removal JR004.012 Oution 2 N,A7 s 2

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c. ECCS / Nitrogen Makeup to the Accumulators JR006.002
d. Reactor Coolant Pump System / Start a RCP per Attachment RCP M A , s, L 4 Start JR003.001 Option 3
e. Containment System / Manually close Isolation Valves on a CI Failure JR103.007 Option2 N,A, s, L 5
f. Emergency Diesel Generators / Start and Load the ADG per PT-12.1 JR 064.002 Option 2 M, 4 7 s 6
g. Reactor Protection System / Defeat a Failed Pressurizer Pressure Channel JROI 2.001 D7 s 7
h. Containment Purge System / Startup CNMT Mini-Purge System JR029.001 Option 2 D, p, A, s 8
i. Plant Fire System / Secure Ventilation Systems During a Fire JN086.002 N, R7 E 8
j. Steam Generator System / Perform Attachment Ruptured Steam Generator Part B JC035.006
k. Waste Gas Disposal System / Release the A GDT per S-4.2.5 JN071.002 1 9 Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank 5915a154 (E)mergency or abnormal in-plant 2 1 1 2 1 I2 1 (L)ow-PowerI Shutdown 2 1 I 2 1 12 1 (N)ew or (M)odified from bank including 1(A) 2212212 1 (P)revious 2 exams 5 3 I5 3 1 5 2 (randomly selected)

(R)CA 2 1 121121 (S)imulator

ES-301, Rev. 9 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: R. E.Ginna Date of Examination: 7/17/2006 Exam Level: RO 0 SRO-I SRO-U Operating Test No.: 06-1 Type Code* Safety Function

a. Rod Control / Realign a Missaligned Rod JROOl.012 N, s 1
b. Containment System / Manually close Isolation Valves on a CI Failure JR103.007 Option 2 N, A, S , L
c. Emergency Diesel Generators / Start and Load the "A"DG per PT-M, A, S , ESF 12.1 JR 064.002 Option 2 d.

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 4 Generator Part B JC035.006 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 I Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 12-3 (C)ontrol room (D)irect from bank 591S81S4 (E)mergency or abnormal in-plant 21 I 2 l l 2 1 (L)ow-Power I Shutdown 21 1 2 1 I 2 1 (N)ew or (M)odified from bank including 1(A) 22/22/21 (P)revious 2 exams 5 3 / 5 3 I5 2 (randomly selected)

(R)CA 21 1 2 1 1 2 1 (S)imulator

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: R. E. Ginna Scenario No.: Op-Test No.: 06-1 Examiners: T. Fish Operators:

G. Johnson

-- Silk D.

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

'T Malf. Event Event Descrintion Start "A" MFW Pump, Transition to MFW Increase Power in preparation to roll turbine

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Spray Valve Control PCV-43 1 A fails causing the spray valve to open BOP (C)

"A" MFRV Fails open (Manual Control available)

R0,SRO Bus 16 Normal Feed Trips (Bus Fault)

SRO (TS)

RCP High Vibration ("B" RCP) Rx Manual Trip required.

RCS-12B 300 gprn LOCA from the "R" RCP Seal Package 8 SI Fails to Actuate SRO(C) 9 EDS-6 IALL (M) Loss of Offsite Power after SI Reset. (manually restart SI equipment) 10 GEN-08 IBOP (C) "A" Diesel Generator Auto Start Failure requiring Manual Start

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: R. E. Ginna Scenario No.: 2 Op-Test No.: 06-1 Examiners: T. Fish Operators:

G. Johnson D. Silk 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 Event Description Condensate Pump Trips, Standby Pump fails to Auto Start CND-08F SR0,BOP Plant power redution to 50% due to report of MFW Pump "B" problems 3 I RCS-16 IR0,SRO (C)

SRO (TS)

Fuel Cladding Failure Letdown Line 30 gpm Leak (Leak isolation is a Critical Task) 5 1 lSRO(7.S) 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 Facility: R. E. Ginna Scenario No.: 3 - (SPARE) Op-Test No.: 06-1 Examiners: Operators:

Initial Conditions: 100% Power. MOL, RCS Boron 845 ppm, "B"SIP fails to Auto Start. "A" SIP 0 0 s 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 0 0 s for motor work. "B" Charging Pump 00s for Belt Replacement. "B" SW Pump 00s for motor work Event Malf. Event Event No. No. Type* 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.

SIS-1A Inadvertant SI with 853B check valve failure resulting a LOCA Outside RCS- 19D CNMT i RPS-7B

- RO(C) l "B"SIP fails to Auto Start

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