ML041060112

Draft Outlines

ML041060112
Person / Time
Site:	Ginna
Issue date:	04/02/2004
From:	Maciuska F Rochester Gas & Electric Corp
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-244/04-301 50-244/04-301
Download: ML041060112 (22)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: R E Ginna Printed: 02/17/2004 Date Of Exam: 04/05/2004 RO WA Category Point! I SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.

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 *l 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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system unless they relate to plant-specific priorities.

4. Systemslevolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category /tier.

6.* 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. 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 columns labeled "K" and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3,enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

1

P W R RO Examination Outline Printed: 0211712004 Facility: R E Ginna ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 / Group 1

- - Form ES-401-2

'/APE# / Name / Safety Function K2 A2 G 000007 Reactor Trip - Stabilization - -

EK2.02 Breakers, relays and Recovery I 1 disconnects 000008 Pressurizer Vapor Space Accident I 3

000011 Large Break LOCA I 3 AK1.02 - Change in leak rate with change in pressure I IEAl. 13 - Safety injection components I 4.1 *

-3.1 1

0000 151000017 RCP Malfunctions I 4 000022 Loss of Rx Coolant Makeup 1'2 AA2.10 When to secure RCPs on loss of cooling or seal injection AA2.01- Whether charging line leak I 3.7 3.2 1

1 exists 000025 Loss of RHR System 1 4 AA1.09 - LPI pump switches, ammeter, 3.2 1 discharge pressure gauge, flow meter, and indicators 000026 Loss of Component Cooling Water I 8

000027 Pressurizer Pressure Control System AA 1.O1 - CCW temperature indications AK3.01 - Isolation of PZR spray I 3.1 3.5*

1 1

Malfunction 13 following loss of PZR heaters 000029 ATWS I 1 -

2.4.50 Ability to verify system alarm 3.3 1 setpoints and operate controls identified in the alarm response manual.

-~_________ - -

~

30038 Steam Gen. Tube Rupture 13 EK3.05 Normal operating precautions 4.0 1 to preclude or minimize SGTR i-000054 Loss of Main Feedwater 1 4 -

2.4.6 Knowledge symptom based EOP 3.1 1 mitigation strategies.

000056 Loss of Off-site Power I 6 -

AK3.O1 Order and time to initiation of 3.5 1 power for the load sequencer 000057 Loss of Vital AC Inst. Bus I 6 -

AK3.01 Actions contained in EOP for 4.1 1 loss of vital ac electrical instrument bus 000058 Loss of DC Power 1 6 AAl.01 - Cross-tie of the affected dc 3.4* 1 bus with the alternate supply 000065 Loss of Instrument Air / 8 -

2.4.3 1 Knowledge of annunciators 3.3 1 alarms and indications, and use of the response instructions.

WE05 Inadequate Heat Transfer - Loss of EK2.2 - Facility's heat removal systems, 3.9 1 Secondary Heat Sink 1 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 W E 11 Loss of Emergency Coolant Recirc. I 2.1.23 - Ability to perform specific 3.9 1 4 system and integrated plant procedures during all modes of plant operation.

T -

1

P W R RO Examination Outline Printed 02/17/2004 Facility: R E Ginna ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 / Group 1 Form ES-401-2

'/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KATopic Imp. Points k../

WE12 Steam Line Rupture Excessive X EA2.2 - Adherence to appropriate 3.4 1 Heat Transfer / 4 procedures and operation within the limitations in the facility's license and amendments WACategoryTotals: 1 2 4 4 3 4 Group Point Total: 18

~ ~ ~

c 2

PWR RO Examination Outline Printed: 02/17/2004 Facility: R E Ginna ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1I Group 2 Form ES-401-2

/APE # I Name I Safety Function K1 K2 K3 U 1 A 2 ( G I KATopic I~ m p . I Points I 000003 Dropped Control Rod / 1 X AK2.05 - Control rod drive power supplies and logic circuits 000028 Pressurizer Level Malfunction / 2 X AK2.02 - Sensors and detectors X 2.4.4 - Ability to recognize abnormal

~ ~~~ ~~ ~~

000032 Loss of Source Range NI / 7 indications for system operating parameters which are entry-level conditions .for emergency and abnormal operating procedures.

i 000037 Steam Generator Tube Leak / 3 AK3.05 Actions contained in 1 procedures for radiation monitoring, ~ 3*7 RCS water inventory balance, S/G tube failure, and plant shutdown 000068 Control Room Evac. / 8 AK2.02 - Reactor trip system 3.7 1 WE02 SI Termination/ 3 -

EA1.1 Components, and functions of 4.0 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 41

-WE03 LOCA Cooldown Depress. / 4 X 2.1.32 - Ability to explain and apply all 3.4 1 system limits and precautions.

1 UE06 had. Core Cooling / 4 EA2.2 - Adherence to appropriate III procedures and operation within the 1 W E 15 Containment Flooding / 5

~~

X limitations in the facility's license and amendments

' EK1.1- Components, capacity, and function of emergency systems WACategoryTotals: 1 3 1 11 1 1 2 1 Group Poin Total:

1

PWR RO Examination Outline Printed: 0211712004 Facility: R E Ginna ES 401 Plant Systems Tier 2 / Group 1 Form ES-401-2 I I I 1 I I I I I I I I I I 3ys/Evol##I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points 003 Reactor Coolant Pump X -

K4.07 Minimizing RCS 3.2 1 leakage (mechanical seals) 004 Chemical and Volume Control X -

K5.27 Reason for nitrogen 2.6 1 purge of CVCS 005 Residual Heat Removal X -

K6.03 RHR heat 2.5 1 exchanger 006 Emergency Core Cooling X -

K1.07 MFW System 2.9* 1 006 Emergency Core Cooling X K2.01- ECCS pumps 3.6 1 007 Pressurizer RelieflQuench X -

A1.O1 Maintaining quench 2.9 1 Tank t ank water level within limits 008 Component Cooling Water X -

A2.02 Highbow surge tank 3.2 1 level 0 10 Pressurizer Pressure Control X -

A2.02 Spray valve failures 3.9 1 012 Reactor Protection X -

K6.01 Bistables and 2.8 1 bistable test equipment 012 Reactor Protection X

~ _ _ _ _

K2.0 1 RPS channels, 3.3 1 components, and interconnections 0 13 Engineered Safety Features X -

A1.05 Main steam pressure 3.4 1 Actuation 913 Engineered Safety Features X -

A4.01 ESFAS-initiated 4.5 1 ictuation equipment which fails to actuate 022 Containment Cooling -

X 2.4.6 Knowledge symptom 3.1 1 based EOP mitigation strategies.

026 Containment Spray X A3.01 - Pump starts and 4.3 1 correct MOV positioning 039 Main and Reheat Steam X K 1.02 - Atmospheric relief 3.3 1 dump valves 056 Condensate X A2.04 - Loss of condensate 2.6 1 Pumps 059 Main Feedwater X A3.03 - Feedwater pump 2.5 1 suction flow pressure 059 Main Feedwater X -

A4.08 Feed regulating 3.0* 1 valve controller 06 1 AuxiliaryEmergency X K4.01 - Water sources and 4.1 1 Feedwater priority of use 062 AC Electrical Distribution X -

K3.03 DC system 3.7 1 063 DC Electrical Distribution X -

A3.O1 Meters, 2.7 1 annunciators, dials, recorders, and indicating lights 064 Emergency Diesel Generator X K6.07 - Air receivers 2.7 1 64 Emergency Diesel Generator X -

A2.06 Operating unloaded, 2.9 1 1

PWR RO Examination Outline Printed: 02/17/2004 Facility: R E Ginna ES - 401 -

Plant Systems Tier 2 / Group 1 Form ES-401-2 I I I Sys/Evol##f Name K1 K2 A2 A3 A4 KA Topic Imp. Points lightly loaded, and highly loaded time limit -

073 Process Radiation Monitoring I I A1.O1 -Radiation levels I 3.2 1 076 Service Water K4.01 - Conditions initiating 2.5* 1 automatic closure of closed cooling water auxiliary building header supply and I return valves -

076 Service Water K3.01 - Closed cooling 3.4* 1 water I 2.4.4 - Ability to recognize 1 4.0 1 abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating mocedures. -

K3.O 1 - Loss of containment 3.3*

II 103 Containment 1 integrity under shutdown conditions WA Category Totals: 2 2 4 3 2 Group Point Total: 28 2

P W R RO Examination Outline Printed: 02/17/2004 Facility: R E Ginna ES 401- -

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

j.ys/Evol# / Name K1 K2 K5 K6 A1 KA Topic Imp.

-.- ~~

002 Reactor Coolant -

K3.02 Fuel 4.2 0 11 Pressurizer Level Control X K6.04 - Oneration of PZR 3.1 level controllers 014 Rod Position Indication -

K4.06 Individual and 3.4 1 group misalignment -

~

015 Nuclear Instrumentation X -

K2.01 NIS channels, 3.3 1 components, and interconnections 0 17 In-core Temperature Monitor X K 1.O1 - Plant computer 3.2* 1 028 Hydrogen Recombiner and -

A2.03 The hydrogen air 3.4 1 Purge Control concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment 029 Containment Purge X -

A 1.03 Containment 3.O* 1 pressure, temperature, and humidity -

045 Main Turbine Generator -

A3.04 T/G trip 3.4

-1 071 Waste Gas Disposal X K5.04 - Relationship of 2.5 1 hydrogedoxygen concentrations to flammability -

7 4 7 9 Station Air -

A4.01 Cross-tie valves 2.7 1 r

with IAS WA Category Totals: 1 1 1 1 1 Group Point Total: 10 c

1

Generic Knowledge and Abilities Outline (Tier 3)

P W R RO Examination Outline Printed: 02/17/2004 Facility: R E Ginna Form ES-401-3 u

Generic Category -

KA Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all 3.0 1 modes of plant operation.

2.1.31 Ability to locate control room switches, controls 4.2 1 and indications and to determine that they are correctly reflecting the desired plant lineup.

2.1.33 Ability to recognize indications for system 3.4 1 operating parameters which are entry-level conditions for technical specifications.

Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

2.2.33 Knowledge of control rod programming.

I I

I I Cateaorv Total: 2 r

I Radiation Control I I

2.3.2 Knowledge of facility ALARA program. 2.5 1 1I t

I 2.3.11 Ability to control radiation releases.

Categorv Total:

2.7 2

1

-L 1

Emergency ProceduresE'lan 2.4.16 Knowledge of EOP implementation hierarchy and 3.0 1 I coordination with other support procedures. I I I 2.4.3 1 Knowledge of annunciators alarms and indications. and use of the remonse instructions. I 3.3 I 2.4.39 Knowledge of the RO's responsibilities in 3.3 1 emergency plan implementation.

-~ ~_______ ____ ~

Generic Total: 10 1

ES-401 PWR Examination Outline Form ES-401-2 RO WA Category Point! SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.

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 ilfrom 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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system unless they relate to plant-specific priorities.

4. Systemslevolutionswithin each group are identified on the associated outline.

5. The shaded areas are not applicable to the category /tier.

6." 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. 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 columns labeled "K" and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

1

PWR SRO Examination Outline Printed: 02/17/2004 Facility: R E Ginna ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1/ Group 1 Form ES-401-2

/APE # / Name / Safety Function K1K2 K3AlA2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X AA2.16 - RCS in-core thermocouple 4.1 1 3 indicators; use of plant computer for interpretation 000011 Large Break LOCA / 3 X 2.4.4- Ability to recognize abnormal 4.3 1 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

000015/000017 RCP Malfunctions / 4 X 2.4.30 - Knowledge of which events 3.6 1 related to system operationslstatus b should be reported to outside agencies.

AA2.07 - Pump cavitation 3.7 1 2.4.6- Knowledge symptom based EOP 4.0 1 mitigation strategies.

2.4.4 - Ability to recognize abnormal 4.3 1 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

EM.1 - Facility conditions and 4.4 1 selection of appropriate procedures during abnormal and emergency operations 1

PWR SRO Examination Outline Printed: 0211712004 Facility: R E Ginna ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1/ Group 2 Form ES-401-2 VAPE # 1 Name / Safety Function K1 K2 K3 AI A2 G KA Topic Imp. Points 000032 Loss of Source Range NI 1 7 X 2.1.32 - Ability to explain and apply all 3.8 1 system limits and precautions.

000067 Plant Fire On-site I 9 X AA2.15 - Requirements for establishing 3.9 1 a fire watch 000069 Loss of CTh4T Integrity I 5 X ~ ~ 21 -. ~0o s of s containment i n t e g r i t y l 4 . 3 1 1

~

WE07 Inad. Core Cooling 14 X 2.4.30 - Knowledge of which events 3.6 1 related to system operationslstatus should be reported to outside agencies.

WE15 Containment Flooding I 5 X EA2.1 - Facility conditions and 3.2 1 selection of appropriate procedures during abnormal and emergency operations WA Category Totals: 0 0 0 0

- 3 2 1

P W R SRO Examination Outline Printed: 02/17/2004 Facility: R E Ginna ES - 401 -

Plant Systems Tier 2 / Group 1 Form ES-401-2 I I I I I I 3ys/Evol# / Name K1 K2 K3 K4 K5 K6 IAl IA21A3 IA4 ( G IKATopic ImD. PoinO i I I , 1 - 1 I 022 Containment cooling I I I I I X I2.2.25 - Knowledge of bases I 3.7 I 1 in technical specifications for limiting conditions for operations and safety limits.

026 Containment Spray X A2.03 - Failure of ESF 4.4 1 039 Main and Reheat Steam -

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

063 DC Electrical Distribution X -

A2.01 Grounds 3.2* 1 WACategoryTotals: 0 0 0 0 0 0 0 2 0 0 2 Group Point Total: 4 1

PWR SRO Examination Outline Printed: 02/17/2004 Facility: R E Ginna I

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 02/17/2004 Facility: R E Ginna Form ES-401-3 Generic CatePorv -

KA KA ToDic ImD. Points Conduct of Operations I2.1.13 2.1.32 Knowledge of facility requirements for controlling vital / controlled access.

Ability to explain and apply all system limits and 2.9 3.8 1

1 precautions.

2.2.17 Knowledge of the process for managing 3.5 1 maintenance activities during power operations.

Radiation Control 2.3.6 Knowledge of the requirements for reviewing and 3.1 1 approving release permits.

2.3.8 Knowledge of the process for performing a 3.2 1 planned gaseous radioactive release.

L Category Total: 2 I Emergency Proceduresmlan 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormavemergency operations.

4.0 1 1- 2.4.46 Ability to verify that the alarms are consistent 3.6 1 with the plant conditions.

Generic Total: 7 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: R. E. Ginna Station Date of Examination: 4/5/04 Examination Level (circle one): RO Operating Test Number: 04-1 I

Administrative Topic Describe activity to be performed Conduct of Operations Calculate Shutdown Margin for an Operation Reactor with an Untrippable Rod JROOl.008 KA 2.1.7 Importance 3.7 r

CFR 41.10 Conduct of Operations Calculate QPTR JROI 5.001 KA 2.1.32 Importance 3.4 CFR41.10 Equipment Control PPCS Computer Checks JR083.001 KA 2.2.12 Importance 3.0 CFR 41.10 Radiation Control Emergency Plan Monitor Critical Safety Function Status Trees JR352.001 KA 2.4.21 Importance 3.7 CFR 41.10 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: R. E. Ginna Station Date of Examination: 4/5/04 Examination Level (circle one): SRO Operating Test Number: 04-1

~~

Administrative Topic Describe activity to be performed (see Note)

Conduct of Operations Fitness for Duty/Shift Staffing Requirements JS343.003 KA 2.1.5 Importance 3.4 CFR 43.2 Conduct of Operations Loss of Safety Function Determination JS341.001 KA 2.1.12 Importance 4.0 CFR 43.2/43.5

~~ ~

Equipment Control Review and Approve a Fuel Handling Deviation Report JS034.001 KA 2.2.26 Importance 3.7 CFR 43.7 Radiation Control Review and Approve a Waste Gas Holdup Tank Release JS071.001 KA 2.3.8 Importance 3.2 CFR 43.4 Emergency Plan Event Classification JS340.016 KA 2.4.41 Importance 4.0 CFR 43.5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

ES-301 Control Room/ln-Plant Systems Form ES-301-2 Outline Facility: R. E. Ginna Station Date of Examination: 4/5/04 Exam Level (circle one): RO Operating Test No.: 04-1 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title

a. 004 Chemical and Volume Control System I NSL Code*

Type

_ _ _ _ ~

I Function Safety 1

Borate RCS for SDM JR012.009

~

b. 035 Steam Generator System NASL 4 Establish RCS Cooling per AP-RHR. 1 JR005.008

c. 103 Containment System NSL 5 Initiate CNMT Closure JR005.007

d. 010 Pressurizer Pressure Control System DASL 3 Depressurize the RCS Using Nitrogen JROlO.003

e. 062 AC Electrical Distribution System DS 6 Transfer 4160V Auxiliary Loads JR062.005

f. 015 Nuclear Instrumentation System DS 7 Remove N-41 from Service JR015.002

~

g. 006 Emergency Core Cooling System MAS 2 Makeup to the "B" Accumulator from RWST JR006.001

h. 029 Containment Purge System DAS 8 Start Containment Mini-Purge JR029.001

i. 061 Auxiliary Feedwater System DA 4 Reset TDAFW Tripmhrottle Valve JC061.005

i. 103 Containment System MLR** 5 Isolate CNMT Closure Valves JCI 03.007

k. 063 DC Electrical Distribution System DL** 6 Align TSC Battery to 1B Main Fuse Cabinet JC063.001 I I Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA **Actions During Emergency Conditions

ES-301 Control Room/ln-Plant Systems Form ES-301-2 Outline Facility: R. E. Ginna Station Date of Examination: 4/5/04 Exam Level (circle one): SRO(U) Operating Test No.: 04-1 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title I Type Code*

Safety Function

a. 004 Chemical and Volume Control System NSL 1 Borate RCS for SDM JR012.008

b. 010 Pressurizer Pressure Control System Depressurize the RCS using N, JROlO.003 I DASL 3

c. 006 Emergency Core Cooling System MAS** 2 Makeup to the B Accumulator from the RWST JR006.001 d.

e.

f.

h.

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

i. 103 Containment System Isolate CNMT Closure Valves JC103.007 I MLR 5

j. 063 DC Electrical Distribution System DL 6 Align TSC Battery to 1B Main Fuse Cabinet JC063.001 k.

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol

-oom, (S)imulator, (L)ow-Power, (R)CA **ESF System

Appendix D Scenario Outline Form ES-D-1 L'

Facility: R. E, Ginna Station Scenario No.: #1 Op-Test No.: 04-1 Examiners: Operators:

Initial Conditions: MOL, 0-1.2 complete UD to startina the first MFW pump. TDAFW DumD has failed.

Turnover: Plant Startup is in procress. 0-1.2 complete up to step 5.4.3.18. Continue startup and place MFW in service.

I Event Malf. No. Event Event Type* Description 1 NA BOP (N) Start MFW Pump SRO (N) -~ ~ ~~

2 PZR03B RO (1) Przr Level Fails Low (Tech Spec)

SRO (I) 3 STM04A BOP (I) S/G ARV fails open. Manual control available.

SRO (I) 4 RCS02A RO (C) Small Leak (Ramps to 25 gpm) develops on CRDM SRO (C) housing (Tech Spec) 5 ROD13C MRPl Coil Stack fails from Leakage (Tech Spec)

G I1 ~ ~~ ~~~

6 ROD05 All (M) Rod Housing Fails Ejecting an RCCA G11 7 SIS02A RO (C) SI Sequencer Failure (A train)

RPS07B SRO(C) B SI Pump Fails to Auto Start 8 RPSO7K BOP (C) No AFW Pumps Auto Start SRO(C)

, (R)eact ty, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Station Scenario No.: #2 Op-Test No.: 04-1 Examiners: Operators:

Initial Conditions: 100% MOL Xenon Ea. (IC-19) Pull StoD and Hold D CNMT Recirc Fan.

Turnover: 100% MOL Xenon Ea.. C, - 778 mm. D CNMT Recirc Fan 00s for Breaker Work (see A-52.41, exDected back in 2-3hours.

Event Event No. Description 1 Turbine First Stage Pressure Transmitter Fails Low 2 Hotwell Level Channel LT-2001 Fails High causing full Hotwell rejection. (Will result in loss of MNV if no action c- taken) 3 EDSOIA All (C) Loss of Offsite Power Circuit 751 (Tech Specs) 4 SGNO4B BOP (N) SG Tube Leak B SG 10 gpm (requires taking plant off RO (R) line) (Tech Specs)

SRO (N) 5 PZROSB RO(C) Przr Relief Valve PCV-431C Fails Open 50% (Tech SRO (C) Specs) 6 SGN04B All (M) SGTR (500gpm) B S/G 7 STM05B BOP (C) B MSlV fails to close SRO (C)

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

Appendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Station Scenario No.: #3 Op-Test No.: 04-1 Examiners: Operators:

Initial Conditions: 100% Power Xe Ea. Auto Rod Control is 00s due to problems in the Tava inDut. I&C is investiaatina. C Condensate Booster Pump is 00s.

Turnover: 100% Power EOL Conditions. C, - 7 wm. Auto Rod Control is 00s due to an internal Tava Droblem. I&C is investiaatina.

Event Malf. No. Event Event Type* Description 1 CLGIO RO (C> Running CCW Pump Trips. Standby pump fails to CLG02B Autostart. (Tech Specs) 2 FDW07A BOP (C) SG AFRV fails in Auto. Manual control is required.

3 CVCI8A RO (I) ACharging Pump Speed Controller failure.

4 CNDOI B BOP (N) B Condensate Booster Pump Trips requiring a down SRO(N) power.

RO (R) 5 PZR02A NA PT-429 Fails Low (sets up for inadvertent SI on station blackout) (Tech Specs) 6 EDSO6 All (C) Station Blackout 7 GEN08 BOP (C) Diesel Generators fail to Auto Start.

8 RCS19D All (M) Inadvertent SI. LOCA Outside CNMT (into RHR from CV-853B)

(R)eact ty, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Station Scenario No.: #4 op-Test No.: 04-1 Examiners: Operators:

Initial Conditions: 72% Power BOL C, 1535 mm. Xenon Increasing. D CNMT Recirc Turnover: The Dlant is at -72% Power following a load decrease to 50% for condenser tube cleanina. Increase Dower to 100% at lO%/hour Der 0-5.2 ster, 5.2.12 CNMT Recirc Fan D is out of service for breaker maintenance (see A-52.4).

Event Malf. No. Event Event No. Type* Description 1 SGNOID NA SG Level Channel LT-463 Fails High. (Tech Spec) 2 RODIA RO (C) When rod motion is called for rods begin stepping and SRO (C) will not stop until placed in manual.

3 RCSIOB NA RCS Flow Channel FT-412 Fails Low. (Tech Spec) 4 GEN03 BOP (C) Main Generator Voltage Regulator Fails requiring manual SRO (C) control.

5 CLG03 RO (C) Tube Leak in the Letdown Non-Regen Hx cause Letdown SRO (C) Leakage into the CCW System.

6 I EDS02C I All (C)

I Fault on Station Service Transformer 15 causes loss of non-vital bus 15 and Instrument Bus D 7 FDW02B RO (R) B MFW Pump Trips requiring power to be reduced until BOP (N) Steam Flow< Feedwater Flow SRO (N) 8 STMOW All (M) Steam Line break downstream of MSIV, MSlVs will not B close.

STM03 9 RPS07U BOP (C) Main Feedwater Isolation to AS/G fails.

FDW17A (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor