ML021610225

Draft - Outlines (Facility Ltr Dtd 02/21/02)

ML021610225
Person / Time
Site:	Oyster Creek
Issue date:	05/31/2002
From:	Hackenberg J AmerGen Energy Co
To:	Conte R NRC/RGN-I/DRS/OSB
References
2130-02-20065, 50-219/02301, NUREG-1021 2002-301
Download: ML021610225 (20)

Text

AmerGen,,

An Exelon/British Energy Company AmerCen Eneigy Company, LLC Oyster Creek US Route 9 South PO Box 388 Foiked River, NJ o8731-0388 NUREG 1021 February 21, 2002 2130-02-20065 U. S. NRC Region 1, Administrator 475 Allendale Road King of Prussia PA 19406

Subject:

Submittal of Integrated Initial License Training NRC Examination Outlines Oyster Creek Generating Station Docket No. 50-219 In accordance with NUREG 1021, Revision 8, "Operating Licensing Examination Standards for Power Reactors", Oyster Creek Generating Station is submitting the integrated initial license training NRC examination outlines for review and approval. This is in support of the NRC initial license examination scheduled for the week of May 13, 2002.

In accordance with NUREG 1021, Revision 8, Section ES-20 1, we request that these materials be withheld from public disclosure until after the examinations are complete.

If you should have any questions concerning this letter or the examination outlines, please contact Mr. Greg Young at (609) 971-4196.

Respectfully, Robin Brown Facility Representative/Manager Operations Support Oyster Creek Nuclear Generating Station

Enclosures:

(Delivered only to Paul Bissett, Chief Examiner, NRC Region 1)

ES-201-2, Examination Outline Quality Checklist ES-201-3, Examination Security Agreements ES-301-1, Administrative Topics Outline ES-301-2, Control Room Systems and Facility Walk-Through Test Outline ES-40 1-1, BWR SRO Examination Outlines

BWR SRO Examination Outline Facility:

Oyster Creek Exam Date: 05/13/2002 ES-401 I-K/A Category Points Tier Group KI K2 K3 K4 K5 K6 Al

1.

1 4

4 5

Emergency 2

3 3

3 Abnormal Plant Tier Evolutions Totals 7

7 8

2.

Plant Systems 1

3 2

2 1

2 2

4 2

6 2

A2 A3 A4 4

4 8

2 2

I G

5 2

7 4

Point Total 26 17 43 23 2

2 1

1 1

1 1

1 1

1 1

2 13 3

0 0

0 1

0 4

Tier Totals 5

3 3

3 3

4 4

3 3

2 7

40 Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge And Abilities 5

5 3

4 17 Note:

1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.

2. Actual point totals must match those specified in the table

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

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

1 Printed: 02/13/2002 Form ES-401-1 Exam Level:

SRO

BWR SRO( _amination Outline Printed:

02/13/{.,L Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-1 E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295003 Partial or Complete Loss of A.C. Power / 6 X 2.2.25 - Knowledge of bases in technical specifications 3.7 1

for limiting conditions for operations and safety limits.

295003 Partial or Complete Loss of A.C. Power / 6 X

AK3.05 - Reactor SCRAM 3.7 1

295006 SCRAM /

X

_ AA2.01 -Reactor power 4.6*

1 295006 SCRAM / 1 X

AK2.04 - Turbine trip logic: Plant-Specific 3.7 1

295007 High Reactor Pressure / 3 X

AKI.04 - Turbine load 2.8 1

295007 High Reactor Pressure / 3 X

AK3.06 - Reactor/turbine pressure regulating system 3.8 1

operation 295009 Low Reactor Water Level / 2 X

AKI.05 - Natural circulation 3.4 1

295009 Low Reactor Water Level / 2 X

AA1.02 -Reactor water level control 4.0 1

295010 High Drywell Pressure / 5 X

AA2.06 - Drywell temperature 3.6 1

295010 High Drywell Pressure/ 5 X

AK3.04 -Leak investigation 3.8 1

295014 Inadvertent Reactivity Addition /

X AK1.06 - Abnormal reactivity additions.

3.9 1

295015 Incomplete SCRAM / 1 X 2.1.33 - Ability to recognize indications for system 4.0 1

operating parameters which are entry-level conditions for technical specifications.

295017 High Off-Site Release Rate I 9 X

AA2.05 - "Meteorological data 3.8 1

295017 High Off-Site Release Rate / 9 X

AK2.03 - Off-gas system 3.5 1

1 Oyster Creek Facility:

ES - 401

BWR SRO& amination Outline Printed:

02/13/L Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 1 E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295023 Refueling Accidents / 8 X 2.1.32 - Ability to explain and apply system limits and 3.8 1

precautions.

295024 High Drywell Pressure / 5 X

EK2.11 - Drywell spray (RHR) logic: Mark-I&II 4.2*

1 295024 High Drywell Pressure / 5 X

EK3.07 - Drywell venting 4.0 1

295030 Low Suppression Pool Water Level / 5 X

EALO. - ECCS systems (NPSH considerations):

3.8 1

Plant-Specific 295030 Low Suppression Pool Water Level / 5 X

EA2.04 - Drywell/ suppression chamber differential 3.7 1

1 pressure: Mark-I&II 295031 Reactor Low Water Level / 2 X

EK2.09 - Recirculation system: Plant-Specific 3.4 1

295031 Reactor Low Water Level / 2 X 2.1.30 - Ability to locate and operate components, 3.4 1

including local controls.

295037 SCRAM Condition Present and Reactor Power X

EA1.07 - RMCS: Plant-Specific 4.0 1

Above APRM Downscale or Unknown / 1 295038 High Off-Site Release Rate / 9 X

EK3.02 - System isolations 4.2 1

295038 High Off-Site Release Rate / 9 X

EA1.06 - Plant ventilation 3.6 1

500000 High Containment Hydrogen Concentration / 5 X 2.1.12 - Ability to apply technical specifications for a 4.0 1

system.

500000 High Containment Hydrogen Concentration / 5 X

EK1.01 - Containment integrity 3.9 1

K/A Category Totals:

4 4

5 4

4 5

Group Point Total:

Oyster Creek Facility:

ES - 401 26 2

Farm FR-4fll-1

BWR SRO *.amination Outline Printed:

02/13/L1,2 Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 2 E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295001 Partial or Complete Loss of Forced Core Flow X

AK3.04 - Reactor SCRAM 3.6 1

Circulation / 1 295004 Partial or Complete Loss of D.C. Power / 6 X

AA2.03 - Battery voltage 2.9 1

295005 Main Turbine Generator Trip / 3 X

AK3.05 - Extraction steam/moisture separator 2.6 1

isolations 295008 High Reactor Water Level / 2 X

AA2.02 - Steam flow/feedflow mismatch 3.4 1

295018 Partial or Complete Loss of Component Cooling X

AK3.06 - Increasing cooling water flow to heat 3.3 1

Water / 8 exchangers 295019 Partial or Complete Loss of Instrument Air / 8 X 2.4.48 - Ability to interpret control room indications to 3.8 1

verify the status and operation of system, and understand how operator action s and directives affect plant and system conditions.

295019 Partial or Complete Loss of Instrument Air / 8 X

AA1.02 - Instrument air system valves: Plant-Specific 3.1 1

295021 Loss of Shutdown Cooling / 4 X

AA2.07 - Reactor recirculation flow 3.1 1

295021 Loss of Shutdown Cooling / 4 X

AKI.04 - Natural circulation 3.7 1

295022 Loss of CRD Pumps / 1 X

AK1.02 - Reactivity control 3.7 1

295022 Loss of CRD Pumps / 1 X

AK2.07 - Reactor pressure (SCRAM assist):

3.6 1

Plant-Specific 295034 Secondary Containment Ventilation High Radiation / X EK1.02 - tRadiation releases 4.4*

1 9

1

(

Oyster Creek Facility:

ES - 401 Form 1L*-401-1

BWR SRO(.amination Outline Printed:

02/13/{ -

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

17 2

(

Oyster Creek Facility:

ES - 401 E/APE #

E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.

Points 295035 Secondary Containment High Differential Pressure /

X EK2.02 - SBGT/FRVS 3.8 1

5 295036 Secondary Containment High Sump/Area Water X

EA2.01 - Operability of components within the affected 3.2 1

Level / 5 area 295036 Secondary Containment High Sump/Area Water X 2.2.25 - Knowledge of bases in technical specifications 3.7 1

Level / 5 for limiting conditions for operations and safety limits.

600000 Plant Fire On Site / 8 X

AK2.04 - Breakers, relays, and disconnects 2.6 1

600000 Plant Fire On Site / 8 X

AA1.08 -Fire fighting equipment used on each class of 2.9 1

fire I

K/A Category Totals:

3 3

3 2

4 2

(

BWR SRO EL.,ination Outline Printed: 02/1f J2 Plant Systems - Tier 2 / Group 1 Sys/Ev #

System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 202002 Recirculation Flow Control System /

X Al.04 - Reactor water level 2.9 1

1 202002 Recirculation Flow Control System /

X A3.02 - Lights and alarms 3.4 1

1 207000 Isolation (Emergency) Condenser / 4 X 2.1.33 - Ability to recognize indications for 4.0 1

system operating parameters which are entry-level conditions for technical specifications.

211000 Standby Liquid Control System / I X

A2.04 - Inadequate system flow 3.4*

1 212000 Reactor Protection System / 7 X

K4. 10 - Individual rod SCRAM testing 3.6 1

212000 Reactor Protection System / 7 X

K1.04 - A.C. electrical distribution 3.6 1

215004 Source Range Monitor (SRM) System X 2.1.32 - Ability to explain and apply system 3.8 1

/ 7 limits and precautions.

215004 Source Range Monitor (SRM) System X

K5.03 - Changing detector position 2.8 1

/7 215005 Average Power Range Monitor/Local X

K2.02 - APRM channels 2.8 1

Power Range Monitor System / 7 215005 Average Power Range Monitor/Local X

A2.06 - Recirculation flow channels upscale 3.5 1

Power Range Monitor System / 7 1

Facility:

ES - 401 Oyster Creek Form ES-401-1

BWR SRO EL..hination Outline Printed:

02/1

__,02 Facility:

Oyster Creek Plant Systems - Tier 2 / Group 1 Form ES-401-1 Sys/Ev#

System/Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.

Points 216000 Nuclear Boiler Instrumentation / 7 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.

218000 Automatic Depressurization System /

X K6.07 - Primary containment instrumentation 3.5 1

3 218000 Automatic Depressurization System /

X A1.02 - ADS valve acoustical monitor noise:

4.0 1

3 Plant-Specific 223002 Primary Containment Isolation X 2.4.4 - Ability to recognize abnormal 4.3 1

System/Nuclear Steam Supply indications for system operating parameters Shut-Off/5 which are entry-level conditions for emergency and abnormal operating procedures.

223002 Primary Containment Isolation X

K3.22 - Containment drainage system 2.6 1

System/Nuclear Steam Supply Shut-Off / 5 226001 RHRJLPCI: Containment Spray X

K1.01 - Suppression pool 3.6 1

System Mode / 5 226001 RHR/LPCI: Containment Spray X

K2.02 - Pumps 2.9*

1 System Mode / 5 239002 Relief/Safety Valves / 3 X

A4.02 - Tail pipe temperatures 3.7 1

241000 Reactor/Turbine Pressure Regulating X

K5.05 - Turbine inlet pressure vs. turbine load 2.9 1

System / 3 1

259002 Reactor Water Level Control System /

X K1.03 - Reactor water level 3.9 1

2 2

ES - 401

BWR SRO E iAnation Outline Facility:

Oyster Creek ES - 401 Plant Systems - Tier 2 / Group 1 Sys/Ev#

System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.

Points 262001 A.C. Electrical Distribution / 6 X

A3.02 - Automatic bus transfer 3.3 1

264000 Emergency Generators (Diesel/Jet) / 6 X

K3.03 - Major loads powered from electrical 4.2*

1 1____1_1_1_1_1_1___1_1_buses fed by the emergency generator(s) 264000 Emergency Generators (Diesel/Jet) / 6 X

K6.03 - Lube oil pumps 3.7 1

K/A Category Totals:

3 2

2 1

2 2

2 2

2 1

4 Group Point Total:

23 3

!i Printed:

02/1d J2 Form ES-401-1

(

BWR SRO Ek._aination Outline Printed:

02/1(, d02 Plant Systems - Tier 2 / Groun 2 Farm FSR-4O1-1 Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.

Points 201001 Control Rod Drive Hydraulic System X

A4.05 - Cooling water header pressure control 2.8 1

1 valve 201006 Rod Worth Minimizer System X

A2.07 - RWM hardware/software failure:

2.8 1

(RWM) (Plant Specific) /?7 P-Spec(Not-BWR6) 202001 Recirculation System / 1 X

A3.09 - MG set trip: Plant-Specific 3.3 1

204000 Reactor Water Cleanup System / 2 X

K5.04 - Heat exchanger operation 2.7 1

205000 Shutdown Cooling System (RHR X

K1.03 - Recirculation loop temperature 3.5 1

Shutdown Cooling Mode) / 4 219000 RH-RILPCI: Torus/Suppression Pool X

K6.01 - A.C. electrical power 3.3 1

Cooling Mode / 5 245000 Main Turbine Generator and X

K4.06 - Generator protection 2.8 1

Auxiliary Systems / 4 259001 Reactor Feedwater System / 2 X

A1.02 - Feedwater inlet temperature 3.3 1

262002 Uninterruptable Power Supply X 2.1,33 - Ability to recognize indications for 4.0 1

(A. C./D.C.) / 6 system operating parameters which are entry-level conditions for technical specifications.

262002 Uninterruptable Power Supply X

K3.14 - Rx power: Plant-Specific 3.1 1

(A.C./D.C.) / 6 263000 D.C. Electrical Distribution / 6 X

K2.01 - Major D.C. loads 3.4 1

1

(

Facility:

ES - 401 Oyster Creek

(

BWR SRO Ex".1iination Outline Facility:

Oyster Creek Plant Systems - Tier 2 / Groun 2 K/A Category Totals:

2 1

1 1

1 1

1 1

1 1

2 Form ES-401-1 Group Point Total:

13 2

ES - 401 Printed:

02/1.

, j2 Sys/Ev#

System/Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G A Topic Imp.

Points 271000 Offgas System / 9 X 2.2.25 - Knowledge of bases in technical 3.7 1

specifications for limiting conditions for operations and safety limits.

400000 Component Cooling Water System X

Ki.04 - Reactor coolant system, in order to 3.1 1

(CCWS) / 8 determine source (s) of RCS leakage into CCWS

BWR SRO EL._ination Outline Printed:

02/13 j2 Facility:

Oyster Creek ES - 401 Plant Systems - Tier 2 / Groun 3 Form ES-401-1 K/A Category Totals:

0 0

0 1

0 1

1 0

0 0

1 Group Point Total:

(

Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 201003 Control Rod and Drive Mechanism /

X K4.05 - Rod position indication 3.3 1

1 215001 Traversing In-Core Probe / 7 X

K6.04 - Primary containment isolation system:

3.4 1

Mark-I&II(Not-BWR1) 239001 Main and Reheat Steam System / 3 X

A1.08 - Reactor pressure 3.8 1

290002 Reactor Vessel Internals / 5 X 2.2.25 - Knowledge of bases in technical 3.7 1

specifications for limiting conditions for operations and safety limits.

4 I

Generic Knowledge aý' kbilities Outline (Tier 3)

BWR SRO Examination Outline Facility:

Oyster Creek Generic Category Printed:

02/13/2002 Form ES-401-5 Imp.

Points KA KA Topic Conduct of Operations 2.1.32 Ability to explain and apply system limits and precautions.

3.8 1

2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.

2.9 1

2.1.8 Ability to coordinate personnel activities outside the control room.

3.6 1

2.1.23 Ability to perform specific system and integrated plant procedures during different 4.0 1

modes of plant operation.

2.1.6 Ability to supervise and assume a management role during plant transients and upset 4.3 1

conditions.

Category Total:

5 Equipment Control 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

3.8 1

2.2.10 Knowledge of the process for determining if the margin of safety, as defined in the basis 3.3 1

of any technical specification is reduced by a proposed change, test or experiment.

2.2.34 Knowledge of the process for determining the internal and external effects on core 3.2*

1 reactivity.

2.2.2 Ability to manipulate the console controls as required to operate the facility between 3.5 1

shutdown and designated power levels.

2.2.13 Knowledge of tagging and clearance procedures.

3.8 1

Category Total:

5 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including 3.1 1

permissible levels in excess of those authorized.

2.3.2 Knowledge of facility ALARA program.

2.9 1

2.3.9 Knowledge of the process for performing a containment purge.

3.4 1

Category Total:

3 1

Generic Knowledge a[' Abilities Outline (Tier 3)

Printed: 02/13/2002(

BWR SRO Examination Outline Facility:

Oyster Creek Generic Category Form ES-401-5 Imp.

Points KA KA Topic Category Total:

Generic Total:

Emergency Plan 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including 3.5 1

system geography and system implications.

2.4.7 Knowledge of event based EOP mitigation strategies.

3.8 1

2.4.25 Knowledge of fire protection procedures.

3.4 1

2.4.29 Knowledge of the emergency plan.

4.0 1

4 17 2

K ES-401 Record of Rejected K/As Form ES-401-10 Tier / Group Randomly Selected K/A Reason for Rejection 2 9 52903t EAP, U QUeiTSQN 0 t A,131L. If N7O0 QP~,2j Spoj, PUt2I"#t(p O~t - Sjr SE o;S M 0-7 f-32ivmAu.MIj 2-z 1C Wc02 -Mts CpaUX4 rM o a~ow Pi.AP10-a:j^

24LI_______

-tz 40mi Pok-csS0Il)T 0u "R~nr&%~

I~MMWIC%-

CVMAAIVQ.

J&C7WY' NUREG-1 021, Revision 8, Supplement 1 4 f4 46 of 46

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Oyster Creek NRC Date of Examination: Week of May 13, 2002 Examination Level (circle one):

RO /(RO Operating Test Number:

SRO Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A. 1 Temporary Procedure Temporary Procedure Change - Alternate Path (JPM)

Change JPM Change of intent - be obvious Plant Parameter Verification of Identified Leakage (JPM)

Verification JPM A.2 Technical Specification Tech Spec interpretation and log entry (JPM)

Equipment Control JPM A.3 Control of Radiation Review and approve a Liquid Radwaste Discharge - Alternate Releases JPM Path (JPM)

Authorize pumping 1-5 sump overboard, SW rad monitor A.4 Emergency Classification Make an Emergency Classification (JPM)

JPM Security based

ES-301 Control Room Systems and Facility Walk-Throuqh Test Outline Facility:

Oyster Creek NRC Date of Examination:

Week of May 13, 2002 Exam Level (circle one): RO /(o

/ SRO(U)

Operating Test No.:

SRO B. 1 Control Room Systems System / JPM Title Type Safety Code*

Function

a. Reactor Manual Controls (RMC) / Perform rod coupling 201.01 check (Alternate Path - Rod Uncoupled)

M, S, A, L

b. Reactor Feedwater System / Place third feedwater pump in N, S 2

service

c. Main Steam / Bypass a MSIV low-low isolation signal 239.01 3

D,S

d. Recirculation system / Respond to a tripped recirc pump 202.10 4

with 5 operating (Alternate Path - Discharge Valve will not D, s, A close)

e. Containment Spray / Manually initiate Containment Spray 226.01 5

(Alternate Path - Containment Spray Pump Trips)

M, S, A

f. Emergency Generators / Normal start of EDG from control 264.01 6

room D, S

g. Standby Gas Treatment system (SGTS) / Confirm N, S, A 9

Secondary Containment Initiations and Isolations (Alternate Path - SGTS fails to start)

B.2 Facility Walk-Through 308.04

a. Shutdown Cooling / Transfer control to LSP 1A2 (shutdown D,R 4

cooling pump)

Abnormal 223.03

b. Primary Containment / Line-up to vent the Torus through D

5 the hardened vent Emergency 279.06

c. Instrument Air / Manually scram the reactor by venting the D, R 8

Scram Air Header Emergency

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Form ES-301-2

Scenario Outline ES-D-1 Simulation Facility Oyster Creek Examiners Scenario No.

SRO #1 Op Test No.

Operators PRO URO Scenario The scenario begins with the reactor at 80% power with the 'A' Isolation Condenser and the 'A' CRD Summary Pump out of service. The crew will begin by swapping the RBCCW Pumps. APRM 4 will then fail upscale requiring the crew to evaluate Tech Specs, bypass the APRM, and reset the half scram. The

'A' Feedwater Pump trips requiring the crew to reduce power to maintain reactor level. A loss of power to Bus 1 B will result in the crew manually scramming due to a loss of all feedwater. The diesel generator will auto start and restore power to Bus 1D but, the 1 B CRD pump will fail to restart due to a logic malfunction. The 1 B CRD pump can be manually restarted. The 'B' Isolation Condenser fails to initiate resulting in a complete loss of high pressure feedwater. The 'B' EMRV fails to reclose following manual actuation. This causes a loss of RPV level, which will result in the need to Emergency Depressurize.

Initial Condition 80% power Turnover:

See Attached "Shift Turnover" Sheet Event Malfunction Event Event No.

No.

Type*

Description SRO 1

N BOP Swap Reactor Water Closed Cooling Water (RBCCW) Pumps SRO 2

I RO APRM 4 Fails Upscale (Tech Spec)

SRO 3

C RO

'A' Feedwater Pump Trips BOP SRO 4

R RO Power Reduction to Control Level BOP SRO 5

M RO Loss of Power to 4160V Bus 1B - Results in Plant Scram BOP SRO 6

I RO

'B' CRD Pump Fails to Auto Restart due to a Logic Malfunction on BOP Power Restoration SRO 7

C RO

'B' Isolation Condenser fails to initiate due to a Valve Failure BOP SRO 8

C RO

'B' EMRV Fails to Reclose After Manual Actuation BOP

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

Scenario Outline ES-D-1 Simulation Facility Oyster Creek Examiners Scenario No.

SRO #2 Op Test No.

Operators PRO URO Scenario The scenario begins with the reactor at 90% power with 4 recirc pumps operating. One recirc pump Summary has been secured due to emergent maintenance. The crew will begin by raising MVAR loading on the main generator. The crew will remove a recirc pump from service due to MG set malfunctions requiring the crew to reduce power to comply with pump and system limitations. A loss of power to a vital bus will occur requiring the crew to restore vital loads. This will require a Tech Spec evaluation.

A steam leak in the drywell will result in the crew manually scramming due to an increase in drywell pressure. Auto and manual scram functions will be disabled, but Alternate Rod Insertion will insert the rods. Drywell pressure will increase requiring Drywell Sprays using the Containment Spray system. The drywell spray valve fails to automatically realign and must operated manually to permit sprays to function.

Initial Condition 90% power Turnover:

See Attached "Shift Turnover" Sheet Event Malfunction Event Event No.

No.

Type*

Description I

SRO N

BOP Raise MVAR Loading on the Main Generator SRO 2

C RO Recirc MG Set Malfunctions requiring Recirc Pump Shutdown BOP SRO 3

R RO Reduce Power during Recirc Pump Shutdown BOP SRO 4

C RO Loss of Power to the Vital Bus (Tech Spec)

BOP SRO 5

M RO Steam Leak in the Drywell BOP SRO 6

I RO Failure of the Auto and Manual Scram Logic SRO 7

C BOP Containment Spray Valve fails to realign automatically when sprays are required

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor CRS Scenario Outline ES-D-11

Scenario Outline ES-D0-11 Simulation Facility Oyster Creek Examiners Scenario No.

PRO URO Scenario The scenario begins with the reactor at 100% power with the 'A' Isolation Condenser out of service.

Summary Following turnover, the crew will swap Main Air Ejectors. A SLC Tank Hi/Lo Temperature alarm will be received. Investigation will show that actual SLC tank temperatures are low due to a failed heater control circuit and a Tech Spec evaluation will be required. A small Main Condenser vacuum leak requires a power reduction and investigation of the vacuum leak. A RWCU leak will occur in the Reactor Building requiring entry into the Primary Containment Control EOP. A RWCU valve will fail preventing the isolation of the leak. Reactor Building Ventilation will fail to automatically isolate requiring manual action to stop the radioactive release. Emergency Depressurization will be required to mitigate the primary leak into the Reactor Building.

Initial Condition 100% power Turnover:

See Attached "Shift Turnover" Sheet Event Malfunction Event Event No.

No.

Type*

Description 1

SRO N

RO Swap Main Steam Air Ejectors BOP SRO 2

I RO SLC Tank Low Temperature due to Failed Heater Control Circuit (Tech BOP Spec)

SRO 3

C RO Main Condenser Vacuum Leak BOP SRO 4

R RO Lower Power to Control Vacuum BOP SRO 5

M RO Reactor Water Clean-Up Leak into the Reactor Building BOP SRO 6

C RO Reactor Water Clean-Up Isolation Valve Failure BOP SRO 7

I RO Reactor Building Ventilation Fails to Automatically Isolate BOP I

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor SRO #3 Operators Op Test No.

CRS Scenario Outline ES-D-I