ML051250488

75-Day Outline Submittal for the Duane Arnold Initial Examination - Jan/Feb 2005

ML051250488
Person / Time
Site:	Duane Arnold
Issue date:	01/31/2005
From:	Hironori Peterson NRC/RGN-III/DRS/OLB
To:	Nuclear Management Co
References
50-331/05-301 50-331/05-301
Download: ML051250488 (115)

Text

ES-301 Control Room/In-plant Systems Outline Form ES-301-2 Facility:__DAEC____________ Date of Examination:__1/31/05___

Exam Level (circle one): SRO-U Operation Test No.:_2005-01_____

Control Room Systems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a.

b. Install Defeat #1 and use RCIC for Level Control. (217000-

12)

D, S, L 2

c.

d.

e. Drain the Torus to Radwaste. AP to install defeat 13.

(219000-04)

N, A, S 5

f.

g.

h. Establish Alternate Leakage Control IAW AOP 672.2.

(272000-03)

N, S 9

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

i. Shutdown of Regulating Transformer 1Y1A for maintenance. (AP requiring transfer of alternate RPS from 1Y16 to 1Y26) [262002-04]

N, A 6

j. Switch CRD Discharge Filters. (264000-08)

R, D 1

k All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate path (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow -power (N)ew or (M)odified form bank including 1(A)

(P)reious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301-1 RO Administrative Topics Outline E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 ES-301-1 Equivalent RO_final.doc 1 3 ES-301 Administrative Topics Outline Form ES-301-1 Equivalent Facility: DAEC Examination Level (circle one): RO /SRO Date of Examination: 18 November, 2002 Operating Test Number:

Administrative Topic/Subject Description Describe method of evaluation:

1. One Administrative JPM, OR

2. TWO Administrative Questions Perform an APRM gain adjust IAW OI 878.4 2.1.30 3.9/3.4 One Administrative JPM to adjust an APRM gain which requires bypassing and un-bypassing APRMs A.1 Respond to a RBM Rod Block annunciator and safety limit violation 2.2.22 -XX 3.4/4.1 One Administrative JPM to determine the plant has violated an administrative safety limit based on an OFFICIAL 3D CASE in response to RBM Rod Block.

A.2 Coil for Relay C71A-K3C opens STA reports a fuse could be the problem and we should have received a 1/2 Scram and 2 alarms.

2.1.24 2.8/3.1 One Administrative JPM locate logic print and evaluate if the fuse is correct and that the STA was incorrect about 1/2 scram and alarms associated with this relay A.3 Gain Access to a High Rad Area 2.3.1-04 2.6/3.0 The JPM will be administered when the operator is in the Plant. It will test the operators knowledge of the requirements for entry into a High Radiation Area.

Note: Used on 2000 NRC Exam A.4 Plant tour with a visitor when the plant evacuation alarm sounds.

2.4.39-xx 3.3/3.1 One Administrative JPM performed in plant with evaluator as a visitor receiving a plant tour. The plant evacuation alarm sounds. The visitor must be escorted to the appropriate location and the candidate must report to his designated ERO location.

ES-301-1 SRO Administrative Topics Outline E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 ES-301-1 Equivalent SRO_final.doc 1 2 ES-301 Administrative Topics Outline Form ES-301-1 Equivalent Facility: DAEC Examination Level (circle one): RO /SRO Date of Examination: 18 November, 2002 Operating Test Number:

Administrative Topic/Subject Description Describe method of evaluation:

1. One Administrative JPM, OR

2. TWO Administrative Questions Determine reportability (Group 1 isolation) 2.1.14-02 2.5/3.3 One Administrative JPM making reportability determination for a Group 1 Isolation.

A.1 Core alterations -

determine actions for a misplaced fuel bundle during core re-load.

2.2.27-01 2.6/3.5 One Administrative JPM. Error is made in the fuel moving has to be identified, fuel moving stopped, and an error in the correction to the fuel moving plan is identified.

A.2 Coil for Relay C71A-K3C opens STA reports a fuse could be the problem and we should have received a 1/2 Scram and 2 alarms.

2.1.24 2.8/3.1 One Administrative JPM locate logic print and evaluate if the fuse is correct and that the STA was incorrect about 1/2 scram and alarms associated with this relay A.3 Gain Access to a High Rad Area 2.3.1-04 2.6/3.0 The JPM will be administered when the operator is in the Plant. It will test the operators knowledge of the requirements for entry into a High Radiation Area.

Note: Used on 2000 NRC Exam A.4 Dispatch an operator into the plant when the TSC/OSC are not activated.

2.4.38-02 2.2/4.0 One Administrative JPM that requires the SRO to send an operator in the plant during EPIP conditions without the TSC/OSC being activated. EPIPs require a briefing by the OSM on various conditions.

ES-301-2 RO Walk-Through Outline E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 ES-301-2 Equivalent RO_final.doc 1 6 ES-301 Control Room System and Facility Walk-Through Test Outline Form ES-301-2 Equivalent Facility: DAEC Examination Level (circle one): RO / SRO(I) / SRO(U)

Date of Examination: 18 November, 2002 Operating Test Number: 2002 ILC EXAM B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a. SLO/ Recirc power reduction/ Recirc MG lube oil high temperature alarm/Recirc pump trip/Scram 202002-xx (N)(S) 1 Reactivity Control

b. Rapid Restart of the RPF following a reactor scram 259001-11 Note: Used on the 2000 NRC Exam (D)(S)(L) 2 Reactor Water Inventory Control

c. Install EOP Defeat 5 to depressurize the reactor 239001-02 Note: Used on the 2000 NRC Exam (D)(S)(L) 3 Reactor Pressure Control

d. Perform required actions for HPCI rapid start for level control.

206000-15 (D)(S)(L)(A) 4 Heat Removal from Core

e. Containment venting irrespective of radioactive release (alternate path hard pipe vent) 295024-06 (D)(S)(L)(A) 5 Containment Integrity

f.

SBDG STP shutdown from fully loaded/Bus overcurrent alarm/manual rapid shutdown of SBDG and trip.

264000-xx (N)(S)(A) 6 Electrical

g. Perform required actions for repeated manual scram.

212000-10 (D)(S) 7 Instrumentation B.2 Facility Walk-Through

a. Manually Initiate CARDOX 286000-03 Note: Used on the 2000 NRC Exam (D), (R), (A)

(AOP) 8 Plant Service Systems

b. Reset a control building chiller after trip 290003-01 (D)(R) 9 Radioactivity Release

c. Shift 250 VDC battery chargers 263000-01 (D) 6 Electrical

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lernate path, (C)ontrol room, (S)imulator, (L)ow power, (R)CA 5

Alternate path 2

New 4

Low Power 3

EOP/AOP 2

RCA

ES-301-2 SRO-I Walk-Through Outline E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 ES-301-2 Equivalent SRO(I)_final.doc 1 5 ES-301 Control Room System and Facility Walk-Through Test Outline Form ES-301-2 Equivalent Facility: DAEC Examination Level (circle one): RO / SRO(I) / SRO(U)

Date of Examination: 18 November, 2002 Operating Test Number: 2002 ILC EXAM B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a. SLO/ Recirc power reduction/ Recirc MG lube oil high temperature alarm/Recirc pump trip/Scram 202002-xx (N)(S)876 1

Reactivity Control

b. Rapid Restart of the RPF following a reactor scram 259001-11 Note: Used on the 2000 NRC Exam (D)(S)(L) 2 Reactor Water Inventory Control

c. Install EOP Defeat 5 to depressurize the reactor 239001-02 Note: Used on the 2000 NRC Exam (D)(S)(L) 3 Reactor Pressure Control

d. Perform required actions for HPCI rapid start for level control.

206000-15 (D)(S)(L)(A) 4 Heat Removal from Core (ESF)

e. Containment venting irrespective of radioactive release (alternate path hard pipe vent) 295024-06 (D)(S)(L)(A) 5 Containment Integrity

f.

SBDG STP shutdown from fully loaded/Bus overcurrent alarm/manual rapid shutdown of SBDG and trip.

264000-xx (N)(S)(A) 6 Electrical

g. Perform required actions for repeated manual scram.

212000-10 (D)(S) 7 Instrumentation B.2 Facility Walk-Through

a. Manually Initiate CARDOX 286000-03 Note: Used on the 2000 NRC Exam (D), (R), (A)

(AOP) 8 Plant Service Systems

b. Reset a control building chiller after trip 290003-01 (D)(R) 9 Radioactivity Release

c. Shift 250 VDC battery chargers 263000-01 (D) 6 Electrical

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lernate path, (C)ontrol room, (S)imulator, (L)ow power, (R)CA 5

Alternate path 2

New 4

Low Power 3

EOP/AOP 2

RCA

ES-301-2 SRO-U Walk-Through Outline E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 ES-301-2 Equivalent SRO(U)_final.doc 1 4 ES-301 Control Room System and Facility Walk-Through Test Outline Form ES-301-2 Equivalent Facility: DAEC Examination Level (circle one): RO / SRO(I) / SRO(U)

Date of Examination: 18 November, 2002 Operating Test Number: 2002 ILC EXAM B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a. Install EOP Defeat 5 to depressurize the reactor 239001-02 Note: Used on the 2000 NRC Exam (D)(S)(L) 3 Reactor Pressure Control

b. Perform required actions for HPCI rapid start for level control.

206000-15 (D)(S)(L)(A) 4 Heat Removal from Core (ESF)

c. SBDG STP shutdown from fully loaded/Bus overcurrent alarm/manual rapid shutdown of SBDG and trip.

264000-xx (N)(S)(A) 6 Electrical

d.

e.

f.

g.

B.2 Facility Walk-Through

a. Manually Initiate CARDOX 286000-03 Note: Used on the 2000 NRC Exam (D), (R), (A)

(AOP) 8 Plant Service Systems

b. Reset a control building chiller after trip 290003-01 (D)(R) 9 Radioactivity Release

c.

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lernate path, (C)ontrol room, (S)imulator, (L)ow power, (R)CA 3

Alternate path 2

New 1

Low Power 3

EOP/AOP 2

RCA

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 1 Suppression Basis 201001 Control Rod Drive Hydraulic System A3.02 Pump start: Plant-Specific The CRD Pumps have no automatic start feature.

K1.11 Reactor water cleanup pumps: Plant-Specific No interrelationship K3.05 Reactor water cleanup pumps: Plant-Specific No interrelationship 201004 Rod Sequence Control System (Plant Specific)

ALL K/As SUPPRESSED This system is bypassed at DAEC and is only used for back lighting 201005 Rod Control and Information System (RCIS)

ALL K/As SUPPRESSED DAEC is not a BWR 6 and does not have this feature.

201006 Rod Worth Minimizer System (RWM)

A1.03 Latched group indication: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC A2.02 Loss of steam flow input: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

A2.06 Loss of reactor water level control input:

P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

A3.05 Latched group indication: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC A4.03 Latched group indication: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC K1.03 Reactor water level control (feed flow):

P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K1.04 Steam flow/reactor power: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K1.08 Reactor power (turbine first stage pressure): P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K4.07 Display of out of position control rods without rod blocks (transition zone): P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC K5.04 Transition zone: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC K5.07 Latch groups: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 2 Suppression Basis K6.02 Reactor water level control input: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K6.05 Steam flow input: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

202001 Recirculation System K4.15 Slow speed pump start: Plant-Specific DAEC has Variable Speed pumps K4.17 Fast speed pump start: Plant-Specific DAEC has Variable Speed pumps K5.08 E/P converters: Plant-Specific DAEC does not has E/P Converters associated with the Recirc System 202002 Recirculation Flow Control System K4.04 Automatic load following: Plant-Specific Not a feature at DAEC K4.05 Limiting recirculation pump speed mismatch: Plant-Specific Not a feature at DAEC K6.06 Reactor/turbine pressure regulating system: Plant-Specific Not a feature at DAEC 204000 Reactor Water Cleanup System K1.16 CRD system: Plant-Specific There are no physical or logical connections between RWCU and CRD K5.06 Pressure controllers DAEC has a high pressure RWCU system K6.09 CRD hydraulics: Plant-Specific There are no physical or logical connections between RWCU and CRD 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

K1.09 Auxiliary steam supply: Plant-Specific DAEC does not use Auxiliary steam for SDC K1.11 Nitrogen: Plant-Specific SDC mode of RHR does not use the nitrogen supply system K4.01 High temperature isolation: Plant-Specific SDC mode does not have a high temperature isolation K6.06 Auxiliary steam supply: Plant-Specific DAEC does not use Auxiliary steam for SDC K6.07 Nitrogen: Plant-Specific SDC mode of RHR does not use the nitrogen supply system 206000 High Pressure Coolant Injection System A4.11 Turning gear: BWR-2, 3, 4(P-Spec)

DAEC HPCI does not have a turning gear K5.09 Testable check valve operation: BWR-2, 3, 4 DAEC HPCI does not have Testable Check Valves

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 3 Suppression Basis 207000 Isolation (Emergency) Condenser ALL K/As SUPPRESSED DAEC does not have an Isolation Condenser System.

209001 Low Pressure Core Spray System A4.06 Testable check valves There are no testable Check Valves K1.04 condensate transfer system There is no logical or physical connection between Core Spray and Service Condensate K1.11 Drywell coolers: Plant-Specific There is no logical or physical connection between Core Spray and Drywell cooling K3.04 Component cooling water systems Core Spray provides no component cooling water K3.05 Drywell cooling: Plant-Specific There is no logical or physical connection between Core Spray and Drywell cooling K5.03 Testable check valve operation No testable check valves K6.07 Pump seal cooler(s)

Core Spray has no seal coolers 209002 High Pressure Core Spray System (HPCS)

ALL K/As SUPPRESSED The DAEC does not have a High Pressure Core Spray System.

211000 Standby Liquid Control System K1.10 HPCI: Plant-Specific At the DAEC, there are no physical or logical connections between the SBLC System and HPCI.

K6.04 Core spray system: Plant-Specific At the DAEC, a failure of the Core Spray System has no effect on the SBLC System.

K6.05 HPCI system: Plant-Specific At the DAEC, there are no physical or logical connections between the SBLC System and HPCI.

212000 Reactor Protection System A1.04 RPS bus voltage: Plant-Specific At the DAEC, there are no dedicated indications for the RPS busses. RPS MG Set voltage and frequency are the indications for the RPS bus.

A1.05 RPS bus frequency: Plant-Specific At the DAEC, there are no dedicated indications for the RPS busses. RPS MG Set voltage and frequency are the indications for the RPS bus.

A4.03 Provide manual select rod insertion:

Plant-Specific Select Rod Insertion does not apply to the DAEC.

K4.06 Select rod insertion: Plant-Specific Select Rod Insertion does not apply to the DAEC.

214000 Rod Position Information System K4.02 Thermocouple CRD Mechanism temperature is not associated with RPIS.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 4 Suppression Basis 215003 Intermediate Range Monitor (IRM)

System K1.05 Display control system: Plant-Specific The DAEC does not have a Display Control System.

K1.06 APRM SCRAM signals: Plant-Specific The DAEC no longer has an IRM Upscale or Inop/APRM Downscale Scram.

215004 Source Range Monitor (SRM) System K1.05 Display control system: Plant-Specific The DAEC does not have a Display Control System.

215005 Average Power Range Monitor/Local Power Range Monitor System K1.08 Display control system: Plant-Specific The DAEC does not have a Display Control System.

K1.15 Redundant reactivity control system:

Plant-Specific The DAEC does not have a Redundant Reactivity Control System.

216000 Nuclear Boiler Instrumentation K1.18 Analog trip system: Plant-Specific The DAEC does not have an Analog Trip System.

K2.01 Analog trip system: Plant-Specific The DAEC does not have an Analog Trip System.

K3.18 Analog trip system: Plant-Specific The DAEC does not have an Analog Trip System.

K3.28 Loose parts detection in the primary system: Plant-Specific The DAEC does not have Loose Parts Monitoring.

K5.05 Vessel vibration measurement (loose parts monitor)

The DAEC does not have Loose Parts Monitoring.

217000 Reactor Core Isolation Cooling System (RCIC)

K1.08 Line fill pump: Plant-Specific At the DAEC, RCIC has no keep fill pump.

K5.04 Testable check valve operation The DAEC has no testable check valves.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 5 Suppression Basis 218000 Automatic Depressurization System SEE NOTE AT BOTTOM OF PAGE 219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode A1.05 Condensate storage tank level: Plant-Specific At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

A1.10 Containment air temperature: Mark-III The DAEC has a MARK 1 containment.

A4.10 Condensate storage tank level: Plant-Specific At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

K1.02 Condensate storage tank At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

K6.05 Condensate storage tank: Plant-Specific At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

223001 Primary Containment System and Auxiliaries A1.12 Moisture concentration The DAEC does not monitor containment moisture content.

A4.13 Hydrogen recombiners: Plant-Specific DAEC has a MARK 1 Containment A4.14 Hydrogen igniters: Plant-Specific DAEC has a MARK 1 Containment K2.05 Hydrogen recombiners: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K2.06 Hydrogen igniters: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K2.08 Containment cooling air handling units:

Plant-Specific The DAEC does not have electric containment cooling units.

K2.10 Drywell chillers: Plant-Specific The DAEC does not have Drywell chillers.

K3.10 Containment/drywell moisture content The DAEC does not monitor containment moisture content.

K5.05 Hydrogen recombiner operation: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K5.06 Hydrogen igniter operation: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K5.15 Moisture content measurement: Plant-Specific The DAEC does not monitor containment moisture content.

K6.04 Combustible gas mixing: Plant-Specific The DAEC does not have a system for combustible gas mixing.

K6.05 Hydrogen recombiner: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K6.07 Hydrogen igniter system: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 6 Suppression Basis 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off K1.09 Reactor vessel head spray: Plant-Specific The DAEC has removed head spray piping.

K1.21 Circulating water: Plant-Specific At the DAEC, there are no logical connections between PCIS and Circulating Water.

K3.17 Reactor vessel head spray: Plant-Specific The DAEC has removed head spray piping.

K3.27 Circulating water At the DAEC, there are no logical connections between PCIS and Circulating Water.

226001 RHR/LPCI: Containment Spray System Mode SEE NOTE AT BOTTOM OF PAGE 233000 Fuel Pool Cooling and Clean-up A4.02 System lineups At the DAEC, Fuel Pool Cooling is controlled and mostly monitored from the Reactor Building.

K1.13 Suppression pool cleanup system: Plant-Specific At the DAEC, Suppression Pool Cleanup/Chemistry would be through the Condensate Demineralizers.

K3.07 Suppression pool chemistry: Plant-Specific At the DAEC, Suppression Pool Cleanup/Chemistry would be through the Condensate Demineralizers.

234000 Fuel Handling Equipment SEE NOTE AT BOTTOM OF PAGE 239001 Main and Reheat Steam System K1.04 Moisture separators The DAEC has Moisture Separator Reheaters (K1.05)

K1.14 Positive leakage control system: Plant Specific The DAEC has no positive leakage control system K1.20 Residual heat removal system: Plant-Specific At the DAEC, there are no physical or logical connections between the Main Steam System and the RHR System.

K2.02 Main steam line shutoff valves (guard valves): Plant-Specific The DAEC has no Main Steam Line Shutoff valves.

K3.14 Residual heat removal system: Plant-Specific At the DAEC, there are no physical or logical connections between the Main Steam System and the RHR System.

K5.04 Definition and reason for steam blanketing of moisture separator reheater: Plant-Specific The DAEC no longer uses Steam Blanketing of MSRs.

K5.07 Hydraulic operated MSIV's The DAEC has pneumatically operated MSIVs.

239002 Relief/Safety Valves K1.05 Plant air systems: Plant-Specific At the DAEC, there are no physical or logical connections between the ADS/LLS Systems and Plant air systems.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 7 Suppression Basis 239003 MSIV Leakage Control System ALL K/As SUPPRESSED The DAEC has removed the MSIV Leakage Control System.

241000 Reactor/Turbine Pressure Regulating System A1.26 Governor valve limit: Plant-Specific The DAEC does not have a governor valve for the Main Turbine.

A2.25 Loss of primary water system: Plant-Specific The DAEC does not have a primary water system.

A3.13 FW heater isolation: Plant-Specific The DAEC does not have a FW heater isolation feature.

A3.14 Grid load following: Plant-Specific Grid Load Following is not applicable to the DAEC.

K1.34 EGC system: Plant-Specific The DAEC does not have an EGC System.

K1.35 Low pressure stop and control valves:

Plant-Specific The DAEC does not have low pressure stop and control valves.

K1.36 Primary water system: Plant-Specific The DAEC does not have a primary water system.

K3.28 Low pressure stop and control valves:

Plant-Specific The DAEC does not have low pressure stop and control valves.

K3.30 EGC: Plant-Specific The DAEC does not have an EGC System.

K4.08 Feedwater heater isolation: Plant-Specific The DAEC does not have FW Heater isolation feature.

K4.11 Load following: Plant-Specific Grid Load Following is not applicable to the DAEC.

K4.12 Recirculation flow control: Plant-Specific There are no design features or interlocks in the EHC System that directly affect Recirculation flow control.

K5.07 Unitized actuator operation: Fermi-Only The DAEC does not have a unitized actuator.

K6.18 Low pressure stop and control valves:

Plant-Specific The DAEC does not have low pressure stop and control valves.

K6.19 Primary water system: Plant-Specific The DAEC does not have a primary water system.

245000 Main Turbine Generator and Auxiliary Systems K2.03 Amplidyne: Plant-Specific The DAEC does not have an amplidyne for the Main Generator.

K2.05 Air seal oil pumps: Plant-Specific The DAEC does not have air seal oil pumps.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 8 Suppression Basis 256000 Reactor Condensate System A2.17 Feedwater heater string trip: Plant-Specific At the DAEC, there are no trips on feedwater heater strings.

A3.09 Feedwater heater drain tank level:

Plant-Specific At the DAEC, there is no feedwater heater drain tank.

A4.14 Feedwater heater drain tank level:

Plant-Specific At the DAEC, there is no feedwater heater drain tank.

K1.04 RCIC: Plant-Specific At the DAEC, there are no physical or logical connections between the Condensate System and the RCIC System.

K1.09 Offgas condenser: Plant-Specific At the DAEC, there are no physical or logical connections between the Condensate System and the Offgas System.

K1.21 Steam seal evaporator: Plant-Specific The DAEC has no Steam Seal Evaporator.

K1.23 Auxiliary steam system: Plant-Specific The DAEC has no Auxiliary Steam System.

K4.01 Condensate and/or booster pump auto start: Plant-Specific At the DAEC, there are no automatic Condensate Pump starts and the DAEC has no condensate booster pumps.

K4.05 Maintenance of 100% system flow if a feedwater string isolates: Plant-Specific At the DAEC, there are no feedwater string isolations.

259001 Reactor Feedwater System A3.01 RFP auto start: Plant-Specific The DAEC has no automatic start feature for the feedwater pumps.

A3.11 Reactor feed pump runbacks: Plant-Specific The DAEC has no runback feature for the feedwater pumps.

K1.15 RHR: Plant-Specific At the DAEC, there are no physical or logical connections between the Feedwater System and the RHR System.

K1.18 Fire protection system (emergency cooling): Plant-Specific At the DAEC, there is no physical or logical connections between the Feedwater System and the Fire Protection System used as emergency cooling.

K1.19 Redundant reactivity control system:

Plant-Specific At the DAEC, there is no Redundant Reactivity Control System associated with the Feedwater System.

K3.11 RHR: Plant-Specific At the DAEC, there are no physical or logical connections between the Feedwater System and the RHR System.

K4.01 Auto start of the RFP's: Plant-Specific The DAEC has no automatic start feature for the feedwater pumps.

K4.10 Feed pump runbacks: Plant-Specific The DAEC has no runback feature for the feedwater pumps.

K6.13 Redundant reactivity control: Plant-Specific At the DAEC, there is no Redundant Reactivity Control System associated with the Feedwater System.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 9 Suppression Basis 259002 Reactor Water Level Control System A3.01 Runout flow control: Plant-Specific At the DAEC, feed pump runout conditions are controlled manually by the operator.

A3.06 Reactor water level setpoint setdown following a reactor scram: Plant-Specific DAEC does not have automatic setpoint setdown A4.05 Runout flow control reset controls:

Plant-Specific At the DAEC, feed pump runout conditions are controlled manually by the operator.

K1.07 Rod worth Minimizer: Plant-Specific At the DAEC, there are no physical or logical connections between the FWLC System and Rod Worth Minimizer.

K1.09 P sat/T sat (compensation)

At the DAEC, FWLC does not use Psat/Tsat compensation.

K3.03 Rod worth Minimizer: Plant-Specific At the DAEC, there are no physical or logical connections between the FWLC System and Rod Worth Minimizer.

K4.02 Bypassing of the RWM: Plant-Specific At the DAEC, there are no physical or logical connections between the FWLC System and Rod Worth Minimizer.

K4.03 Reactor feed pump runout protection:

MDFP At the DAEC, feed pump runout conditions are controlled manually by the operator.

K4.05 P sat/T sat (compensation)

At the DAEC, FWLC does not use Psat/Tsat compensation.

K4.11 DP control: Plant-Specific At the DAEC, FWLC is not designed to control dP.

K5.01 GEMAC/Foxboro/Bailey controller operation: Plant-Specific At the DAEC, FWLC uses MOORE controllers.

K6.06 Reactor pressure/temperature input (for water level input compensation)

At the DAEC, FWLC does not use Psat/Tsat compensation.

K6.08 Loss of dP across startup level control bypass valve: Plant-Specific At the DAEC, FWLC is not designed to control dP.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 10 Suppression Basis 262002 Uninterruptible Power Supply (A.C./D.C.)

A1.02 Motor generator outputs The DAEC uses a static inverter.

K1.02 RFPT control: Plant-Specific The DAEC does not have RFPT control.

K1.08 Containment isolation system: Plant-Specific At the DAEC, PCIS is powered from RPS.

K1.09 Drywell ventilation control: Plant-Specific At the DAEC, Drywell ventilation is not affected by Uninterruptible AC power.

K1.10 Fire protection system: Plant-Specific At the DAEC, the Fire Protection System is unaffected by the Uninterruptible AC System.

K1.12 Generator hydrogen and stator cooling water controls: Plant-Specific At the DAEC, the Hydrogen and Stator Cooling controls are unaffected by Uninterruptible AC power.

K1.14 Main steam line radiation monitors:

Plant-Specific At the DAEC, the Main Steam Line Rad Monitors are unaffected by Uninterruptible AC power.

K1.16 MSIV's: Plant-Specific At the DAEC, the MSIVs are unaffected by Uninterruptible AC power.

K1.17 Scram solenoid valves: Plant-Specific At the DAEC, the scram solenoids are unaffected by Uninterruptible AC power.

K3.03 RFPT speed: Plant-Specific The DAEC does not have RFPT control.

K3.04 Fire protection system: Plant-Specific At the DAEC, the Fire Protection System is unaffected by Uninterruptible AC power.

K3.09 Drywell ventilation control: Plant-Specific At the DAEC, the Drywell ventilation control is unaffected by Uninterruptible AC power.

K3.10 Containment isolation: Plant-Specific At the DAEC, the Containment Isolations are unaffected by Uninterruptible AC power.

K3.11 MSIV's: Plant-Specific At the DAEC, the MSIVs are unaffected by Uninterruptible AC power.

K5.02 General principles of motor generator operation: Plant-Specific The DAEC uses a static inverter.

K5.03 General principles of inertia fly wheel operation: Plant-Specific The DAEC uses a static inverter.

263000 D.C. Electrical Distribution A4.02 Battery voltage indicator: Plant-Specific At the DAEC, operators do not maintain the batteries, and there are no controls or indications in the control room.

A4.03 Battery discharge rate: Plant-Specific At the DAEC, operators do not maintain the batteries, and there are no controls or indications in the control room.

A4.04 Ground detection circuit: Plant-Specific At the DAEC, operators do not maintain the batteries, and there are no controls or indications in the control room.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 11 Suppression Basis 264000 Emergency Generators (Diesel/Jet)

SEE NOTE AT BOTTOM OF PAGE 268000 Radwaste K1.10 Auxiliary steam: Plant-Specific The DAEC does not have an Auxiliary Steam System.

271000 Offgas System SEE NOTE AT BOTTOM OF PAGE 272000 Radiation Monitoring System A3.02 Offgas system isolation indications At the DAEC, the Offgas System no longer isolates on high radiation.

A3.05 Refuel floor overhead crane operation interrupt: Plant-Specific At the DAEC, there is no interrupt/interlock of the Reactor Building crane due to high radiation.

A3.11 Circulating water system blowdown isolations: Plant-Specific The DAEC does not monitor the Circ Water System for radiation and there is no isolation of the Blowdown Valve due to radiation.

K1.11 Reactor building overhead crane; Plant-Specific At the DAEC, there is no interrupt/interlock of the Reactor Building crane due to high radiation.

K1.15 Filter building: Plant-Specific The DAEC does not have a Filter Building.

K1.18 Primary containment/containment building: Plant-Specific The DAEC has a Drywell. (K1.19)

K1.20 Auxiliary building: Plant-Specific The DAEC does not have an Auxiliary Building.

K3.07 Reactor building overhead crane operation: Plant-Specific At the DAEC, there is no interrupt/interlock of the Reactor Building crane due to high radiation.

K3.08 Auxiliary building ventilation: Plant-Specific The DAEC does not have an Auxiliary Building.

286000 Fire Protection System A2.12 Low diesel fuel supply: Plant-Specific The DAEC has no procedure for transferring diesel fuel to the diesel fire pump.

K1.08 Intake canals: Plant-Specific The DAEC has no Intake canals.

K1.11 Screen wash system: Plant-Specific At the DAEC, there is no physical or logical connections between the Fire Protection System and the screen wash system.

K6.04 Diesel fuel transfer system: Plant-Specific The DAEC has no procedure for transferring diesel fuel to the diesel fire pump.

K6.05 Screen wash system: Plant-Specific At the DAEC, there is no physical or logical connections between the Fire Protection System and the screen wash system.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 12 Suppression Basis 290001 Secondary Containment A4.03 Auxiliary building differential pressure:

Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

A4.04 Auxiliary building area temperature:

Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

A4.05 Fuel building differential pressure:

Plant-Specific The DAEC does not have a Fuel Building.

A4.06 Fuel building area temperature: Plant-Specific The DAEC does not have a Fuel Building.

A4.07 Radwaste building differential pressure:

Plant-Specific At the DAEC, Radwaste building dP and area temperature are not monitored in the Control Room.

A4.08 Radwaste building area temperature:

Plant-Specific At the DAEC, Radwaste building dP and area temperature are not monitored in the Control Room.

K1.05 Auxiliary building ventilation: Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

K6.05 Auxiliary building ventilation: Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

K6.07 Auxiliary boiler system: BWR-3, 4 At the DAEC, a loss of the Aux Boiler does not effect Secondary Containment.

290002 Reactor Vessel Internals K1.18 Lost parts monitoring: Plant-Specific The DAEC has no lost parts monitoring K6.16 Loss parts monitoring The DAEC has no lost parts monitoring 290003 Control Room HVAC K1.02 Chlorine ammonia detectors: Plant-Specific The DAEC does not use Chorine Ammonia detectors.

K1.04 Nuclear steam supply shut off system (NSSSS/PCIS): Plant-Specific At the DAEC, there are no logical connections between Control Building HVAC and NSSSS/PCIS.

295001 Partial or Complete Loss of Forced Core Flow Circulation SEE NOTE AT BOTTOM OF PAGE 295002 Loss of Main Condenser Vacuum AK3.08 Recirculation system run-backs: Plant-Specific The DAEC does not have Recirculation System runbacks based on Main Condenser vacuum.

295003 Partial or Complete Loss of AC Power SEE NOTE AT BOTTOM OF PAGE 295005 Main Turbine Generator Trip AK2.06 Seal steam evaporator: Plant-Specific The DAEC does not have a seal steam evaporator.

295006 SCRAM AK3.05 Direct turbine generator trip: Plant-Specific At the DAEC, there is no direct turbine trip caused by a scram signal.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 13 Suppression Basis 295007 High Reactor Pressure SEE NOTE AT BOTTOM OF PAGE 295008 High Reactor Water Level AK1.04 Containment integrity: Alis-Chalmers This is not applicable to the DAEC.

AK2.01 RPS: Plant-Specific The DAEC does not have a reactor scram signal due to High Reactor Water Level.

AK2.04 PCIS/NSSSS: Plant-Specific The DAEC does not have PCIS Isolations due to High Reactor Water Level.

AK3.02 Reactor SCRAM: Plant-Specific The DAEC does not have a reactor scram signal of High Reactor Water Level.

AK3.03 PCIS/NSSSS initiation: Plant-Specific The DAEC does not have PCIS Isolations due to High Reactor Water Level.

AK3.06 RCIC turbine trip: Plant-Specific The DAEC RCIC System Steam Supply Valve closes on High Reactor Water Level. (AK3.08) 295009 Low Reactor Water Level AK3.02 Reactor feed pump runout flow control:

Plant-Specific The DAEC does not have a Feed pump runout control system.

295010 High Drywell Pressure AA2.04 Drywell humidity: Plant-Specific The DAEC does not monitor Drywell humidity.

295011 High Containment Temperature (Mark III Containment Only)

ALL K/As SUPPRESSED The DAEC has a MARK I containment.

295012 High Drywell Temperature AA2.03 Drywell humidity: Plant-Specific The DAEC does not monitor Drywell humidity.

295014 Inadvertent Reactivity Addition SEE NOTE AT BOTTOM OF PAGE 295015 Incomplete SCRAM AA1.06 RSCS: Plant-Specific At the DAEC, RSCS has been decommissioned and only provides back lighting.

AK2.06 RSCS: Plant-Specific At the DAEC, RSCS has been decommissioned and only provides back lighting.

295016 Control Room Abandonment SEE NOTE AT BOTTOM OF PAGE 295017 High Off-Site Release Rate SEE NOTE AT BOTTOM OF PAGE 295019 Partial or Complete Loss of Instrument Air SEE NOTE AT BOTTOM OF PAGE 295020 Inadvertent Containment Isolation SEE NOTE AT BOTTOM OF PAGE 295021 Loss of Shutdown Cooling AK2.06 Reactor vessel head spray: Plant-Specific The DAEC has removed the Head Spray piping.

295022 Loss of CRD Pumps AA1.04 Reactor water cleanup system: Plant-Specific The loss of a CRD pump does not effect RWCU.

AK2.05 Reactor water cleanup: Plant-Specific The loss of a CRD pump does not effect RWCU.

AK2.06 Shared components with other units:

Plant-Specific Single Unit Site.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 14 Suppression Basis 295023 Refueling Accidents AA1.05 Fuel transfer system: Plant-Specific The DAEC does not have a Fuel Transfer System.

295024 High Drywell Pressure EK2.17 Auxiliary building isolation logic: Plant-Specific The DAEC does not have an Auxiliary Building.

EK3.09 Auxiliary building isolation: Plant-Specific.

The DAEC does not have an Auxiliary Building.

295025 High Reactor Pressure SEE NOTE AT BOTTOM OF PAGE 295026 Suppression Pool High Water Temperature SEE NOTE AT BOTTOM OF PAGE 295027 High Containment Temperature (Mark III Containment Only)

ALL K/As SUPPRESSED The DAEC has a MARK I containment.

295029 High Suppression Pool Water Level SEE NOTE AT BOTTOM OF PAGE 295030 Low Suppression Pool Water Level SEE NOTE AT BOTTOM OF PAGE 295031 Reactor Low Water Level EK2.10 Redundant reactivity control: Plant-Specific The DAEC does not have a Redundant Reactivity Control System.

295034 Secondary Containment Ventilation High Radiation EA1.05 Fuel building ventilation: Plant-Specific The DAEC has a MARK 1 Containment and does not have a Fuel Building.

EK3.04 Fuel building ventilation: Plant-Specific The DAEC has a MARK 1 Containment and does not have a Fuel Building.

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown SEE NOTE AT BOTTOM OF PAGE 295038 High Off-Site Release Rate SEE NOTE AT BOTTOM OF PAGE 300000 Instrument Air System (IAS)

K1.03 Containment air At the DAEC, Containment pneumatics is supplied with nitrogen, including all MSIVs.

K1.05 Main Steam Isolation Valve air At the DAEC, Containment pneumatics is supplied with nitrogen, including all MSIVs.

K3.01 Containment air system At the DAEC, Containment pneumatics is supplied with nitrogen, including all MSIVs.

K3.03 Cross-tied units The DAEC is a single unit site 500000 High Containment Hydrogen Concentration EK2.05 Hydrogen and oxygen recombiners The DAEC does not have hydrogen and oxygen recombiners associated with Containment.

EK3.03 Operation of hydrogen and oxygen recombiners The DAEC does not have hydrogen and oxygen recombiners associated with Containment.

Condensed System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases condensed.doc NOTE: Systems with no K/As listed have suppressed K/As based on system or design features which do not apply at the DAEC. (See the list on Attachment 1 Methodology Used for the DAEC K/A Suppressed Catalog) 15 Suppression Basis 600000 Plant Fire On Site AA2.10 Time limit of long-term-breathing air system for control room The DAEC has no long term breathing air system for the control room.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 1

Suppression Basis 201001 Control Rod Drive Hydraulic System A1.04 Head spray flow: BWR-3 Not BWR 3 A3.02 Pump start: Plant-Specific The CRD Pumps have no automatic start feature.

K1.04 Head spray: BWR-3 Not a BWR 3 K1.11 Reactor water cleanup pumps: Plant-Specific No interrelationship K3.04 Head spray: BWR-3 Not a BWR 3 K3.05 Reactor water cleanup pumps: Plant-Specific No interrelationship 201004 Rod Sequence Control System (Plant Specific) 2.1.14 Knowledge of system status criteria which require the notification of plant personnel.

This system is bypassed at DAEC and is only used for back lighting 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

This system is bypassed at DAEC and is only used for back lighting 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation.

This system is bypassed at DAEC and is only used for back lighting 2.1.27 Knowledge of system purpose and/or function.

This system is bypassed at DAEC and is only used for back lighting 2.1.28 Knowledge of the purpose and function of major system components and controls.

This system is bypassed at DAEC and is only used for back lighting 2.1.30 Ability to locate and operate components, including local controls.

This system is bypassed at DAEC and is only used for back lighting 2.1.32 Ability to explain and apply system limits and precautions.

This system is bypassed at DAEC and is only used for back lighting 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

This system is bypassed at DAEC and is only used for back lighting 2.2.22 Knowledge of limiting conditions for operations and safety limits.

This system is bypassed at DAEC and is only used for back lighting 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

This system is bypassed at DAEC and is only used for back lighting 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.

This system is bypassed at DAEC and is only used for back lighting 2.4.31 Knowledge of annunciators alarms and indications, and use of the response instructions.

This system is bypassed at DAEC and is only used for back lighting

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 2

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

This system is bypassed at DAEC and is only used for back lighting 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

This system is bypassed at DAEC and is only used for back lighting 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

This system is bypassed at DAEC and is only used for back lighting 2.4.6 Knowledge symptom based EOP mitigation strategies.

This system is bypassed at DAEC and is only used for back lighting A1.01 Reactor manual control system: BWR-4, 5

This system is bypassed at DAEC and is only used for back lighting A2.01 Loss of rod position information: BWR-4, 5

This system is bypassed at DAEC and is only used for back lighting A2.02 Attempting to move a stuck control rod:

BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A2.03 Turbine trip: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A3.01 Rod select switch light: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A3.02 Rod select bottom lamp dimmer logic:

BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A3.03 Back panel indicators: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A3.04 Annunciator and alarm signals: BWR-4, 5

This system is bypassed at DAEC and is only used for back lighting A3.05 Verification of proper function/

operability: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A4.01 System bypass switches: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A4.02 RSCS console switches and indicators:

BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting A4.03 RSCS back panel switches and indicators: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K1.01 Reactor manual control system: BWR-4, 5

This system is bypassed at DAEC and is only used for back lighting K1.02 Turbine generator system: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K1.03 Rod position information system: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K1.04 Rod worth minimizer: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K3.01 Reactor manual control: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 3

Suppression Basis K4.01 Select blocks: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K4.02 Insert rod blocks: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K4.03 Withdraw rod blocks: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K4.04 RSCS bypass as reactor power increases:

BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K4.05 Rod movement, direction, and selection information: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K4.06 Group notch control: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K4.07 Minimizing rod worth: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K5.01 Prevention of clad damage if a control rod drop accident (CRDA) occurs: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K5.02 Sequences and groups: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K5.03 Group notch control limits and rod density: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K6.01 Rod position information: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K6.02 Rod direction information: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K6.03 Rod movement information: BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting K6.04 Turbine generator (1st stage shell pressure): BWR-4, 5 This system is bypassed at DAEC and is only used for back lighting 201005 Rod Control and Information System (RCIS)

A1.01 First stage shell pressure/turbine load:

BWR-6 DAEC is not a BWR 6 and does not have this feature A2.01 High flux (SRM, IRM, APRM): BWR-6 DAEC is not a BWR 6 and does not have this feature A2.02 Position indication probe failure: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.03 Insert block: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.04 Withdraw block: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.05 Insert required: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.06 Insert inhibit: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.07 Withdraw inhibit: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.08 LPRM upscale/down scale: BWR-6 DAEC is not a BWR 6 and does not have this feature

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 4

Suppression Basis A2.09 Test display blinking: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.10 Data fault: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.11 Accumulator fault: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.12 Rod uncoupled: BWR-6 DAEC is not a BWR 6 and does not have this feature A2.13 Rod drift: BWR-6 DAEC is not a BWR 6 and does not have this feature A3.01 Operator control module lights: BWR-6 DAEC is not a BWR 6 and does not have this feature A3.02 Rod display module lights: BWR-6 DAEC is not a BWR 6 and does not have this feature A3.03 Verification of proper functioning/

operability: BWR-6 DAEC is not a BWR 6 and does not have this feature A3.04 Annunciator and alarm signals: BWR-6 DAEC is not a BWR 6 and does not have this feature A4.01 Operator control module (lights and push buttons): BWR-6 DAEC is not a BWR 6 and does not have this feature A4.02 Rod display module (lights and push buttons): BWR-6 DAEC is not a BWR 6 and does not have this feature A4.03 Back panel indicating lights: BWR-6 DAEC is not a BWR 6 and does not have this feature K1.01 Neutron monitoring system: BWR-6 DAEC is not a BWR 6 and does not have this feature K1.02 Reactor/turbine pressure control system:

BWR-6 DAEC is not a BWR 6 and does not have this feature K1.03 Control rod drive system: BWR-6 DAEC is not a BWR 6 and does not have this feature K1.04 Rod position information system: BWR-6 DAEC is not a BWR 6 and does not have this feature K1.05 Rod action control system: BWR-6 DAEC is not a BWR 6 and does not have this feature K1.06 Rod gang drive system: BWR-6 DAEC is not a BWR 6 and does not have this feature K1.07 Rod interface system: BWR-6 DAEC is not a BWR 6 and does not have this feature K2.01 AC electrical power: BWR-6 DAEC is not a BWR 6 and does not have this feature K3.01 Control rod drive system: BWR-6 DAEC is not a BWR 6 and does not have this feature K3.02 Reactor startup: BWR-6 DAEC is not a BWR 6 and does not have this feature K3.03 Reactor shutdown: BWR-6 DAEC is not a BWR 6 and does not have this feature K3.04 Flux shaping: BWR-6 DAEC is not a BWR 6 and does not have this feature

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 5

Suppression Basis K4.01 Limiting the effects of a control Rod accident: BWR-6 DAEC is not a BWR 6 and does not have this feature K4.02 Bank position withdrawal sequence (BPWS): BWR-6 DAEC is not a BWR 6 and does not have this feature K4.03 Rod withdrawal block signals: BWR-6 DAEC is not a BWR 6 and does not have this feature K4.04 Rod insertion block signals: BWR-6 DAEC is not a BWR 6 and does not have this feature K4.05 Rod withdrawal limiter: BWR-6 DAEC is not a BWR 6 and does not have this feature K4.06 Rod pattern controller rod blocks: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.01 Rod pattern and program development:

BWR-6 DAEC is not a BWR 6 and does not have this feature K5.02 Rod pattern controller (RPC): BWR-6 DAEC is not a BWR 6 and does not have this feature K5.03 Rod groups: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.04 Rod sequences: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.05 Rod density: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.06 Target rod pattern: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.07 Low power alarm point: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.08 Transition zone: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.09 High power setpoints BWR-6 DAEC is not a BWR 6 and does not have this feature K5.10 Rod withdrawal limiter: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.11 Control rod motion: BWR-6 DAEC is not a BWR 6 and does not have this feature K5.12 Command word generation and sequencing (operator follow, scan and test): BWR-6 DAEC is not a BWR 6 and does not have this feature K5.13 Position indication probes: BWR-6 DAEC is not a BWR 6 and does not have this feature K6.01 First stage shell pressure or opening of a bypass valve(s): BWR-6 DAEC is not a BWR 6 and does not have this feature K6.02 Rod position signal: BWR-6 DAEC is not a BWR 6 and does not have this feature K6.03 AC electrical power: BWR-6 DAEC is not a BWR 6 and does not have this feature K6.04 IRM channel: BWR-6 DAEC is not a BWR 6 and does not have this feature K6.05 SRM channel: BWR-6 DAEC is not a BWR 6 and does not have this feature

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 6

Suppression Basis K6.06 APRM channel: BWR-6 DAEC is not a BWR 6 and does not have this feature 201006 Rod Worth Minimizer System (RWM)

A1.03 Latched group indication: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC A2.02 Loss of steam flow input: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

A2.06 Loss of reactor water level control input:

P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

A3.05 Latched group indication: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC A4.03 Latched group indication: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC K1.03 Reactor water level control (feed flow):

P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K1.04 Steam flow/reactor power: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K1.08 Reactor power (turbine first stage pressure): P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K4.07 Display of out of position control rods without rod blocks (transition zone): P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC K5.04 Transition zone: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC K5.07 Latch groups: P-Spec(Not-BWR6)

This is not a feature of the RWM at DAEC K6.02 Reactor water level control input: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

K6.05 Steam flow input: P-Spec(Not-BWR6)

The LPSP has been caused to enforce at all power levels at DAEC. This causes The RWM to enforce continuously without regard to power level.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 7

202001 Recirculation System A1.08 Recirculation FCV position: BWR-5, 6 Not a BWR 5 or 6 A2.25 Recirculation flow control valve lockup:

Plant-Specific Not a plant feature A3.06 Flow control valve position: BWR-5, 6 Not a BWR 5 or 6 A3.08 Pump downshift: BWR-5, 6 Not a BWR 5 or 6 K1.24 Isolation condenser: Plant-Specific DAEC has no ISO Condenser K2.04 Hydraulic power unit oil pumps: Plant-Specific DAEC has no Recirc Hydraulic Power Unit K3.12 Isolation condenser: Plant-Specific DAEC has no ISO Condenser K4.15 Slow speed pump start: Plant-Specific DAEC has Variable Speed pumps K4.17 Fast speed pump start: Plant-Specific DAEC has Variable Speed pumps K5.08 E/P converters: Plant-Specific DAEC does not has E/P Converters associated with the Recirc System K5.09 Hydraulically operated valves: Plant-Specific DAEC has no Recirc Hydraulic Power Unit 202002 Recirculation Flow Control System A1.08 Recirculation FCV position: BWR-5, 6 Not a BWR 5 or 6 A2.08 FCV lockup: BWR-5, 6 Not a BWR 5 or 6 A3.01 Flow control valve operation: BWR-5, 6 Not a BWR 5 or 6 A4.02 Hydraulic power unit: BWR-5, 6 Not a BWR 5 or 6 K1.12 Recirculation flow control valves: Plant-Specific Not a feature at DAEC K2.02 Hydraulic power unit: Plant-Specific Not a feature at DAEC K3.06 Recirculation flow control valve position:

Plant-Specific Not a feature at DAEC K4.04 Automatic load following: Plant-Specific Not a feature at DAEC K4.05 Limiting recirculation pump speed mismatch: Plant-Specific Not a feature at DAEC K4.08 Automatic flow control valve positioning:

BWR-5, 6 Not a BWR 5 or 6 K4.09 Minimum and maximum flow control valve position setpoints: BWR-5, 6 Not a BWR 5 or 6 K6.06 Reactor/turbine pressure regulating system: Plant-Specific Not a feature at DAEC K6.07 APRM signal input: BWR-5, 6 Not a BWR 5 or 6

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 8

204000 Reactor Water Cleanup System A2.02 Pressure control valve failure: LP-RWCU DAEC has a high pressure RWCU system A3.01 System pressure downstream of the pressure regulating valve: LP-RWCU DAEC has a high pressure RWCU system K1.16 CRD system: Plant-Specific There are no physical or logical connections between RWCU and CRD K4.08 Reducing reactor pressure upstream of low pressure piping: LP-RWCU DAEC has a high pressure RWCU system K5.06 Pressure controllers DAEC has a high pressure RWCU system K6.09 CRD hydraulics: Plant-Specific There are no physical or logical connections between RWCU and CRD 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

K1.09 Auxiliary steam supply: Plant-Specific DAEC does not use Auxiliary steam for SDC K1.11 Nitrogen: Plant-Specific SDC mode of RHR does not use the nitrogen supply system K1.12 Isolation condenser: Plant-Specific DAEC does not have an ISO condenser K4.01 High temperature isolation: Plant-Specific SDC mode does not have a high temperature isolation K6.06 Auxiliary steam supply: Plant-Specific DAEC does not use Auxiliary steam for SDC K6.07 Nitrogen: Plant-Specific SDC mode of RHR does not use the nitrogen supply system 206000 High Pressure Coolant Injection System A4.11 Turning gear: BWR-2, 3, 4(P-Spec)

DAEC HPCI does not have a turning gear K5.09 Testable check valve operation: BWR-2, 3, 4 DAEC HPCI does not have Testable Check Valves 207000 Isolation (Emergency) Condenser A1.01 Isolation condenser level: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A1.02 Shell side water temperature: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A1.03 Steam flow: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A1.04 Condensate flow: BWR-2, 3(P-Spec)

DAEC does not have an Isolation Condenser System.

A1.05 Reactor pressure: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A1.06 Reactor water level: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A1.07 Vent radiation level: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A1.08 Cooldown rate: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A1.09 Valve operations: BWR-2, 3 DAEC does not have an Isolation Condenser System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 9

A1.10 Primary side temperature: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.01 Tube bundle leak: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.02 High vent radiation: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.03 PCIS signal resulting in system isolation: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.04 Inadequate system flow: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.05 Insufficient shell side makeup flow:

BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.06 Valve openings: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.07 Valve closures: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A2.08 System initiation: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.01 Isolation condenser level: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.02 Reactor pressure: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.03 Reactor water level: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.04 Vent radiation levels: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.05 System lineup: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.06 Lights and alarms: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.07 Primary and shell side temperatures:

BWR-2, 3 DAEC does not have an Isolation Condenser System.

A3.08 System flow: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A4.01 Isolation condenser level: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A4.02 Steam line pressure: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A4.03 Primary and shell side temperatures:

BWR-2, 3 DAEC does not have an Isolation Condenser System.

A4.04 Vent line radiation levels: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A4.05 Major system valves: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A4.06 Shell side makeup valves: BWR-2, 3 DAEC does not have an Isolation Condenser System.

A4.07 Manually initiate the isolation condenser: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.01 Reactor vessel: BWR-2, 3 DAEC does not have an Isolation Condenser System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 10 K1.02 Reactor pressure: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.03 Reactor water level: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.04 Condensate transfer system: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.05 Demineralized water system: BWR-2, 3(P-Spec)

DAEC does not have an Isolation Condenser System.

K1.06 Fire protection/service water: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.07 LPCI: BWR-2, 3(P-Spec)

DAEC does not have an Isolation Condenser System.

K1.08 Recirculation system: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.09 Main steam system: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.10 Plant air systems: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K1.11 Primary containment isolation system:

BWR-2, 3 DAEC does not have an Isolation Condenser System.

K2.01 Motor operated valves: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K2.02 Initiation logic: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K3.01 Reactor pressure control during conditions in which the reactor vessel is isolated: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K3.02 Reactor water level (EPG's address the isolation condenser as a water source):

BWR-2, 3 DAEC does not have an Isolation Condenser System.

K4.01 Isolation of the system in the event of a line break: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K4.02 Automatic initiation: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K4.03 Filling of the system: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K4.04 Steam and condensate flow indication:

BWR-2, 3 DAEC does not have an Isolation Condenser System.

K4.05 Detection of a tube bundle leak: BWR-2, 3

DAEC does not have an Isolation Condenser System.

K4.06 Throttling of system flow: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K4.07 Manual operation of the system: BWR-2, 3

DAEC does not have an Isolation Condenser System.

K4.08 Protection against incomplete steam condensation (condensate outlet valve does not fully open): BWR-2,3,(P-Spec)

DAEC does not have an Isolation Condenser System.

K5.01 Flow measurement across an elbow using differential pressure: BWR-2, 3 DAEC does not have an Isolation Condenser System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 11 K5.02 Heat exchanger operation: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.03 Heat transfer: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.04 Latent heat of vaporization: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.05 Saturated steam: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.06 Saturated liquid: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.07 Temperature sensing: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.08 Level indicator operation: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.09 Cooldown rate: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K5.10 System venting: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K6.01 Demineralized water system: BWR-2, 3(P-Spec)

DAEC does not have an Isolation Condenser System.

K6.02 Fire protection/service water system:

BWR-2, 3 DAEC does not have an Isolation Condenser System.

K6.03 Condensate transfer system: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K6.04 Plant air systems: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K6.05 Primary containment isolation system:

BWR-2, 3 DAEC does not have an Isolation Condenser System.

K6.06 Recirculation system: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K6.07 AC power: BWR-2, 3 DAEC does not have an Isolation Condenser System.

K6.08 D.C. power: BWR-2, 3 DAEC does not have an Isolation Condenser System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 12 209001 Low Pressure Core Spray System A2.11 Loss of fire protection: BWR-1 Not a BWR 1 A4.06 Testable check valves There are no testable Check Valves A4.14 Containment level: BWR-1 Not a BWR 1 K1.04 condensate transfer system There is no logical or physical connection between Core Spray and Service Condensate K1.11 Drywell coolers: Plant-Specific There is no logical or physical connection between Core Spray and Drywell cooling K3.04 Component cooling water systems Core Spray provides no component cooling water K3.05 Drywell cooling: Plant-Specific There is no logical or physical connection between Core Spray and Drywell cooling K5.03 Testable check valve operation No testable check valves K5.06 Recirculation operation: Plant-Specific(BWR-1)

Not a BWR 1 K6.07 Pump seal cooler(s)

Core Spray has no seal coolers K6.09 Fire protection: BWR-1 Not a BWR 1 209002 High Pressure Core Spray System (HPCS)

A1.01 HPCS flow: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.02 HPCS pressure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.03 Reactor water level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.04 Reactor pressure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.05 Suppression pool water level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.06 Motor amps: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.07 Diesel loading: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.08 System lineup: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A1.09 Condensate storage tank level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.01 System initiation: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.02 Pump trips: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.03 Valve closures: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.04 AC electrical failure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.05 D.C. electrical failure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 13 A2.06 Core spray line break: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.07 Pump seal failure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.08 Inadequate system flow: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.09 Loss of room cooling: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.10 Valve openings: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.11 Low suppression pool level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.12 High suppression pool level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.13 Low condensate storage tank level BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.14 High suppression pool temperature:

BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A2.15 Clogged suppression pool suction strainers: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A3.01 Valve operation: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A3.02 Pump start: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A3.03 System pressure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A3.04 System flow: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A3.05 Reactor water level BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A3.06 Lights and alarms: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.01 HPCS pump: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.02 Suction valves: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.03 Injection valve: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.04 Minimum flow valve: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.05 Manual Initiation controls: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.06 Testable check valve: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.07 Line fill pump: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.08 Reactor water level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.09 Suppression pool level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 14 A4.10 Reactor pressure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.11 System flow: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.12 System pressure: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.13 Lights and alarms: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.14 Test return valve: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

A4.15 Initiation reset: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.01 Condensate transfer and storage system:

BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.02 Suppression Pool: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.03 Water leg (jockey) pump: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.04 HPCS diesel generator: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.05 Standby liquid control system: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K1.06 Suppression pool cleanup system: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.07 ECCS room coolers: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.08 Component cooling water systems:

BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.09 Leak detection: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.10 Suppression pool suction strainers:

BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.11 Adequate core cooling: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.12 Reactor vessel: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.13 Instrument nitrogen: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K1.14 Plant air systems: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K2.01 Pump electrical power: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K2.02 Valve electrical power: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K2.03 Initiation logic: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K3.01 Reactor water level: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K3.02 Standby liquid control system: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 15 K3.03 Adequate core cooling: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K4.01 Prevents water hammer: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K4.02 Prevents over filling reactor vessel:

Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K4.03 Prevents pump over heating: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K4.04 Testable check valve operation: BWR-5, 6

The DAEC does not have a High Pressure Core Spray System.

K4.05 Motor operated valve operation: BWR-5, 6

The DAEC does not have a High Pressure Core Spray System.

K4.06 Centrifugal pump operation: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K4.07 Override of reactor water level interlock:

Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K5.01 Indications of pump cavitation: BWR-5, 6

The DAEC does not have a High Pressure Core Spray System.

K5.02 Heat removal (transfer) mechanism:

BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K5.03 System venting: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K5.04 Adequate core cooling: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K6.01 Electrical power: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K6.02 Condensate storage tank water level:

BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K6.03 Component cooling water systems:

BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

K6.04 Suppression pool suction strainer: BWR-5, 6 The DAEC does not have a High Pressure Core Spray System.

211000 Standby Liquid Control System K1.10 HPCI: Plant-Specific At the DAEC, there are no physical or logical connections between the SBLC System and HPCI.

K6.04 Core spray system: Plant-Specific At the DAEC, a failure of the Core Spray System has no effect on the SBLC System.

K6.05 HPCI system: Plant-Specific At the DAEC, there are no physical or logical connections between the SBLC System and HPCI.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 16 212000 Reactor Protection System A1.04 RPS bus voltage: Plant-Specific At the DAEC, there are no dedicated indications for the RPS busses. RPS MG Set voltage and frequency are the indications for the RPS bus.

A1.05 RPS bus frequency: Plant-Specific At the DAEC, there are no dedicated indications for the RPS busses. RPS MG Set voltage and frequency are the indications for the RPS bus.

A4.03 Provide manual select rod insertion:

Plant-Specific Select Rod Insertion does not apply to the DAEC.

K4.06 Select rod insertion: Plant-Specific Select Rod Insertion does not apply to the DAEC.

214000 Rod Position Information System A3.04 RCIS: Plant-Specific The DAEC does not have a Rod Control and Information System.

A4.01 RCIS rod action control bypass switches The DAEC does not have a Rod Control and Information System.

K1.06 RCIS: Plant-Specific The DAEC does not have a Rod Control and Information System.

K3.04 RCIS: Plant-Specific The DAEC does not have a Rod Control and Information System.

K4.02 Thermocouple CRD Mechanism temperature is not associated with RPIS.

215003 Intermediate Range Monitor (IRM)

System K1.03 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

K1.05 Display control system: Plant-Specific The DAEC does not have a Display Control System.

K1.06 APRM SCRAM signals: Plant-Specific The DAEC no longer has an IRM Upscale or Inop/APRM Downscale Scram.

K3.03 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

215004 Source Range Monitor (SRM) System K1.03 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

K1.05 Display control system: Plant-Specific The DAEC does not have a Display Control System.

K3.03 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 17 215005 Average Power Range Monitor/Local Power Range Monitor System A1.06 Recirculation flow control valve position:

Plant-Specific The DAEC does not have Recirculation Flow Control valves.

K1.08 Display control system: Plant-Specific The DAEC does not have a Display Control System.

K1.09 Reactor recirculation system: BWR-5, 6 The DAEC has a BWR-4 design.

K1.11 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

K1.15 Redundant reactivity control system:

Plant-Specific The DAEC does not have a Redundant Reactivity Control System.

K3.02 Reactor recirculation system: BWR-5, 6 The DAEC has a BWR-4 design.

K3.04 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

216000 Nuclear Boiler Instrumentation K1.04 High pressure core spray system: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K1.11 MSIV leakage control system: Plant-Specific The DAEC has removed the MSIV-LCS System.

K1.15 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

K1.18 Analog trip system: Plant-Specific The DAEC does not have an Analog Trip System.

K2.01 Analog trip system: Plant-Specific The DAEC does not have an Analog Trip System.

K3.04 High pressure core spray system: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K3.11 MSIV leakage control system: Plant-Specific The DAEC has removed the MSIV-LCS System.

K3.15 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

K3.18 Analog trip system: Plant-Specific The DAEC does not have an Analog Trip System.

K3.28 Loose parts detection in the primary system: Plant-Specific The DAEC does not have Loose Parts Monitoring.

K5.05 Vessel vibration measurement (loose parts monitor)

The DAEC does not have Loose Parts Monitoring.

217000 Reactor Core Isolation Cooling System (RCIC)

K1.08 Line fill pump: Plant-Specific At the DAEC, RCIC has no keep fill pump.

K5.04 Testable check valve operation The DAEC has no testable check valves.

218000 Automatic Depressurization System A1.02 ADS valve acoustical monitor noise:

Plant-Specific DAEC has no acoustical monitors.

A3.03 ADS valve acoustical monitor noise:

Plant-Specific DAEC has no acoustical monitors.

A4.07 ADS valve acoustical monitor noise:

Plant-Specific DAEC has no acoustical monitors.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 18 219000 RHR/LPCI: Torus/Suppression Pool Cooling Mode A1.05 Condensate storage tank level: Plant-Specific At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

A1.10 Containment air temperature: Mark-III The DAEC has a MARK 1 containment.

A4.10 Condensate storage tank level: Plant-Specific At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

K1.02 Condensate storage tank At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

K6.05 Condensate storage tank: Plant-Specific At the DAEC, there are no physical or logical connections between RHR-Torus Cooling mode and the CSTs.

223001 Primary Containment System and Auxiliaries A1.03 Containment pressure: Mark-III The DAEC has a MARK 1 containment.

A1.04 Containment temperature: Mark-III The DAEC has a MARK 1 containment.

A1.12 Moisture concentration The DAEC does not monitor containment moisture content.

A2.06 High containment pressure: Mark-III The DAEC has a MARK 1 containment.

A2.13 High containment temperature: Mark-III The DAEC has a MARK 1 containment.

A2.14 Low containment to annulus pressure:

Mark-III The DAEC has a MARK 1 containment.

A3.07 Containment/drywell differential pressure: Mark-III DAEC has a MARK 1 Containment A4.01 Containment relief valves: Mark-III DAEC has a MARK 1 Containment A4.06 Containment pressure: Mark-III DAEC has a MARK 1 Containment A4.13 Hydrogen recombiners: Plant-Specific DAEC has a MARK 1 Containment A4.14 Hydrogen igniters: Plant-Specific DAEC has a MARK 1 Containment K1.05 Suppression pool makeup system: Mark-III The DAEC has a MARK 1 containment.

K1.13 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K2.04 Combustible gas mixing compressors:

Mark-III The DAEC has a MARK 1 containment.

K2.05 Hydrogen recombiners: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K2.06 Hydrogen igniters: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K2.08 Containment cooling air handling units:

Plant-Specific The DAEC does not have electric containment cooling units.

K2.10 Drywell chillers: Plant-Specific The DAEC does not have Drywell chillers.

K3.10 Containment/drywell moisture content The DAEC does not monitor containment moisture content.

K5.02 Guard pipe operation: Mark-III The DAEC has a MARK 1 containment.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 19 K5.04 Horizontal vent operation: Mark-III The DAEC has a MARK 1 containment.

K5.05 Hydrogen recombiner operation: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K5.06 Hydrogen igniter operation: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K5.15 Moisture content measurement: Plant-Specific The DAEC does not monitor containment moisture content.

K6.02 Containment cooling: Mark-III The DAEC has a MARK 1 containment.

K6.04 Combustible gas mixing: Plant-Specific The DAEC does not have a system for combustible gas mixing.

K6.05 Hydrogen recombiner: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K6.07 Hydrogen igniter system: Plant-Specific The DAEC does not have Hydrogen recombiners or igniters for the containment.

K6.10 Containment vacuum relief system:

Mark-III The DAEC has a MARK 1 containment.

223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off K1.05 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

K1.09 Reactor vessel head spray: Plant-Specific The DAEC has removed head spray piping.

K1.15 High pressure core spray : Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K1.21 Circulating water: Plant-Specific At the DAEC, there are no logical connections between PCIS and Circulating Water.

K3.13 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

K3.17 Reactor vessel head spray: Plant-Specific The DAEC has removed head spray piping.

K3.23 High pressure core spray : Plant-Specific The DAEC does not have a High Pressure Core Spray System.

K3.27 Circulating water At the DAEC, there are no logical connections between PCIS and Circulating Water.

226001 RHR/LPCI: Containment Spray System Mode A4.17 Manual initiation controls: BWR-6 The DAEC has a BWR-4 design.

A4.18 Automatic system initiation reset: BWR-6 The DAEC has a BWR-4 design.

K1.10 Containment (spray penetration): Mark-III The DAEC has a MARK 1 containment.

K4.09 Automatic containment spray initiation:

BWR-6 The DAEC has a BWR-4 design.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 20 233000 Fuel Pool Cooling and Clean-up A1.11 Suppression pool chemistry: BWR-6 The DAEC has a BWR-4 design.

A2.17 Fuel transfer tube drain tank high level/low level: BWR-6 The DAEC has a BWR-4 design.

A4.02 System lineups At the DAEC, Fuel Pool Cooling is controlled and mostly monitored from the Reactor Building.

K1.13 Suppression pool cleanup system: Plant-Specific At the DAEC, Suppression Pool Cleanup/Chemistry would be through the Condensate Demineralizers.

K3.07 Suppression pool chemistry: Plant-Specific At the DAEC, Suppression Pool Cleanup/Chemistry would be through the Condensate Demineralizers.

K4.08 Pool cooling during loss of coolant accident: BWR-6 The DAEC has a BWR-4 design.

234000 Fuel Handling Equipment K1.06 RC & IS: Plant-Specific The DAEC has no RC & IS System.

K1.07 Fuel transfer tube system: Mark-III The DAEC has a MARK 1 Containment.

K1.08 Fuel pools configuration: Mark-III The DAEC has a MARK 1 Containment.

K3.02 RC & IS: Plant-Specific The DAEC has no RC & IS System.

K4.05 Movement of fuel via fuel transfer tube:

Mark-III The DAEC has a MARK 1 Containment.

K6.03 RC & IS: Plant-Specific The DAEC has no RC & IS System.

K6.05 Upper fuel pool water inventory: Mark-III The DAEC has a MARK 1 Containment.

K6.06 Fuel transfer tube interlocks: Mark-III The DAEC has a MARK 1 Containment.

239001 Main and Reheat Steam System K1.04 Moisture separators The DAEC has Moisture Separator Reheaters (K1.05)

K1.13 Main steam isolation valve leakage control: Plant-Specific The DAEC has removed MSIV-LCS K1.14 Positive leakage control system: Plant Specific The DAEC has no positive leakage control system K1.20 Residual heat removal system: Plant-Specific At the DAEC, there are no physical or logical connections between the Main Steam System and the RHR System.

K1.21 Isolation condenser system: Plant-Specific The DAEC has no Isolation Condenser.

K2.02 Main steam line shutoff valves (guard valves): Plant-Specific The DAEC has no Main Steam Line Shutoff valves.

K3.03 Reactor feed pump turbines: Plant-Specific The DAEC has motor driven feedwater pumps not turbine driven.

K3.12 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

K3.14 Residual heat removal system: Plant-Specific At the DAEC, there are no physical or logical connections between the Main Steam System and the RHR System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 21 K4.03 Insures that steam released from a steam line break will not bypass suppression pool; BWR-6 The DAEC has a BWR-4 design.

K5.04 Definition and reason for steam blanketing of moisture separator reheater: Plant-Specific The DAEC no longer uses Steam Blanketing of MSRs.

K5.07 Hydraulic operated MSIV's The DAEC has pneumatically operated MSIVs.

K6.07 MSIV leakage control The DAEC has removed MSIV-LCS 239002 Relief/Safety Valves A1.02 Acoustical monitor noise: Plant-Specific The DAEC does not have an acoustical monitor for SRVs.

A3.04 Acoustical monitor noise: Plant-Specific The DAEC does not have an acoustical monitor for SRVs.

A4.03 Acoustical monitor noise: Plant-Specific The DAEC does not have an acoustical monitor for SRVs.

K1.05 Plant air systems: Plant-Specific At the DAEC, there are no physical or logical connections between the ADS/LLS Systems and Plant air systems.

K5.03 Acoustical monitoring: Plant-Specific The DAEC does not have an acoustical monitor for SRVs.

239003 MSIV Leakage Control System A1.01 Main steam line pressure: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A1.02 Heater operation: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A1.03 Dilution air flow: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A1.04 Status indicating lights and alarms:

BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A1.05 System lineup: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A1.06 MSIV leakage flow: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A1.07 Reactor building temperature: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A2.01 Inboard MSIV valve leakage: BWR-4, 5, 6

The DAEC has removed the MSIV Leakage Control System.

A2.02 Outboard MSIV valves leakage: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A2.03 Low dilution air flow (inboard and/or outboard): BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A2.04 Outboard system logic failure: BWR-4, 5, 6

The DAEC has removed the MSIV Leakage Control System.

A2.05 Inboard system logic failure: BWR-4, 5, 6

The DAEC has removed the MSIV Leakage Control System.

A2.06 Blower failure: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A2.07 Heater failure: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 22 A2.08 Motor operator valve failure(s): BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A2.09 Outboard main steamline high pressure:

BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A2.10 AC distribution power failures: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A2.11 High reactor pressure: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A2.12 MSIV valve failure to close: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A3.01 System logic initiation: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A3.02 Main steamline pressures: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A3.03 Dilution air flaws: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A3.04 MSIV leakage flows: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A3.05 Heater operation: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A3.06 System status lights and alarms: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A3.07 System lineups: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A3.08 Blower operation: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A3.09 Reactor building temperature: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.01 Manually initiate system operation:

BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.02 Surveillance testing: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.03 Main steamline pressures: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

A4.04 Dilution air flows: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.05 MSIV leakage flows: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.06 Heater operation: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.07 System status lights and alarms: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.08 System lineups: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

A4.09 System reset: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K1.01 Main steam system: BWR-4, 5, 6(P-Spec) The DAEC has removed the MSIV Leakage Control System.

K1.02 Standby gas treatment system: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 23 K1.03 Main steam line pressure instrumentation: BWR-4,5,6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K1.04 AC electrical distribution: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K1.05 Steam tunnel: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K1.06 Radwaste system: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K1.07 Floor drainage system: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K1.08 Nuclear boiler instrumentation: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K2.01 Motor operated valves: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K2.02 Leakage control system blowers: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K2.03 Leakage control system heaters: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K3.01 Radiation release to the environment:

BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K4.01 Performance of its safety function following a loss of offsite power: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K4.02 Performance of intended safety function following any single active component failure: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K4.03 The prevention of inadvertent system operation: BWR-4,5,6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K4.04 Surveillance for system operability:

BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

K4.05 Assurance that any MSIV leakage will pass through the system and into standby gas treatment prior to release to the atmosphere: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K4.06 The depressurization of main steam piping prior to routing leakage through system: BWR-4, 5, 6 The DAEC has removed the MSIV Leakage Control System.

K4.07 The reduction of MSIV leakage temperature: BWR-4,5,6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K4.08 Prevention of collected condensate in system bleed lines: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K4.09 The dilution of MSIV leakage: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K6.01 AC electrical distribution: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K6.02 Standby gas treatment system: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

K6.03 Nuclear boiler instrumentation: BWR-4, 5, 6(P-Spec)

The DAEC has removed the MSIV Leakage Control System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 24 241000 Reactor/Turbine Pressure Regulating System A1.26 Governor valve limit: Plant-Specific The DAEC does not have a governor valve for the Main Turbine.

A2.25 Loss of primary water system: Plant-Specific The DAEC does not have a primary water system.

A3.13 FW heater isolation: Plant-Specific The DAEC does not have a FW heater isolation feature.

A3.14 Grid load following: Plant-Specific Grid Load Following is not applicable to the DAEC.

K1.34 EGC system: Plant-Specific The DAEC does not have an EGC System.

K1.35 Low pressure stop and control valves:

Plant-Specific The DAEC does not have low pressure stop and control valves.

K1.36 Primary water system: Plant-Specific The DAEC does not have a primary water system.

K3.28 Low pressure stop and control valves:

Plant-Specific The DAEC does not have low pressure stop and control valves.

K3.30 EGC: Plant-Specific The DAEC does not have an EGC System.

K4.08 Feedwater heater isolation: Plant-Specific The DAEC does not have FW Heater isolation feature.

K4.11 Load following: Plant-Specific Grid Load Following is not applicable to the DAEC.

K4.12 Recirculation flow control: Plant-Specific There are no design features or interlocks in the EHC System that directly affect Recirculation flow control.

K5.07 Unitized actuator operation: Fermi-Only The DAEC does not have a unitized actuator.

K6.18 Low pressure stop and control valves:

Plant-Specific The DAEC does not have low pressure stop and control valves.

K6.19 Primary water system: Plant-Specific The DAEC does not have a primary water system.

245000 Main Turbine Generator and Auxiliary Systems K2.03 Amplidyne: Plant-Specific The DAEC does not have an amplidyne for the Main Generator.

K2.05 Air seal oil pumps: Plant-Specific The DAEC does not have air seal oil pumps.

256000 Reactor Condensate System A2.17 Feedwater heater string trip: Plant-Specific At the DAEC, there are no trips on feedwater heater strings.

A3.09 Feedwater heater drain tank level:

Plant-Specific At the DAEC, there is no feedwater heater drain tank.

A4.14 Feedwater heater drain tank level:

Plant-Specific At the DAEC, there is no feedwater heater drain tank.

K1.04 RCIC: Plant-Specific At the DAEC, there are no physical or logical connections between the Condensate System and the RCIC System.

K1.09 Offgas condenser: Plant-Specific At the DAEC, there are no physical or logical connections between the Condensate System and the Offgas System.

K1.12 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 25 K1.15 HPCS: Plant-Specific The DAEC has no High Pressure Core Spray System.

K1.21 Steam seal evaporator: Plant-Specific The DAEC has no Steam Seal Evaporator.

K1.23 Auxiliary steam system: Plant-Specific The DAEC has no Auxiliary Steam System.

K3.07 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

K3.12 HPCS: Plant-Specific The DAEC has no High Pressure Core Spray System.

K4.01 Condensate and/or booster pump auto start: Plant-Specific At the DAEC, there are no automatic Condensate Pump starts and the DAEC has no condensate booster pumps.

K4.05 Maintenance of 100% system flow if a feedwater string isolates: Plant-Specific At the DAEC, there are no feedwater string isolations.

259001 Reactor Feedwater System A1.04 RFP turbine speed: Turbine-Driven-Only The DAEC has motor driven feedwater pumps not turbine driven.

A1.05 RFP turbine control valve position:

Turbine-Driven-Only The DAEC has motor driven feedwater pumps not turbine driven.

A2.09 TDRFP steam inlet pressure flow: Plant-Specific The DAEC has motor driven feedwater pumps not turbine driven.

A3.01 RFP auto start: Plant-Specific The DAEC has no automatic start feature for the feedwater pumps.

A3.08 Turbine speed: TDRFP'S-Only The DAEC has motor driven feedwater pumps not turbine driven.

A3.11 Reactor feed pump runbacks: Plant-Specific The DAEC has no runback feature for the feedwater pumps.

K1.12 RFP turbine seal steam system:

TDRFP's-Only The DAEC has motor driven feedwater pumps not turbine driven.

K1.15 RHR: Plant-Specific At the DAEC, there are no physical or logical connections between the Feedwater System and the RHR System.

K1.18 Fire protection system (emergency cooling): Plant-Specific At the DAEC, there is no physical or logical connections between the Feedwater System and the Fire Protection System used as emergency cooling.

K1.19 Redundant reactivity control system:

Plant-Specific At the DAEC, there is no Redundant Reactivity Control System associated with the Feedwater System.

K1.20 Main steam system: TDRFPs-Only The DAEC has motor driven feedwater pumps not turbine driven.

K3.10 HPCS: Plant-Specific The DAEC has no High Pressure Core Spray System.

K3.11 RHR: Plant-Specific At the DAEC, there are no physical or logical connections between the Feedwater System and the RHR System.

K4.01 Auto start of the RFP's: Plant-Specific The DAEC has no automatic start feature for the feedwater pumps.

K4.08 RFP turbine seals: TDRFP's-Only The DAEC has motor driven feedwater pumps not turbine driven.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 26 K4.10 Feed pump runbacks: Plant-Specific The DAEC has no runback feature for the feedwater pumps.

K5.03 Turbine operation: TDRFP's-Only The DAEC has motor driven feedwater pumps not turbine driven.

K6.10 RFP turbine seal system: TDRFP's-Only The DAEC has motor driven feedwater pumps not turbine driven.

K6.11 Main steam: TDRFP's-Only The DAEC has motor driven feedwater pumps not turbine driven.

K6.13 Redundant reactivity control: Plant-Specific At the DAEC, there is no Redundant Reactivity Control System associated with the Feedwater System.

259002 Reactor Water Level Control System A1.06 Feedwater string(s) selected for FWCI:

FWCI The DAEC does not have a FWCI/HPCI System.

A1.07 TDRFP speed: TDRFP The DAEC has motor driven feedwater pumps not turbine driven.

A2.08 Receipt of an ECCS initiation signal:

FWCI The DAEC does not have a FWCI/HPCI System.

A2.09 FWCI system failure alarm: FWCI The DAEC does not have a FWCI/HPCI System.

A3.01 Runout flow control: Plant-Specific At the DAEC, feed pump runout conditions are controlled manually by the operator.

A3.06 Reactor water level setpoint setdown following a reactor scram: Plant-Specific DAEC does not have automatic setpoint setdown A3.08 FWCI system initiation: FWCI The DAEC does not have a FWCI/HPCI System.

A3.09 Transfer of system from flow control to level control mode: FWCI The DAEC does not have a FWCI/HPCI System.

A3.10 TDRFP lockup: TDRFP The DAEC has motor driven feedwater pumps not turbine driven.

A4.05 Runout flow control reset controls:

Plant-Specific At the DAEC, feed pump runout conditions are controlled manually by the operator.

A4.08 Manually initiate FWCI: FWCI The DAEC does not have a FWCI/HPCI System.

A4.09 TDRFP lockout reset: TDRFP The DAEC has motor driven feedwater pumps not turbine driven.

K1.07 Rod worth Minimizer: Plant-Specific At the DAEC, there are no physical or logical connections between the FWLC System and Rod Worth Minimizer.

K1.09 P sat/T sat (compensation)

At the DAEC, FWLC does not use Psat/Tsat compensation.

K1.10 Emergency generator(s): FWCI/HPCI The DAEC does not have a FWCI/HPCI System.

K1.11 Drywell pressure: FWCI/HPCI The DAEC does not have a FWCI/HPCI System.

K1.12 Emergency condensate transfer pump:

FWCI/HPCI The DAEC does not have a FWCI/HPCI System.

K2.02 Feedwater coolant injection (FWCI) initiation logic: FWCI/HPCI The DAEC does not have a FWCI/HPCI System.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 27 K3.03 Rod worth Minimizer: Plant-Specific At the DAEC, there are no physical or logical connections between the FWLC System and Rod Worth Minimizer.

K4.02 Bypassing of the RWM: Plant-Specific At the DAEC, there are no physical or logical connections between the FWLC System and Rod Worth Minimizer.

K4.03 Reactor feed pump runout protection:

MDFP At the DAEC, feed pump runout conditions are controlled manually by the operator.

K4.05 P sat/T sat (compensation)

At the DAEC, FWLC does not use Psat/Tsat compensation.

K4.07 TDRFP 20% power interlock: TDRFP The DAEC has motor driven feedwater pumps not turbine driven.

K4.08 TDRFP speed control: TDRFP The DAEC has motor driven feedwater pumps not turbine driven.

K4.11 DP control: Plant-Specific At the DAEC, FWLC is not designed to control dP.

K4.15 Automatic initiation of the feedwater system upon receipt of an ECCS initiation signal: FWCI/HPCI The DAEC does not have a FWCI/HPCI System.

K4.16 Dedication of feedwater string(s) to ECCS: FWCI/HPCI The DAEC does not have a FWCI/HPCI System.

K5.01 GEMAC/Foxboro/Bailey controller operation: Plant-Specific At the DAEC, FWLC uses MOORE controllers.

K5.07 Turbine speed control mechanisms:

TDRFP The DAEC has motor driven feedwater pumps not turbine driven.

K5.08 Heat removal mechanisms: FWCI The DAEC does not have a FWCI/HPCI System.

K5.09 Adequate core cooling: FWCI The DAEC does not have a FWCI/HPCI System.

K6.06 Reactor pressure/temperature input (for water level input compensation)

At the DAEC, FWLC does not use Psat/Tsat compensation.

K6.07 Drywell pressure input: FWCI The DAEC does not have a FWCI/HPCI System.

K6.08 Loss of dP across startup level control bypass valve: Plant-Specific At the DAEC, FWLC is not designed to control dP.

262002 Uninterruptible Power Supply (A.C./D.C.)

A1.02 Motor generator outputs The DAEC uses a static inverter.

A2.04 Abnormal battery operation: BWR-1 The DAEC has a BWR-4 design.

K1.02 RFPT control: Plant-Specific The DAEC does not have RFPT control.

K1.08 Containment isolation system: Plant-Specific At the DAEC, PCIS is powered from RPS.

K1.09 Drywell ventilation control: Plant-Specific At the DAEC, Drywell ventilation is not affected by Uninterruptible AC power.

K1.10 Fire protection system: Plant-Specific At the DAEC, the Fire Protection System is unaffected by the Uninterruptible AC System.

K1.12 Generator hydrogen and stator cooling water controls: Plant-Specific At the DAEC, the Hydrogen and Stator Cooling controls are unaffected by Uninterruptible AC power.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 28 K1.14 Main steam line radiation monitors:

Plant-Specific At the DAEC, the Main Steam Line Rad Monitors are unaffected by Uninterruptible AC power.

K1.16 MSIV's: Plant-Specific At the DAEC, the MSIVs are unaffected by Uninterruptible AC power.

K1.17 Scram solenoid valves: Plant-Specific At the DAEC, the scram solenoids are unaffected by Uninterruptible AC power.

K3.03 RFPT speed: Plant-Specific The DAEC does not have RFPT control.

K3.04 Fire protection system: Plant-Specific At the DAEC, the Fire Protection System is unaffected by Uninterruptible AC power.

K3.09 Drywell ventilation control: Plant-Specific At the DAEC, the Drywell ventilation control is unaffected by Uninterruptible AC power.

K3.10 Containment isolation: Plant-Specific At the DAEC, the Containment Isolations are unaffected by Uninterruptible AC power.

K3.11 MSIV's: Plant-Specific At the DAEC, the MSIVs are unaffected by Uninterruptible AC power.

K5.02 General principles of motor generator operation: Plant-Specific The DAEC uses a static inverter.

K5.03 General principles of inertia fly wheel operation: Plant-Specific The DAEC uses a static inverter.

263000 D.C. Electrical Distribution A4.02 Battery voltage indicator: Plant-Specific At the DAEC, operators do not maintain the batteries, and there are no controls or indications in the control room.

A4.03 Battery discharge rate: Plant-Specific At the DAEC, operators do not maintain the batteries, and there are no controls or indications in the control room.

A4.04 Ground detection circuit: Plant-Specific At the DAEC, operators do not maintain the batteries, and there are no controls or indications in the control room.

264000 Emergency Generators (Diesel/Jet)

A1.07 Gas generator temperature: Plant-Specific The DAEC does not have gas generators.

A1.08 Gas generator speed: Plant-Specific The DAEC does not have gas generators.

K2.03 Turning gear (jet engine): Plant-Specific The DAEC does not have jet engines.

K2.04 Ignition system (jet engine): Plant-Specific The DAEC does not have jet engines.

K6.04 Turning gear (jet engine): Plant-Specific The DAEC does not have jet engines.

K6.05 Ignition system (jet engine): Plant-Specific The DAEC does not have jet engines.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 29 268000 Radwaste K1.10 Auxiliary steam: Plant-Specific The DAEC does not have an Auxiliary Steam System.

271000 Offgas System K6.13 Plant exhaust: BWR-1 The DAEC has a BWR-4 design.

272000 Radiation Monitoring System A3.02 Offgas system isolation indications At the DAEC, the Offgas System no longer isolates on high radiation.

A3.05 Refuel floor overhead crane operation interrupt: Plant-Specific At the DAEC, there is no interrupt/interlock of the Reactor Building crane due to high radiation.

A3.11 Circulating water system blowdown isolations: Plant-Specific The DAEC does not monitor the Circ Water System for radiation and there is no isolation of the blowdown Valve due to radiation.

K1.07 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

K1.11 Reactor building overhead crane; Plant-Specific At the DAEC, there is no interrupt/interlock of the Reactor Building crane due to high radiation.

K1.15 Filter building: Plant-Specific The DAEC does not have a Filter Building.

K1.18 Primary containment/containment building: Plant-Specific The DAEC has a Drywell. (K1.19)

K1.20 Auxiliary building: Plant-Specific The DAEC does not have an Auxiliary Building.

K1.22 Fuel building: mark-III The DAEC has a MARK 1 Containment and does not have a Fuel Building.

K3.07 Reactor building overhead crane operation: Plant-Specific At the DAEC, there is no interrupt/interlock of the Reactor Building crane due to high radiation.

K3.08 Auxiliary building ventilation: Plant-Specific The DAEC does not have an Auxiliary Building.

286000 Fire Protection System A2.12 Low diesel fuel supply: Plant-Specific The DAEC has no procedure for transferring diesel fuel to the diesel fire pump.

K1.02 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

K1.08 Intake canals: Plant-Specific The DAEC has no Intake canals.

K1.11 Screen wash system: Plant-Specific At the DAEC, there is no physical or logical connections between the Fire Protection System and the screen wash system.

K6.04 Diesel fuel transfer system: Plant-Specific The DAEC has no procedure for transferring diesel fuel to the diesel fire pump.

K6.05 Screen wash system: Plant-Specific At the DAEC, there is no physical or logical connections between the Fire Protection System and the screen wash system.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 30 290001 Secondary Containment A1.02 High area temperature: BWR-6 The DAEC has a BWR-4 design and does not have an Auxiliary Building.

A2.06 Auxiliary building isolation: BWR-6 The DAEC has a BWR-4 design and does not have an Auxiliary Building.

A4.03 Auxiliary building differential pressure:

Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

A4.04 Auxiliary building area temperature:

Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

A4.05 Fuel building differential pressure:

Plant-Specific The DAEC does not have a Fuel Building.

A4.06 Fuel building area temperature: Plant-Specific The DAEC does not have a Fuel Building.

A4.07 Radwaste building differential pressure:

Plant-Specific At the DAEC, Radwaste building dP and area temperature are not monitored in the Control Room.

A4.08 Radwaste building area temperature:

Plant-Specific At the DAEC, Radwaste building dP and area temperature are not monitored in the Control Room.

K1.05 Auxiliary building ventilation: Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

K1.06 Auxiliary building isolation: BWR-6 The DAEC has a BWR-4 design and does not have an Auxiliary Building.

K4.04 Auxiliary building isolation: BWR-6 The DAEC has a BWR-4 design and does not have an Auxiliary Building.

K5.02 Flow measurement: BWR-3 The DAEC has a BWR-4 design.

K6.05 Auxiliary building ventilation: Plant-Specific The DAEC has a BWR-4 design and does not have an Auxiliary Building.

K6.07 Auxiliary boiler system: BWR-3, 4 At the DAEC, a loss of the Aux Boiler does not effect Secondary Containment.

K6.09 AC power: BWR-6 The DAEC has a BWR-4 design.

290002 Reactor Vessel Internals K1.06 HPCS: Plant-Specific The DAEC has no High Pressure Core Spray System.

K1.07 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

K1.18 Lost parts monitoring: Plant-Specific The DAEC has no lost parts monitoring K6.12 Isolation condenser: Plant-Specific The DAEC has no Isolation Condenser.

K6.16 Loss parts monitoring The DAEC has no lost parts monitoring K6.19 HPCS: Plant-Specific(BWR-5&6)

The DAEC has no High Pressure Core Spray System.

290003 Control Room HVAC K1.02 Chlorine ammonia detectors: Plant-Specific The DAEC does not use Chorine Ammonia detectors.

K1.04 Nuclear steam supply shut off system (NSSSS/PCIS): Plant-Specific At the DAEC, there are no logical connections between Control Building HVAC and NSSSS/PCIS.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 31 295001 Partial or Complete Loss of Forced Core Flow Circulation AA1.04 Rod control and information system:

BWR-5&6 The DAEC does not have a Rod Control and Information System.

AA1.08 Standby liquid control: BWR-1 The DAEC has a BWR-4 design.

AK2.08 Standby liquid control: BWR-1 The DAEC has a BWR-4 design.

295002 Loss of Main Condenser Vacuum AK3.03 Reactor feed pump turbine trip: Plant-Specific The DAEC does not have turbine driven feedwater pumps.

AK3.08 Recirculation system run-backs: Plant-Specific The DAEC does not have Recirculation System runbacks based on Main Condenser vacuum.

295003 Partial or Complete Loss of AC Power AK2.05 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

AK3.07 Initiation of isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

295005 Main Turbine Generator Trip AK2.06 Seal steam evaporator: Plant-Specific The DAEC does not have a seal steam evaporator.

AK2.09 Feedwater-HPCI: BWR-2 The DAEC has a BWR-4 design.

AK3.08 Feedwater-HPCI actuation: BWR-2 The DAEC has a BWR-4 design.

295006 SCRAM AK3.05 Direct turbine generator trip: Plant-Specific At the DAEC, there is no direct turbine trip caused by a scram signal.

295007 High Reactor Pressure AA1.01 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

AK3.01 Isolation condenser operation: Plant-Specific The DAEC does not have an Isolation Condenser.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 32 295008 High Reactor Water Level AA1.06 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

AK1.04 Containment integrity: Alis-Chalmers This is not applicable to the DAEC.

AK2.01 RPS: Plant-Specific The DAEC does not have a reactor scram signal due to High Reactor Water Level.

AK2.04 PCIS/NSSSS: Plant-Specific The DAEC does not have PCIS Isolations due to High Reactor Water Level.

AK2.07 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

AK3.02 Reactor SCRAM: Plant-Specific The DAEC does not have a reactor scram signal of High Reactor Water Level.

AK3.03 PCIS/NSSSS initiation: Plant-Specific The DAEC does not have PCIS Isolations due to High Reactor Water Level.

AK3.06 RCIC turbine trip: Plant-Specific The DAEC RCIC System Steam Supply Valve closes on High Reactor Water Level. (AK3.08)

AK3.07 HPCS isolation: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

AK3.09 HPCS injection valve closure: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

295009 Low Reactor Water Level AK3.02 Reactor feed pump runout flow control:

Plant-Specific The DAEC does not have a Feed pump runout control system.

295010 High Drywell Pressure AA2.04 Drywell humidity: Plant-Specific The DAEC does not monitor Drywell humidity.

AA2.05 Drywell air cooler drain flow: BWR-6 The DAEC has a BWR-4 design.

AK1.02 Submergence vent control: Mark-III The DAEC has a MARK 1 Containment.

AK2.03 Drywell/containment differential pressure: Mark-III The DAEC has a MARK 1 Containment.

295011 High Containment Temperature (Mark III Containment Only)

AA1.01 Containment ventilation/cooling system:

Mark-III The DAEC has a MARK I containment.

AA2.01 Containment temperature: Mark-III The DAEC has a MARK I containment.

AA2.02 Containment pressure: Mark-III The DAEC has a MARK I containment.

AA2.03 Containment humidity: Mark-III The DAEC has a MARK I containment.

AK1.01 Containment pressure: Mark-III The DAEC has a MARK I containment.

AK2.01 Containment ventilation/cooling: Mark-III The DAEC has a MARK I containment.

AK3.01 Increased containment cooling: Mark-III The DAEC has a MARK I containment.

295012 High Drywell Temperature AA2.03 Drywell humidity: Plant-Specific The DAEC does not monitor Drywell humidity.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 33 295014 Inadvertent Reactivity Addition AA1.04 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

AK2.09 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

295015 Incomplete SCRAM AA1.04 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

AA1.06 RSCS: Plant-Specific At the DAEC, RSCS has been decommissioned and only provides back lighting.

AK2.03 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

AK2.06 RSCS: Plant-Specific At the DAEC, RSCS has been decommissioned and only provides back lighting.

295016 Control Room Abandonment AA1.09 Isolation/emergency condenser(s): Plant-Specific The DAEC does not have an Isolation Condenser.

295017 High Off-Site Release Rate AA1.08 MSIV leakage control: Plant-Specific The DAEC has removed the MSIV-LCS System.

AK2.11 MSIV leakage control: Plant-Specific The DAEC has removed the MSIV-LCS System.

295019 Partial or Complete Loss of Instrument Air AK2.13 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

295020 Inadvertent Containment Isolation AK2.05 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

295021 Loss of Shutdown Cooling AK2.06 Reactor vessel head spray: Plant-Specific The DAEC has removed the Head Spray piping.

295022 Loss of CRD Pumps AA1.04 Reactor water cleanup system: Plant-Specific The loss of a CRD pump does not effect RWCU.

AK2.05 Reactor water cleanup: Plant-Specific The loss of a CRD pump does not effect RWCU.

AK2.06 Shared components with other units:

Plant-Specific Single Unit Site.

295023 Refueling Accidents AA1.05 Fuel transfer system: Plant-Specific The DAEC does not have a Fuel Transfer System.

AA1.08 Containment building ventilation: Mark-III The DAEC has a MARK 1 Containment.

AK2.06 Containment ventilation: Mark-III The DAEC has a MARK 1 Containment.

AK3.05 Initiation of SLC/shut-down cooling:

Plant-Specific(BWR-1)

The DAEC has a BWR-4 design.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 34 295024 High Drywell Pressure EA1.02 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EA1.18 Containment ventilation system: Mark-III The DAEC has a MARK 1 Containment.

EA2.07 Containment radiation levels: Mark-III The DAEC has a MARK 1 Containment.

EA2.09 Containment pressure: Mark-III The DAEC has a MARK 1 Containment.

EA2.10 Containment temperature: Mark-III The DAEC has a MARK 1 Containment.

EK1.02 Containment building integrity: Mark-III The DAEC has a MARK 1 Containment.

EK2.02 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EK2.14 Containment pressure: Mark-III The DAEC has a MARK 1 Containment.

EK2.17 Auxiliary building isolation logic: Plant-Specific The DAEC does not have an Auxiliary Building.

EK3.03 Containment venting: Mark-III The DAEC has a MARK 1 Containment.

EK3.09 Auxiliary building isolation: Plant-Specific.

The DAEC does not have an Auxiliary Building.

295025 High Reactor Pressure EA1.06 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

EA1.08 RRCS: Plant-Specific The DAEC does not have a RRCS System.

EK2.02 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

EK2.03 RRCS: Plant-Specific The DAEC does not have a RRCS System.

EK3.04 Isolation condenser initiation: Plant-Specific The DAEC does not have an Isolation Condenser.

EK3.07 RRCS initiation: Plant-Specific The DAEC does not have a RRCS System.

295026 Suppression Pool High Water Temperature EK2.05 Containment pressure: Mark-III The DAEC has a MARK 1 Containment.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 35 295027 High Containment Temperature (Mark III Containment Only)

EA1.01 Containment spray: Plant-Specific The DAEC has a MARK I containment.

EA1.02 Containment ventilation/cooling: Mark-III The DAEC has a MARK I containment.

EA1.03 Emergency depressurization: Mark-III The DAEC has a MARK I containment.

EA2.01 Containment temperature: Mark-III The DAEC has a MARK I containment.

EA2.02 Containment pressure: Mark-III The DAEC has a MARK I containment.

EA2.03 Reactor pressure: Mark-III The DAEC has a MARK I containment.

EA2.04 Containment radiation levels: Mark-III The DAEC has a MARK I containment.

EK1.01 Equipment environmental qualifications: Mark-III The DAEC has a MARK I containment.

EK1.02 Reactor water level measurement:

Mark-III The DAEC has a MARK I containment.

EK1.03 Containment integrity: Mark-III The DAEC has a MARK I containment.

EK2.01 Containment spray: Plant-Specific The DAEC has a MARK I containment.

EK2.02 Components internal to the containment: Mark-III The DAEC has a MARK I containment.

EK2.03 Containment ventilation/cooling: Mark-III The DAEC has a MARK I containment.

EK2.04 SPDS/ERIS/CRIDS/GDS: Mark-III The DAEC has a MARK I containment.

EK3.01 Emergency depressurization: Mark-III The DAEC has a MARK I containment.

EK3.02 Containment spray: Plant-Specific The DAEC has a MARK I containment.

EK3.03 Reactor SCRAM: Mark-III The DAEC has a MARK I containment.

295029 High Suppression Pool Water Level EA1.02 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EK2.03 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

295030 Low Suppression Pool Water Level EA1.03 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EA1.04 Suppression pool make-up system:

Mark-III The DAEC has a MARK 1 Containment.

EK2.05 HPCS: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EK2.06 Suppression pool make-up: Mark-III The DAEC has a MARK 1 Containment.

EK3.04 HPCS operation: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EK3.05 Suppression pool make-up operation:

Mark-III The DAEC has a MARK 1 Containment.

Complete System K/A Suppression Basis E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 final KA Suppression Bases extended.doc 36 295031 Reactor Low Water Level EA1.04 High pressure core spray: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EA1.09 Isolation condenser: Plant-Specific The DAEC does not have an Isolation Condenser.

EK2.07 High pressure core spray: Plant-Specific The DAEC does not have a High Pressure Core Spray System.

EK2.10 Redundant reactivity control: Plant-Specific The DAEC does not have a Redundant Reactivity Control System.

295034 Secondary Containment Ventilation High Radiation EA1.05 Fuel building ventilation: Plant-Specific The DAEC has a MARK 1 Containment and does not have a Fuel Building.

EK2.05 Fuel building ventilation: Mark-III The DAEC has a MARK 1 Containment and does not have a Fuel Building.

EK3.04 Fuel building ventilation: Plant-Specific The DAEC has a MARK 1 Containment and does not have a Fuel Building.

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1.02 RRCS: Plant-Specific The DAEC does not have a RRCS System.

EA1.08 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

EK2.02 RRCS: Plant-Specific The DAEC does not have a RRCS System.

EK2.12 Rod control and information system:

Plant-Specific The DAEC does not have a Rod Control and Information System.

295038 High Off-Site Release Rate EK2.11 MSIV leakage control: Plant-Specific The DAEC has removed the MSIV-LCS System.

EK2.12 Feedwater leakage control: BWR-6 The DAEC has a BWR-4 design.

300000 Instrument Air System (IAS)

K1.03 Containment air At the DAEC, Containment pneumatics is supplied with nitrogen, including all MSIVs.

K1.05 Main Steam Isolation Valve air At the DAEC, Containment pneumatics is supplied with nitrogen, including all MSIVs.

K3.01 Containment air system At the DAEC, Containment pneumatics is supplied with nitrogen, including all MSIVs.

K3.03 Cross-tied units The DAEC is a single unit site 500000 High Containment Hydrogen Concentration EK2.05 Hydrogen and oxygen recombiners The DAEC does not have hydrogen and oxygen recombiners associated with Containment.

EK3.03 Operation of hydrogen and oxygen recombiners The DAEC does not have hydrogen and oxygen recombiners associated with Containment.

600000 Plant Fire On Site AA2.10 Time limit of long-term-breathing air system for control room The DAEC has no long term breathing air system for the control room.

JPM MAP E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 JPM MAP 75 day.doc 1 6 Safety Function NRC EXAM RO/

SRO-I NRC EXAM SRO AUDIT RO/SRO-I AUDIT SRO PRE-AUDIT RO/

SRO-I PREAUDIT SRO 1

Reactivity Control SLO/ Recirc power reduction/ Recirc MG lube oil high temperature alarm/Recirc pump trip/Scram 202002-xx SLO/ Recirc power reduction/ Recirc MG lube oil high temperature alarm/Recirc pump trip/Scram 202002-xx Perform required actions for single loop to two loop transfer 202001-02 Perform required actions for single loop to two loop transfer 202001-02 Take local control of the MG set scoop tube 202002-05 Take local control of the MG set scoop tube 202002-05 2

Reactor Water Inventory Control Rapid Restart of the RPF following a reactor scram Note: Used for 2000 NRC exam 259001-11 Recover RWCU following a system isolation 204000-05 Vent the core spray system for startup 209001-01 Vent the core spray system for startup 209001-01 3

Reactor Pressure Control Install EOP Defeat 5 to depressurize the reactor Note: Used for 2000 NRC exam 239001-02 Rapid depressurization with bypass (faulted) 241000-02 Rapid depressurization with bypass (faulted) 241000-02 Isolate Main Steam Line Loads in preparation for RPV Flooding.

239001-01 4

Heat Removal from Core Perform required actions for HPCI rapid start for level control.

(ESF) 206000-15 Perform required actions for HPCI rapid start for level control.

(ESF) 206000-15 Perform in-plant actions for ECCS suction strainer blockage (SEP 305) 203000-03 Perform required actions for manual start up of RCIC system for RPV level control with an electrical overspeed trip and reset (alternate path) 217000-15 Perform required actions for manual start up of RCIC system for RPV level control with an electrical overspeed trip and reset (alternate path) 217000-15 5

Containment Integrity Containment venting irrespective of radioactive release (alternate path hard pipe vent) 295024-06 Initiate torus cooling with LPCI initiation signal present 219000-01 Lower torus water level after HPCI and RCIC testing 219000-03

JPM MAP E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 JPM MAP 75 day.doc 2 6 Safety Function NRC EXAM RO/

SRO-I NRC EXAM SRO AUDIT RO/SRO-I AUDIT SRO PRE-AUDIT RO/

SRO-I PREAUDIT SRO 6

Electrical SBDG STP shutdown from fully loaded/Bus overcurrent alarm/manual rapid shutdown of SBDG and trip 264000-xx SBDG STP shutdown from fully loaded/Bus overcurrent alarm/manual rapid shutdown of SBDG and trip 264000-xx Open the Main Generator Output Breakers Locally 295004-10 Open the Main Generator Output Breakers Locally 295004-10 Placing the main generator on the grid 262001-05 Placing the main generator on the grid 262001-05 7

Instrumentation Perform required actions for repeated manual scram 212000-10 Bypass a rod using NUMAC RWM 201006-01 Restoration of a flow unit / Respond to APRM upscale and remove a flow unit from service 215005-02 8

Plant Service Systems Manually Initiate CARDOX (AOP)

Note: Used for 2000 NRC exam 286000-03 Manually Initiate CARDOX (AOP)

Note: Used for 2000 NRC exam 286000-03 Alternating RBCCW pumps w/ failure of RBCCW pumps (faulted) 400000-01 Alternating RBCCW pumps w/ failure of RBCCW pumps (faulted) 400000-01 Manual start of the diesel fire pump 1P-49 (alternate path) 286000-02 9

Radioactivity Release Reset a control building chiller after trip 290003-01 Reset a control building chiller after trip 290003-01 Perform required actions for SBGT overheating (faulted) 261000-20 Manual initiation of SBGT and secondary containment isolation (modified - alternate path) 261000-07 Manual initiation of SBGT and secondary containment isolation (modified - alternate path) 261000-07 6

Electrical (NRC)

AOP for Control Room Abandonment (Audit) 7 Instrumentation (Pre-Audit)

Shift 250 VDC battery chargers 263000-01 Perform required actions for control to the remote shutdown panel (alternate path/short version) 295016-21 Perform required actions for control to the remote shutdown panel (alternate path/short version) 295016-21 Remove RPS Fuses 212000-06

JPM MAP E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\2002 JPM MAP 75 day.doc 3 6 Safety Function NRC EXAM RO NRC EXAM SRO AUDIT RO AUDIT SRO PRE-AUDIT RO PREAUDIT SRO A.1.a Perform an APRM gain adjust IAW STP3.0.0-01 2.1.7-02 Determine reportability (Group 1 isolation) 2.1.14-02 Operate the plant process computer during plant startup 2.1.19-01 Review a system valve line-up in preparation for a startup 2.1.29-02 Perform control room shiftly checklist (faulted) 2.1.7-01 Safety function determination program (SFDP) 2.1.12-02 A.1.b Coil for Relay C71A-K3C opens.

Finds relay in electrical prints and discuss logic.

2.1.24-xx Coil for Relay C71A-K3C opens.

Review fuse removal request and determine if logic has functioned correctly.

2.1.24-xx Conduct a system valve checklist 2.1.29-01 Determine rod block monitor operability requirements 2.1.33-04 Limiting control rod pattern determination using STP 3.0.0-01 2.1.33-03 Actions to return MOV to operable status 2.1.7-03 A.2 Respond to a RBM Rod Block annunciator and safety limit violation 2.2.22-xx Core alterations -

determine actions for a misplaced fuel bundle during core re-load.

2.2.27-01 Fuel handling questions 2.2.27-02 Review a work order for completion 2.2.19-01 Perform STP 3.0.0-01 Instrument Checks STP, AP 2.2.12-01 Review/authorize a temporary mod.

2.2.15-01 A.3 Gain Access to a High Rad Area Note: Used for 2000 NRC exam 2.3.1-04 Gain Access to a High Rad Area Note: Used for 2000 NRC exam 2.3.1-04 Entry into a locked high radiation area 2.3.1-01 Entry into a locked high radiation area 2.3.1-01 Entry into the RCA 2.3.1-02 Entry into the RCA 2.3.1-02 A.4 Plant tour with a visitor when the plant evacuation alarm sounds.

2.4.39-xx Dispatch an operator into the plant when the TSC/OSC are not activated.

2.4.38-02 Fill the spent fuel pool with ESW 2.4.35-01 Determine required emergency action level and perform control room actions for EPIP notification 2.4.38-01 Function as the back panel communicator 2.4.3-01 Determine the emergency action level and direct the protective action recommendations 2.4.30-01 In plant Alternate Path Alternate Path New JPM Not Required

Appendix D AUDIT Scenario Outline Form ES-D-1 Facility :_____DAEC______ Scenario No.:__Audit ESG#1___ Op-Test No.:A2004-01 Examiners:_________________________ Operators:_________________________

Initial Conditions:

The plant is operating at 100% electrical output. No systems are out of service.

Turnover:

The plant is operating at 100% electrical output. No inoperable equipment.

The A RWCU F/D has been precoated and is ready to be placed in service Event No.

Malf No:

Event Type*

Event Description 1

N Place RWCU A bed. In service IAW OI 261, RWCU System.

2 1

I (ATC)

TS (SRO)

APRM fail up scale. This will result in a half scram.

3 2

C (BOP)

TS (SRO)

Leak in RWCU Hx room. Failure to isolate on Group 5 signal. The crew will enter EOP 3 on the room high temperature and isolate the RWCU system.

4 3

C (ATC)

CRD flow controller failure in auto. The controller will fail down scale requiring the crew to take manual control of the CRD flow 5

4 C (BOP)

HWC, H2 leak in the B FWP line, with a failure to automatically close. [FCV 8909B and SV-8901 must be manually closed]

6 5

R Loss of a circ water pump resulting is a Fast Power Reduction to maintain condenser back pressure.

7 6

M Change the loss of condenser vacuum. Based on discussions with NRC on 11/12/04

A LOCA will occur resulting in a high DW pressure.

DW sprays will not work.

ED on high drywell temperature

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

Appendix D AUDIT Scenario Outline Form ES-D-1 Facility :_____DAEC______ Scenario No.:__Audit ESG#2___ Op-Test No.:A2004-01 Examiners:_________________________ Operators:_________________________

Initial Conditions:

Reactor power is 75% the A EDG is inoperable.

Turnover:

TS 3.8.1. Condition A 7 day for the A EDG inoperable. The EDG is repaired and is to be run for its operability. STP 3.8.1-03 Standby Diesel Generators Operability Test will be run to demonstrate that he A EDG is operable.

Event No.

Malf No:

Event Type*

Event Description 1

N Start up of the EDG per STP 3.8.1-03, Standby Diesel Generators Operability Test is to be run for the A EDG to prove operability 2

R Power ascension using recirc IAW IPOI 3.

3 1

C (ATC)

TS (SRO)

Recirc pump trip due to a shaft failure 4

2 C (ATC)

Loss of annunciator power for 1C 05B.

5 3

C (BOP)

TS (SRO)

HPCI will receive an isolation signal based on a steam line break. HPCI will not automatically isolate. The BOP will take actions to isolate the system.

6 4

C (BOP)

Stator cooling pump will trip and the standby pump will not automatically start. The BOP will restart the pump 7

5 M

The first Stator cooling pump tripped due to a leak spraying on it. Soon the second pump trips and a Stator cooling run back will occur.

The crew will perform a fast power reduction IAW IPOI4.

When the runback overtakes the power reduction, the

crew will insert a manual scram.

The crew will determine that a Hydraulic ATWS has occurred and take actions to insert the control rods.

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

Appendix D AUDIT Scenario Outline Form ES-D-1 Facility :_____DAEC______ Scenario No.:__Audit ESG#3___ Op-Test No.:A2004-01 Examiners:_________________________ Operators:_________________________

Initial Conditions:

Power is at 75%. REs want to pull rods for a load line adjustment Turnover:

Power is at 75%. REs want to pull rods for a load line adjustment Event No.

Malf No:

Event Type*

Event Description 1

N Perform daily operation of the H2O2 analyzer OI 873 Section 4.1.

2 R

Rod pulls from 75% for load line adjust 3

1 C (ATC)

Control rod double notches, entry into AOP 255.1 4

2 C (ATC)

TS (SRO)

RBM fails downscale resulting in a rod block. This will require bypassing one of the RBMs 5

3 C (BOP)

The selected Isophase Bus Duct cooler fan will trip resulting in the starting of the standby fan.

6 4

M A packing leak on the B outboard MSIV will occur resulting in steam tunnel temperatures rising. The crew will enter EOP 3 and scram the plant prior to the steam tunnel reaching Max Safe 7

5 C (BOP)

The MSIVs will fail to close on the Group one signal and will have to be manually closed.

8 6

M The leak will worsen in the steam tunnel and spread to the area above the TIP room..

This will result in two different areas above max safe, which requires an ED.

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

ES-301 AUDIT Control Room/In-plant Systems Outline Form ES-301-2 Facility:___________________ Date of Examination:____________

Exam Level (circle one): RO Operation Test No.:_____________

Control Room Systems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. Perform STP 3.4.9-03 Recirc Pump Start Temperature Recording A1.13, 3.1/3.2, 202001 N, S 1

b. Perform required actions for HPCI rapid start for level control. Task 5.05, JPM 206000-02.

A4.05, 4.4/4.4, 206000 D, S 2

c. Install EOP Defeat 5 to depressurize the reactor. Task 95.15 239001-02 A4-02 3.2/3.2 D, S 3

d. STP 3.4.1-02, Single Loop Operation, Determine forward or reverse flow. [Alternate Path when the running recirc pump trips]

Task 1.07 202001 A2.04 3.7/3.8 A, N, S 4

e. Torus Vent irrespective of radioactive release. (Alternate

{Path, Hard Pipe Vent)

Task 95.30 223001 A2-07 4.2/4.3

[ Old JPM Task 95.30 295024-06]

A, M, S 5

f. Bypass a rod using NUMAC RWM Task 84.03 201006-04 D, S 7

g. Alternating RBCCW pumps w/ failure of RBCCW pumps Task 29.04 400000 A2-01 3.3/3.4 Current JPM 400000-01 A, D, S 8

h. Perform downscale/upscale trip operational check of ARMs Task 86.04 272000 A1.01 3.2/3.2 Current JPM Task 86.04, 272000-01 D, S 9

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

i. Perform required actions for transfer of control to the remote shutdown panel. [Alternate Path]

Current JPM 295016-10 AA1.07 4.2/4.3 A, M, 2

j. Shift 125 VDC battery chargers Current JPM Task [NSPEO] 29.04 263000-02 A3.01 3.2/3.3 D

6

k. Take NSPEO logs on CAD pressure, determine it is low and charge the CAD system via the CAD compressor A, N 8

All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow -power (N)ew or (M)odified form bank including 1(A)

(P)reious 2 exams (S)imulator 4-6 / 4-6 / 2-3 9 / 8 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 AUDIT Administrative Topics Outline Form ES-301-1 Facility:___________________ Date of Examination:____________

Exam Level (circle one):SRO I/U Operation Test No.:_____________

Administrative Topic (see note)

Type Code*

Describe Activity to be performed Equipment Control S, N

[2.2.12, Knowledge of surveillance procedures]

Review the Jet pump daily operability and determine that one jet pump is bad, and determine the associated TS requirements Conduct of Operations S, D

[2.1.12, Ability to apply technical specifications for a system.]

JPM 2.1.12-01 Safety Function Determination.

Conduct of Operations S, D

[2.1.7, Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation]

Perform an APRM Gain adjust Radiation Control C, D

[2.3.1, Knowledge of 10cfr20 and related facility radiation control requirements]

Perform JPM 2.3.1-04, Gain access to a high radiation area.

Emergency Plan S, D

[2.4.43, Knowledge of emergency communications systems and techniques.}

Perform OP-28, EPIP Offsite Agencies Notification Weekly Test.

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 (D)irect from bank (N)ew or (M)odified form bank including (1)

(P)reious 2 exams (< or = to 1; randomly selected (S)imulator

ES-301 AUDIT Administrative Topics Outline Form ES-301-1 Facility:___________________ Date of Examination:____________

Exam Level (circle one):RO Operation Test No.:_____________

Administrative Topic (see note)

Type Code*

Describe Activity to be performed Equipment Control S, N

[2.2.12, Knowledge of surveillance procedures]

Perform the Jet pump daily operability and determine that one jet pump is bad.

Conduct of Operations S, N

[2.1.29, Knowledge of how to conduct and verify valve lineups]

candidate will peer check a panel lineup for the RHR system.

Conduct of Operations S, D

[2.1.7, Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation]

Perform an APRM Gain Adjust.

Radiation Control C, D

[2.3.1, Knowledge of 10cfr20 and related facility radiation control requirements]

Perform JPM 2.3.1-04, Gain access to a high radiation area.

Emergency Plan 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 (D)irect from bank (N)ew or (M)odified form bank including (1)

(P)reious 2 exams (< or = to 1; randomly selected (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility :_____DAEC______ Scenario No.:__ESG#1___ Op-Test No.:_2005-01 Examiners:_________________________ Operators:_________________________

Initial Conditions: Reactor start up is in progress. The reactor is currently at 150 psig. Work was performed on PSV 4407 while the plant was shutdown, it is currently inoperable. Prior to exceeding 150 psig, (its MODE of operability), PSV -4407 must be proved operable. RHR is in Torus Cooling. The Start Up Feed Reg Valve has is isolated and RPV level is being controlled via the B feed reg valve.

Turnover: Reactor start up is in progress. The plant was shut down due to PSV 4407 leaking. It has been fixed. We are currently at 150 psig and holding.

STP 3.4.3-03, MANUAL OPENING AND EXERCISING OF THE ADS AND LLS RELIEF VALVES, for LLS PSV 4407 must be run prior to raising reactor power.

Currently one bypass valve is open 75%. The STP requires that one bypass valve be opened 100% and the second be open 15%. Control rods will have to be withdrawn to achieve the STP conditions. When he STP is complete begin pulling control rods to start up the plant.

Torus Cooling has been placed in service preparation of the STP, and TS 3.5.1 Condition B has been entered.

STP 3.6.2.1-01, Suppression Pool Water Temperature Surveillance, is available for when you open the SRV.

During the start up the Start Up Feed Reg Valve was sticking. It was decided that the Start Up Feed Reg Valve be isolated and level be controlled via the B Feed Reg Valve. At the beginning of your shift, there are 2 I & C techs going to look at the operator. They may call for your assistance to cycle the valve.

There is a severe thunder storm warning for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the Linn and Benton Counties.

Event No.

Malf No:

Event Type*

Event Description 1

R A control rod pull brief will be conducted. At the end of the brief, the RO will raise power with control rods to achieve 1 bypass valve 100% open and the second bypass valve 15% open. During the power ascension, the C IRM will fail up scale resulting in a half scram.. When the target conditions are met, the STP cab be run.

2 1

I (RO/SRO)

The RO will respond to annunciators 1C05A B-3, C-3, and A-2. C IRM will fail up scale resulting in a half scram. The RO will bypass the failed IRM and reset the half scram. This is a TS entry due to the loss of the C IRM and another IRM bypassed. The actions of the TS are already met, and the TS is exited when the operable IRM is unbypassed and the failed IRM is bypassed. TS is 3.3.1.1 Condition A is momentarily entered 3

N (BOP)

Performance of STP 3.4.3-03, Manual Opening and Exercising of the ADS and LLS Relief Valves for PSV 4407 will be run.

4 2

C (RO)

The B Feed Reg valve will lock up due to an air line being broken off during the repairs to the Start Up Feed Reg Valve.. The RO will respond IAW ARP 1C05A F-1.

Shortly after the lock up, the I & C Techs working on the start up feed reg valve, will call and confess that they inadvertently caused the lock up and the condition for the lock up is cleared.

The RO will unlock the B feed reg valve IAW the ARP.

5 3

C (BOP)

The running condensate pump will develop high vibrations. The crew will start the idle condensate pump and secure the running.

6 4

C (BOP) and TS (SRO)

A lightning strike will start the B EDG. The BOP will send the Aux man to investigate. The report back from the EDG room will state that there are 2 annunciators on 1C94, A-3, JACKET COOLANT LEVEL LOW, and A-4, JACKET COOLANT TEMPERATURE HIGH OR LOW. The report will also state that the jacket coolant temperature is currently 195 degrees and going up.

The BOP will remove the B EDG from service and the SRO will enter the applicable TS 7

5 C

(BOP/SRO)

PSV 4407 will not close when the HS is taken to the Auto position.

AOP 683 will be entered. Per the AOP, the valved will be cycled.

The cycling of the valve will allow it to go closed.

8 6

M The condensate pump transient will result in a rupture of feedwater piping in the DW. The rupture will occur at the feed water check valve. This will result in a drywell high pressure and entry into EOP 1 and EOP 2.

On the 2-psig signal, 1A3 will lock out due to a short in the A CS motor.

The B CS pump will trip For EOP 2, the crew will have to spray the drywell. The Crew will also have to monitor Torus water level and secure Condensate and Feed to stop the torus water level rise.

Because RPV pressure is so low, HPCI and RCIC will isolate shortly after the event.

The RHR inject valve will fail to automatically open.

The BOP will have to control his injection into the RPV with CS and/or LPCI.

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

Appendix D Scenario Outline Form ES-D-1 Facility: _____DAEC______ Scenario No.: ESG 2__ Op-Test No.:__2005-01 Examiners:_________________________ Operators:_________________________

Initial Conditions: The plant is at 1500MWth.A CS pump is tagged out to repair a lower bearing. TS 3.5.1 Condition B has been entered.

Turnover: Power has been lowered to perform NS-930002, Turbine Stop Valve and Combined Intermediate Valve Test.

The A CS pump is tagged out for replacement of the lower bearing. TS 3.5.1 Condition B has been entered, and are currently in day 3 of 7 of the LCO. Work is expected to be complete in 2 days.

Last shift the I & C Techs just finished work on the LT-4559, which feeds into the feedwater level control circuit and the A GEMAC level indicator. The I & C Techs and System Engineer would like to maintain level control in A over night to observe its response.

Event No.

Malf No:

Event Type*

Event Description 1

N (BOP)

Performance of NS-930002, Main Turbine Stop and Combined Intermediate Valve Test 2

R (RO)

Begin raising power with reactor recirc to achieve 100%

capability.

3 1

C (RO/SRO)

B recirc speed controller will fail and will begin to run away requiring the RO to lock it up. This will require a TS check to determine if the speed mis-match between the two recirc pumps is with in the required band.

4 2

C (BOP/SRO)

Spurious Group 2 isolation with the failure of CV 3729 failing to isolate. This will require entry into TS for a failed primary containment isolation valve.

5 3

I (RO/SRO)

The A GEMAC level transmitter will fail upscale requiring that level control be transferred to B. This is also a TS for GEMAC level instruments being > 2.5 apart.

6 4

C (BOP)

The running River Water Supply pump trips requiring entry into AOP 410. the operator will assess the situation and start another RWS pump.

7 5

M (all)

A slow leak in the Turbine Lube oil system will develop requiring entry into ARP 1C07A A-7.

8 5a C (BOP)

IAW ARP 1C07A A-7 the operator is to verify that additional turbine lube oil pumps start. These pumps fails to auto start requiring the BOP operator to manually start them..

9 6

M (all)

The lube oil pressure will momentarily recover. However as the leak worsens, the system pressure continue to lower.

This will force the crew to enter AOP 693, Main Turbine/EHC Failures When the crew attempts to scram the plant they will determine that an electrical ATWS prevents the rods from inserting.

They will enter Power Level control, (EOP Contingency) to lower reactor power.

The control rods will be inserted by pulling the RPS fuses per RIP 101.2.

7 continued All When all control rods have been inserted, the crew will continue to work through AOP 693. This will have them close the MSIVs and break condenser vacuum.

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

Appendix D Scenario Outline Form ES-D-1 Facility: _____DAEC______ Scenario No.: ESG 3__ Op-Test No.:_2005-01 Examiners:_________________________ Operators:_________________________

Initial Conditions: The plant is operating at 100% capability. There is no inoperable equipment.

Turnover: The plant is operating at 100% capability. It is a warm summer day. The B RHRSW pump is to be started for chemistry to obtain a sample. You are to start the B RHRSW pump, IAW OI 416, and then call the Chemists.

Event No.

Malf No:

Event Type*

Event Description 1

N (BOP)

IAW OI 416, start the B RHRSW pump.

2 1

C (RO)

An APRM flow unit will fail down scale. This will result in a half scram. RO will respond to ARP 1C05A E-2 for the flow unit, and 1C05A A2 for the half scram. Per the actions of ARP 1C05A E-2 the RO will remove the A flow unit from service and reset the half scram.

3 2

C (BOP/SRO)

The B RHRSW pump will develop a motor bearing problem and begin to seize up. The BOP will have to remove the RHRSW pump from service.

The SRO will enter TS 3.7.1 Condition A.

4 3

C (BOP/SRO)

The Start up transformer will receive annunciator 1C08A A-7, Start Up Transformer Trouble. When investigated the problem will require the transformer r to be removed from service.

This will require entry into TS 3.8.1 Condition A, for loss of one offsite power source.

5 4

C (RO/SRO)

A control rod will drift in, (OE 18716). Per the actions of ARP 1C05 A D-6, the RO will stop the drifting by applying an Emergency In signal to the control rod. TS will be entered for either an inoperable accumulator or control rod.

6 5

C (BOP)

The #3 feed water heater controller will fail in AUTOMATIC. This will require controlling the feedwater heater in manual.

7 6

M (all)

Condenser Hot Well conductivity will begin to rise due to a tube leak. The crew will enter AOP 639 8

R (RO)

IAW AOP 639 when the influent conductivity of the condensate demineralizers reaches 1 micro mho, the crew will perform a fast power reduction with recirc to 27 million lbm/hr flow and scram the plant 9

7 M (all)

Following the reactor scram a LOCA will develop.

The crew will enter EOP 1 and 2 Torus and Drywell sprays will be initiated to protect the containment.

HPCI will malfunction and trip.

Due to failure high-pressure injection systems, ALC will be entered.

The available inject systems will be lined up. When RPV level lowers to +15 inches an ED will be performed.

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

Operated by Nuclear Management Company LLC Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 January 18, 2002 NG-02-0068 U.S Nuclear Regulatory Commission, Region III Mr. Dave Pelton 801 Warrenville Road Lisle, IL 60532-4351

Subject:

Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 K/A Suppression for DAEC Initial License Examination Week of November 18, 2002.

File:

A117a

References:

NUREG 1021, Operating License Examination Standard for Power Reactors, Revision 8, Supplement 1.

Dear Mr. Pelton:

In accordance with the guidelines of NUREG 1021, Operating License Examination Standard for Power Reactors, Revision 8, Supplement 1, we are sending you the DAEC K/A Suppression.

NUREG 1021 physical security requirements are not required for the enclosed material.

You may direct any questions or comments regarding this material to Steve Brewer at 319-851-7268 (or 7575) or George Thullen at 319-851-7268 (or 7945)

Sincerely Jim Sparano DAEC Training Manager

NG-02-0068 Attachments:

1. Methodology used for the DAEC K/A Suppressed Catalog

2. Additional Guidance on K/A Suppression

3. Condensed System K/A Suppression Basis

4. Complete System K/A Suppression Basis

5. Word Document on CD ROM with full Suppressed K/A Catalog Basis cc: Documaster w/o Johnson, Al w/o

Methodology Used For The DAEC K/A Suppressed Catalog E:\\DAEC 2005\\DAEC 75 Day Submital Outline\\Methodology for Suppressed Catalog.doc 1

The DAEC developed a suppressed K/A catalog for the 2001 ILC Exam. This was done before the additional guidance had been placed on the NRC web site (Attachment 2). We have changed our suppression based on that guidance for the 2002 ILC Exam.

We suppressed 3 Generic K/As listed below from the Generic section:

The Duane Arnold Energy Center is a single unit site, Generic K/As 2.2.3 and 2.2.4. do not apply.

BWR EOPs are symptom based, Generic K/A 2.4.7 does not apply.

We suppressed Generic K/As in systems based on the guidance in Attachment 2.

Note: Attachment 4 Complete System K/A Suppression Basis lists all the systems and the K/As which were suppressed after the Generic suppressions above were complete.

We suppressed K/As for the following systems or design features that do not apply to the Duane Arnold Energy Center:

Acoustical Monitoring Any reference to designs other than BWR 4 or Mark I Containment FWCI GAS or Jet Drive Generators HPCS Isolation Condenser LP-RWCU MSIV LCS (Removed from DAEC)

RCIS Recirc Flow Control Valves or Hydraulic Power units associated with Recirc.

RRCS Turbine driven Feed Pumps (TDFP)

RSCS (This system is bypassed at DAEC and is only used for back lighting)

Note: Attachment 3 Condensed System K/A Suppression Basis lists all the systems and the K/As which were suppressed after the suppressions above were complete. (Generic and System/Features which do not apply at the DAEC)

There is also a CD ROM which has the complete ACCESS data base for the Suppressed Catalog.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:___DAEC_________ Date of Examination:_1/31/05____

Exam Level (circle one):RO Operation Test No.:_2005-01_____

Administrative Topic (see note)

Type Code*

Describe Activity to be performed Conduct of Operations S, N Pump the DW Equipment and Floor drain sumps for the 1200 readings. Perform the calculation per STP 3.0.0-01. Determine that the reading is out of spec high and recommend that the SRO take the prescribed actions of the STP.

[2.1.2]

Conduct of Operations S, N Worker Call out. Determine if it is acceptable to assume the watch as an RO.

Ensuring that the Overtime limits are not exceeded and that their license is currently active does this.

Based on the information provided, the operator will not be able to assume the watch.

2.1.7 Equipment Control S, N Perform STP 3.8.1-01 for Offsite Sources inoperable.

The RO will have to perform the STP and determine if the proper alignment of off site sources exists.

Based on th conditions given the RO, the required number of offsite sources will not exist.

2.2.12 Radiation Control S, N Review a survey map and RWP for an area in the plant.

Determine the exposure, the exposure limit are acceptable when compared to the RWP. (HPPs 31.03.3 for Survey map, and 3101.5 for the RWP requirements.

2.3.10 Emergency Plan 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 (D)irect from bank ) 3 for ROs; 4 for SROs and RO retakes (N)ew or (M)odified form bank including (1)

(P)reious 2 exams (< or = to 1; randomly selected (S)imulator

ES-401 BWR Examination Outline Form ES-401-1 Facility: DAEC Date of Exam: 01/31/2005 RO K/A Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G

• Total 1

3 3

2 3

2 7

20 7

2 0

2 4

0 0

1 7

3

1.

Emergency Abnormal Plant Evolutions Tier Totals 3

5 6

N/A 3

2 N/A 8

27 10 1

3 5

1 2

2 4

3 1

1 2

2 26 5

2 0

1 1

0 3

1 0

1 1

4 0

12 3

2.

Plant Systems Tier Totals 3

6 2

2 5

5 3

2 2

6 2

38 8

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 3

2 2

3 10 7

Note: 1.

Ensure that at least two topics from every K/A 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 K/A 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 +/-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.

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 outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

4.

Select topics from as many systems and evolutions 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 K/As 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 K/A categories.

7.*

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8.

On the following pages, enter the K/A 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 table above. Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, Page 16 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro exam nureg-1021 rev 9 form es-401-1 bwr examination outline.doc 5/5/2005 1:24 PM

ES-401 2

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 E

d Ab l Pl t E l ti Ti 1/G 1 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G K/A Topic(s)

IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X

AK1.03 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: (CFR: 41.8 to 41.10) Thermal limits.

3.6 1

295003 Partial or Complete Loss of AC / 6 X

AA1.02 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: (CFR: 41.8 to 41.10)

Emergency generators.

4.2*

1 295004 Partial or Total Loss of DC Pwr / 6 X

2.4.6 Knowledge symptom based EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13) 3.1 1

X AK2.04 Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: (CFR:

41.7 / 45.8) Main generator protection.

3.3 1

295005 Main Turbine Generator Trip / 3 X

2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 3.4 1

295006 SCRAM / 1 X

AA2.03 Ability to determine and/or interpret the following as they apply to SCRAM: (CFR: 41.10 / 43.5 / 45.13)

Reactor water level.

4.0 1

295016 Control Room Abandonment / 7 X

2.2.22 Knowledge of limiting conditions for operations and safety limits. (CFR: 43.2 / 45.2) 3.4 1

295018 Partial or Total Loss of CCW / 8 X

AK1.01 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: (CFR: 41.8 to 41.10) Effects on component/system operations.

3.5 1

295019 Partial or Total Loss of Inst. Air / 8 X

AK3.01 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: (CFR: 41.5 / 45.6)

Backup air system supply: Plant-Specific.

3.3 1

295021 Loss of Shutdown Cooling / 4 X

AA1.01 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING: (CFR:

41.7 / 45.6) Reactor water cleanup system.

3.4 1

295023 Refueling Acc / 8 X

2.4.31 Knowledge of annunciators alarms and indications / and use of the response instructions. (CFR:

41.10 / 45.3) 3.3 1

295024 High Drywell Pressure / 5 X

2.4.24 Knowledge of loss of cooling water procedures.

(CFR: 41.10 / 45.13) 3.3 1

295025 High Reactor Pressure / 3 X

EA2.01 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: (CFR:

41.10 / 43.5 / 45.13) Reactor pressure 4.3*

1 295026 Suppression Pool High Water Temp. / 5 X

EK2.01 Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following: (CFR: 41.7 / 45.8) Suppression pool 4.1*

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ES-401 2

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 E

d Ab l Pl t E l ti Ti 1/G 1 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G K/A Topic(s)

IR water temperature 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 X

EK1.01 Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE: (CFR: 41.8 to 41.10) Reactor water level measurement.

3.5 1

295030 Low Suppression Pool Wtr Lvl / 5 X

EK3.06 Knowledge of the reasons for the following responses as they apply to LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.5 / 45.6) Reactor SCRAM 3.6 1

295031 Reactor Low Water Level / 2 X

2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 3.4 1

295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 X

2.4.31 Knowledge of annunciators alarms and indications / and use of the response instructions. (CFR:

41.10 / 45.3) 3.3 1

295038 High Off-site Release Rate / 9 X

EK2.07 Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following: (CFR:

41.7 / 45.8) Control room ventilation 3.5 1

600000 Plant Fire On Site / 8 X

AA1.05 Ability to operate and / or monitor the following as theyapply to PLANT FIRE ON SITE: Plant and control room ventilation systems 3.0 1

K/A Category Totals:

3 3

2 3

2 7 Group Point Total:

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ES-401 3

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G K/A Topic(s)

IR 295002 Loss of Main Condenser Vac / 3 X

AK3.05 Knowledge of the reasons for the following responses as they apply to LOSS OF MAIN CONDENSER VACUUM: (CFR: 41.5 / 45.6) Main steam isolation valve:

Plant-Specific 3.4 1

295007 High Reactor Pressure / 3 X

AK2.05 Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: (CFR: 41.7 /

45.8)

Shutdown cooling: Plant-Specific. PRESSURE and the following: (CFR: 41.7 / 45.8) 2.9 1

295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X

AK3.01 Knowledge of the reasons for the following responses as they apply to LOW REACTOR WATER LEVEL: (CFR: 41.5 / 45.6) Recirculation pump run back:

Plant-Specific.

3.2 1

295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 X

2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. (CFR: 43.2 / 43.3 / 45.3) 3.4 1

295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 X

AK2.07 Knowledge of the interrelations between INCOMPLETE SCRAM and the following: (CFR: 41.7 /

45.8) CRD mechanism 3.3 1

295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 X

EK3.01 Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: (CFR: 41.5 / 45.6)

Isolating secondary containment ventilation.

3.8 1

295035 Secondary Containment High Differential Pressure / 5 X

EK3.02 Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT 3.3 1

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ES-401 3

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G K/A Topic(s)

IR HIGH DIFFERENTIAL PRESSURE: (CFR: 41.5 / 45.6)

Secondary containment ventilation response 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:

0 2

4 0

0 1

Group Point Total:

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ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 203000 RHR/LPCI: Injection Mode X

A1.02 Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) controls including: (CFR: 41.5 / 45.5) Reactor pressure 3.9*

1 205000 Shutdown Cooling X

K6.05 Knowledge of the effect that a loss or malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE):

(CFR: 41.7 / 45.7) Component cooling water systems 3.2 1

206000 HPCI X

K2.04 Knowledge of electrical power supplies to the following: (CFR: 41.7)

Turbine control circuits: BWR-2,3,4 2.5*

1 207000 Isolation (Emergency) Condenser 209001 LPCS X

K2.02 Knowledge of electrical power supplies to the following: (CFR: 41.7)

Valve power 2.5*

1 209002 HPCS X

A3.07 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including: (CFR:

41.7 / 45.7) Lights and alarms: Plant-Specific 3.7 1

211000 SLC X

2.4.6 Knowledge symptom based EOP mitigation strategies. (CFR: 41.10 / 43.5 /

45.13) 3.1 1

212000 RPS X

A1.08 Ability to predict and/or monitor changes in parameters associated with operating the REACTOR PROTECTION SYSTEM controls including: (CFR: 41.5 /

45.5) Valve position 3.4 1

215003 IRM X

A4.06 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /

45.5 to 45.8) Detector drives 3.0 1

215004 Source Range Monitor X

K2.01 Knowledge of electrical power supplies to the following: (CFR: 41.7) SRM channels/detectors 2.6 1

215005 APRM / LPRM X

K3.08 Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE MONITOR/LOCAL POWER 3.0 1

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ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR RANGE MONITOR SYSTEM will have on following: (CFR: 41.7 / 45.4) core thermal calculations X

K1.02 Knowledge of the physical connections and/or cause effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following: (CFR: 41.2 to 41.9 /

45.7 to 45.8) Nuclear boiler system 3.5 1

217000 RCIC X

2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 45.3) 3.3 1

218000 ADS X

K5.01 Knowledge of the operational implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM: (CFR:

41.5 / 45.3) ADS logic operation 3.8 1

223002 PCIS/Nuclear Steam Supply Shutoff X

K1.11 Knowledge of the physical connections and/or cause effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Containment atmosphere sampling 2.9 1

X K2.01 Knowledge of electrical power supplies to the following: (CFR: 41.7) SRV solenoids 2.8*

1 239002 SRVs X

A1.08 Ability to predict and/or monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including: (CFR: 41.5 / 45.5)

Suppression pool water temperature 3.8 1

259002 Reactor Water Level Control X

K5.03 Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM: (CFR: 41.5 / 45.3)

Water level measurement 3.1 1

261000 SGTS X

A2.01 Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the 2.9 1

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ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Low system flow 262001 AC Electrical Distribution X

K4.01 Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7) Bus lockouts 3.0 1

262002 UPS (AC/DC)

X A4.01 Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature(s) and/or interlocks which provide for the following: (CFR: 41.7) Transfer from preferred power to alternate power supplies 3.1 1

263000 DC Electrical Distribution X

K2.01 Knowledge of electrical power supplies to the following: (CFR: 41.7)

Major D.C. loads 3.1 1

264000 EDGs X

K6.07 Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET): (CFR: 41.7 / 45.7) Cooling water system 3.8 1

X K4.02 Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following:

(CFR: 41.7) Cross-over to other air systems 3.0 1

300000 Instrument Air X

K6.12 Knowledge of the effect that a loss or malfunction of the following will have on the INSTRUMENT AIR SYSTEM: (CFR:

41.7 / 45.7) Breakers, relays and disconnects 2.9 1

X K1.03 Knowledge of the physical connections and / or cause-effect relationships between CCWS and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Radiation monitoring systems 2.7 1

400000 Component Cooling Water X

K6.07 Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: (CFR: 41.7 / 45.7) Breakers, relays, and disconnects 2.7 1

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ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR K/A Category Point Totals:

3 5 1 2

24 3 1 1 2 2 Group Point Total 26/5 ES-401, Page 19 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro exam nureg-1021 rev 9 form es-401-1 bwr examination outline.doc 5/5/2005 1:24 PM

ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 201001 CRD Hydraulic X

K5.08 Knowledge of the operational implications of the following concepts as they apply to CONTROL ROD DRIVE HYDRAULIC SYSTEM: (CFR: 41.5 / 45.3)

Solenoid operated valves 2.5 1

201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM X

K5.06 Knowledge of the operational implications of the following concepts as they apply to ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC):

(CFR: 41.5 / 45.3) Rod groups and steps:

P-Spec (Not-BWR6) 2.8 1

202001 Recirculation X

K2.01 Knowledge of electrical power supplies to the following: (CFR: 41.7)

Recirculation pumps: Plant-Specific 3.2*

1 202002 Recirculation Flow Control 204000 RWCU X

A4.05 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /

45.5 to 45.8) System pressure 2.9 1

214000 RPIS 215001 Traversing In-core Probe X

A4.03 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /

45.5 to 45.8) Isolation valves: Mark-I&II (Not-BWR1) 3.0 1

215002 RBM X

A2.01 Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Withdrawal of control rod in high power region of core: BWR-3,4,5 3.3 1

216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

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ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam X

A4.05 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /

45.5 to 45.8) System temperature 2.7 1

239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator X

K6.06 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM: (CFR: 41.7 /

45.7) Reactor pressure 3.8*

1 245000 Main Turbine Gen. / Aux.

X K5.07 Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: (CFR: 41.5 / 45.3) Generator operations and limitations 2.6 1

256000 Reactor Condensate X

A4.02 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /

45.5 to 45.8) System motor operated valves 2.8 1

259001 Reactor Feedwater X

K3.06 Knowledge of the effect that a loss or malfunction of the REACTOR FEEDWATER SYSTEM will have on following: (CFR: 41.7 / 45.4) Core inlet subcooling 3.1 1

268000 Radwaste 271000 Offgas X

A3.02 Ability to monitor automatic operations of the OFFGAS SYSTEM including: (CFR: 41.7 / 45.7) System flows 2.9 1

272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals e:\\daec 2005\\daec 75 day submital outline\\ro exam nureg-1021 rev 9 form es-401-1 bwr examination outline.doc 5/5/2005 1:24 PM

ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR K/A Category Point Totals:

0 1 1 0

31 0

1 1

4 0

Group Point Total 12/3 ES-401, Page 20 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro exam nureg-1021 rev 9 form es-401-1 bwr examination outline.doc 5/5/2005 1:24 PM

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: DAEC Date of Exam: 01/31/2005 RO SRO-Only Category K/A #

Topic IR IR 2.1.3 Knowledge of shift turnover practices. (CFR: 41.10 / 45.13) 3.0 1

2.1.8 Ability to coordinate personnel activities outside the control room.

(CFR: 45.5 / 45.12 / 45.13) 3.8 1

2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. (CFR: 43.2 /

43.3 / 45.3) 3.4 1

2.1.

2.1.

2.1.

1.

Conduct of Operations Subtotal 3

2.2.12 Knowledge of surveillance procedures. (CFR: 41.10 / 45.13) 3.0 1

2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area / communication with fuel storage facility / systems operated from control room in support of fueling operations / and supporting instrumentation. (CFR: 45.12) 3.5 1

2.2.

2.2.

2.2.

2.2.

2.

Equipment Control Subtotal 2

2.3.2 Knowledge of facility ALARA program. (CFR: 41.12 / 43.4 / 45.9 /

45.10) 2.5 1

2.3.11 Ability to control radiation releases. (CFR: 45.9 / 45.10) 2.7 1

2.3.

2.3.

2.3.

2.3.

3.

Radiation Control Subtotal 2

2.4.18 Knowledge of the specific bases for EOPs.

(CFR: 41.10 / 45.13) 2.7 1

2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures. (CFR: 41.10 / 43.5 / 45.13) 3.0 1

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm. (CFR: 43.5 / 45.3 / 45.12) 3.3 1

2.4.

2.4.

4.

Emergency Procedures

/ Plan 2.4.

ES-401, Page 26 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro exam nureg-1021 rev 9 form es-401-3 generic knowledge and abiliities outline tier 3.doc Page 1 of 2 5/5/2005 1:28 PM

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Subtotal 3

Tier 3 Point Total 10 7

ES-401, Page 26 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro exam nureg-1021 rev 9 form es-401-3 generic knowledge and abiliities outline tier 3.doc Page 2 of 2 5/5/2005 1:28 PM

D-301 Control Room/In-plant Systems Outline Form ES-301-2 Facility:__DAEC___________ Date of Examination:__1/31/05___

Exam Level (circle one): RO Operation Test No.:__2005-01____

Control Room Systems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. CRD Exercise with a rod Overtravel. (201003-06)

D, A, S 1

b. Install Defeat #1 and use RCIC for Level Control. (217000-

12)

D, S, L 2

c. Isolate an MSIV at power. (239001-03)

N, S 3

d. Manual Start of Core Spray for injection. (209001-04)

N, S 4

e. Drain the Torus to Radwaste. AP to install defeat 13.

(219000-04)

N, A, S 5

f. Perform A logic Manual Scram Functional Test (STP 3.3.1.1-21) (212000-15)

N, S, 7

g. Install Defeat 4 with a Group 7 Isolation. (4000-02)

N, A, S 8

h. Establish Alternate Leakage Control IAW AOP 672.2.

(272000-03)

N, S 9

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

i. Shutdown of Regulating Transformer 1Y1A for maintenance. (AP requiring transfer of alternate RPS from 1Y16 to 1Y26) [262002-04]

N, A 6

j. Switch CRD Discharge Filters. (264000-08)

R, D 1

k. Establish Make-up Flow to RHRSW/ESW. (295018-01)

D, E, 8

All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow -power (N)ew or (M)odified form bank including 1(A)

(P)reious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-401 BWR Examination Outline Form ES-401-1 e:\\daec 2005\\daec 75 day submital outline\\ro sro exam nureg-1021 rev 9 form es-401-1 bwr examination outline page 1.doc 5/5/2005 1:29 PM Facility: DAEC Date of Exam: 01/31/2005 RO K/A Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A 2 G

• Total 1

3 3

2 3

2 7

20 4

3 7

2 0

2 4

0 0

1 7

1 2

3

1.

Emergency Abnormal Plant Evolutions Tier Totals 3

5 6

N/A 3

2 N/A 8

27 5

5 10 1

3 5

1 2

2 4

3 1

1 2

2 26 3

2 5

2 0

1 1

0 3

1 0

1 1

4 0

12 3

0 3

2.

Plant Systems Tier Totals 3

6 2

2 5

5 3

2 2

6 2

38 6

2 8

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 3

2 2

3 10 2

2 2

1 7

Note: 1.

Ensure that at least two topics from every K/A 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 K/A 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 +/-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.

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 outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

4.

Select topics from as many systems and evolutions 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 K/As 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 K/A categories.

7.*

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8.

On the following pages, enter the K/A 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 table above. Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, Page 16 of 33

ES-401 Record of Rejected K/As Form ES-401-4 ES-401, Page 27 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro sro exam nureg-1021 rev 9 form es-401-4 record of rejected kas.doc Page 1 of 4 5/5/2005 1:30 PM Tier /

Group Randomly Selected K/A Reason for Rejection RO Tier 1 Group 1 Question 12 295025 EA2.06 Emergency High Reactor Pressure was combined with ability to determine and/or interpret the following as they apply to High Reactor Pressure: Reactor water level. A Search of industry questions showed that some plants must pressure compensate for water level indicators. Operators at DAEC do not adjust RPV level for high reactor pressure. Randomly selected another EA2, EA2.01, Reactor Pressure as a replacement.

RO Tier 1 Group 1 Question 13 295026 EK2.02 Emergency High Torus Water Temperature was combined with Knowledge of interrelations with Torus Spray. Normally, initiation of Torus Spray at DAEC is not dependent on Torus Water Temperature. NPSH limits might apply if Torus very hot, >190°. An SRO might be asked to interpret the NPSH EOP curves, but this is not a major EOP breakpoint suitable for ROs. Randomly selected another EK2, EK2.01, as a replacement.

RO Tier 1 Group 1 Question 16 295031 2.4.49 Reactor Low Level (Emergency) was combined with generic ability to perform immediate actions without procedures. The resulting question conflicted with the Low Level (Abnormal) question in T1G2. Also, at the emergency/EOP stage of this transient, there would be no immediate operator actions.

Randomly selected another Generic, 2.1.32, Ability to apply system limits and precautions, as a replacement.

RO Tier 1 Group 2 Question 19 600000 AA1.08 Plant Fire on site was combined with the knowledge of fire fighting equipment used on each class of fire. Resulting questions had low discriminatory value.

Randomly selected another AA1, AA1.05, as a replacement.

RO Tier 1 Group 2 Question 24 295012 2.1.28 Abnormal High Drywell Temperature was combined with system generic knowledge of the purpose and function of major system components and controls. Since a High Drywell temperature event does not have components or controls, it would not be possible to write a question about their purpose and function. Randomly selected another Generic, 2.1.33, as a replacement.

RO Tier 1 Group 2 Question 27 295035 EK3.01 Secondary Containment high DP was combined with Knowledge of the reasons for the following responses as they apply to Secondary Containment high DP: Blow out panel operation. Any question that addressed the reason for blowout panels would always have the answer of preventing overpressure, making this combination too easy. Selected the only other 295035 EK3, EK3.02 as a replacement.

ES-401 Record of Rejected K/As Form ES-401-4 ES-401, Page 27 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro sro exam nureg-1021 rev 9 form es-401-4 record of rejected kas.doc Page 2 of 4 5/5/2005 1:30 PM Tier /

Group Randomly Selected K/A Reason for Rejection RO Tier 2 Group 1 Question 29 205000 K6.03 Shutdown Cooling was combined with knowledge of the effect of a loss or malfunction of Recirculation System. Topic was too closely related to SRO 295001 Loss of forced circulation with 2.4.9 Knowledge of low power implications in an accident. Randomly selected K6.04, Reactor water level, as a replacement, but that K/A would still have the same problem. Randomly selected another K6 topic K6.05, Component Cooling Water, as a replacement.

RO Tier 2 Group 1 Question 32 211000 A3.04 SBLC was combined with the ability to monitor reactor power which is read on panel 1C05 right next to SBLC control and which obviously goes down when SBLC is initiated. A question to this combination would be too easy. The clincher was that we could not find any industry bank questions on this combination. Randomly selected another A3 topic A3.07, Lights and alarms, as a replacement.

RO Tier 2 Group 1 Question 34/35 215003 (IRM) K2.01 and 215004 (SRM) K2.01 K2.01, Knowledge of power supply to channel/detectors, was randomly selected for both IRM and SRM. The answer in both cases is 24 VDC, which is too similar. IRM has only one K2 topic and SRM has only one K2 topic with an importance rating of 2.5. Randomly selected 215003 (IRM) and then randomly selected A4.01 for that system.

RO Tier 2 Group 1 Question 34 215003 (IRM)

A4.01 IRM system was combined with the ability to manually operate and/or monitor in the control room: IRM recorder Indication. A question to this combination would be too easy. The recorders are frequently read at 1C05. Any question that used IRM indication in response to range switches positioning or reactivity changes would match up better with another K/A. Randomly selected another A4 topic, A4.06, Detector Drives, as a replacement.

RO Tier 2 Group 1 Question 51 239002 A1.01 SRV system was combined with ability to predict and/or monitor changes in parameters associated with operating the SRV controls including: Tail Pipe Temperatures. This ability would also be measured during a planned simulator normal evolution. Randomly selected another A1 topic, A1.08, Torus water temperature, as a replacement.

RO Tier 2 Group 1 Question 52 300000 K6.04 Instrument Air was combined with the knowledge of the effect of a loss or malfunction of a service air refusal valve. DAEC has no air system valve by this name. DAEC does have a valve that isolates the Service Air Header first as pressure lowers during abnormal conditions. Closing it would have no effect on Instrument Air during normal operations. Randomly selected another K6 topic, K6.03, Temperature Indicators, as a replacement.

RO Tier 2 Group 1 Question 52 300000 K6.03 Instrument Air was combined with the knowledge of the effect of a loss or malfunction of Temperature Indicators. A Loss of a temperature indictor could not have an effect other than loss of the ability to read that temperature. This would result in a question that was too easy. Randomly selected another K6 topic, K6.12, Breakers, relays and disconnects, as a replacement.

RO Tier 2 Group 2 Question 60 239001 A4.08 Main and Reheat Steam was combined with the ability to operate or monitor Reactor Level, which is already the topic in 295031(T1G1), 295009 (T1G2) and 259002 (T2G1). Randomly selected another A4 topic, A4.10 Reactor Power as a replacement. This would result in a question that was too easy. Randomly selected another A4 topic, A4.05 System Temperature as a replacement.

RO Tier 3 Question 73 2.4.1 Knowledge of EOP entry conditions and immediate action steps was in conflict with several SRO questions. In addition, DAEC EOPs have no immediate operator actions and a memory level question on EOP entry conditions would be too easy.

ES-401 Record of Rejected K/As Form ES-401-4 ES-401, Page 27 of 33 e:\\daec 2005\\daec 75 day submital outline\\ro sro exam nureg-1021 rev 9 form es-401-4 record of rejected kas.doc Page 3 of 4 5/5/2005 1:30 PM Tier /

Group Randomly Selected K/A Reason for Rejection Randomly selected another Generic 2.4 topic, 2.4.18, Knowledge of specific bases for EOPs as a replacement.

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Group Randomly Selected K/A Reason for Rejection SRO Tier 1 Group 1 Question 3 295006 2.4.49 Reactor SCRAM was combined with Ability to perform immediate actions without reference to procedures. This Generic K/A had already been selected with 295031 (RPV Low Water Level) on the RO exam. The two questions would be too similar. Randomly selected another Generic, 2.1.7, as a replacement.

SRO Tier 1 Group 1 Question 4 295019 AA2.01 Partial or complete loss of instrument air was randomly selected. This Evolution must also be selected for the RO exam in Tier 1. In Tier 2 Group 1, some systems must be selected more than once. On the RO exam, System 300000, Instrument Air was one such system. Therefore, on the SRO exam, randomly selected 295030 EA2.03 in its place rather than have four questions on Instrument Air or loss of Instrument Air.

SRO Tier 1 Group 1 Question 5 295025 2.4.16 System Generic 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures was also selected for the RO exam in Tier 3. To avoid duplication, randomly selected generic 2.1.14 in its place.

SRO Tier 1 Group 2 Question 8 295008 2.1.14 2.1.14 is a System Generic K/A (System status that requires notification of plant personnel) that was also selected for System 218000 (ADS) in Tier 2 and Event 295025 in Tier 1. To avoid duplication, randomly selected generic 2.1.32 as a replacement.

SRO Tier 1 Group 2 Question 9 295035 2.1.32 295035 High Secondary Containment Differential Pressure was also selected in Tier 1 Group 2 on the RO exam. Questions would conflict. Randomly selected 295017 from a field of T1G2 Evolutions that were not previously selected on RO exam. 2.1.32 remained as the Generic topic.

SRO Tier 2 Group 1 Question 12 215003 A2.03 Ability to predict impact of a Stuck Detector (2.03) on IRMs and use procedures to correct. DAEC has no procedures for a stuck detector. (Checked ARPs, OIs, and System Descriptions) A stuck detector would read higher or lower than normal but those are covered by other K/As. All other A.2 topics for IRMs would conflict with a scenario segment for an upscale/inoperable IRM. Randomly selected another T2 G1 System, HPCI 206000, and randomly selected another A.2 topic, A2.09, on low CST level.

SRO Tier 2 Group 1 Question 15 262002 2.4.30 Uninterruptible AC was combined with the Knowledge of system events that should be reported to outside agencies. A loss of UPS was used as the bases for SRO T1G1 295006 so another question on this topic would conflict.

Randomly Selected System 215005, APRM/LPRM, as a replacement. 2.4.30 remained as the Generic topic.

SRO Tier 3 Question 22 2.2.33 2.2.33 Knowledge of control rod programming could not be converted into a relevant SRO level question. Programming at DAEC is performed by the Reactor Engineers who load the program into the Rod Worth Minimizer. All questions must therefore be systems questions about the RWM bases, procedure, or hardware. Randomly selected Generic 2.2.21 Knowledge of pre and post maintenance operability requirements as a replacement.

SRO Tier 3 Question 23 2.3.2 2.3.2 Knowledge of ALARA was randomly selected first for the RO exam.

Randomly selected 2.3.3 Knowledge of SRO responsibilities for Auxiliary systems outside of control room as a replacement for the SRO Exam SRO Tier 3 Question 24 2.3.6 2.3.6 Knowledge of requirements for reviewing and approving release permits.

This activity is not relevant to the DAEC. The Radwaste Liquid Release line at DAEC has been isolated for more than 25 years. Randomly selected 2.3.9, Knowledge of the process for performing a containment purge as a replacement for the SRO Exam.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:__DAEC___________ Date of Examination:__1/31/05 Exam Level (circle one):SRO I/U Operation Test 2005-01 No.:_____________

Administrative Topic (see note)

Type Code*

Describe Activity to be performed Conduct of Operations S, N Interpret the 1200 DW Equipment and Floor drain sumps, calculation per STP 3.0.0-01.

Determine that the reading is out of spec high.

Take the directed actions of STP 3.0.0-01

[2.1.2]

Conduct of Operations S, N Worker Call out. Determine if it is acceptable for RO to assume the watch in a Licensed Control Room position.

The SRO will ensure that the Overtime limits are not exceeded and if their license is currently active.

Based on the information given, the operator will not be eligible to stand the watch.

[2.1.7]

Equipment Control S, N Review a Work Order for closure IAW ACP 1408.1

[2.2.19]

Radiation Control S, N Review a survey map and RWP for an area in the plant.

Determine the exposure, the exposure limit are acceptable when compared to the RWP. (HPPs 31.03.3 for Survey map, and 3101.5 for the RWP requirements.

In addition determine if the worker will need a dose extension.

[2.3.10]

Emergency Plan S, N Given plant conditions, determine the proper EAL, fill out Emergency Plan Note 5, (Notification).

[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 (D)irect from bank ) 3 for ROs; 4 for SROs and RO retakes (N)ew or (M)odified form bank including (1)

(P)reious 2 exams ( 1; randomly selected (S)imulator

ES-401 BWR Examination Outline Form ES-401-1 Facility: DAEC Date of Exam: 01/31/2005 RO K/A Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A 2 G

• Total 1

20 4

3 7

2 7

1 2

3

1.

Emergency Abnormal Plant Evolutions Tier Totals N/A N/A 27 5

5 10 1

26 3

2 5

2 12 3

0 3

2.

Plant Systems Tier Totals 38 6

2 8

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 10 2

2 2

1 7

Note: 1.

Ensure that at least two topics from every K/A 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 K/A 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 +/-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.

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 outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

4.

Select topics from as many systems and evolutions 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 K/As 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 K/A categories.

7.*

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8.

On the following pages, enter the K/A 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 table above. Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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ES-401 2

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 E

d Ab l Pl t E l ti Ti 1/G 1 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G K/A Topic(s)

IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X

2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.(CFR: 41.10 / 43.5 / 45.13) 3.9 1

295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Pwr / 6 X

AA2.02 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : (CFR: 41.10 / 43.5 / 45.13) Extent of partial or complete loss of D.C. power 3.9 1

295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 X

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics

/ reactor behavior / and instrument interpretation. (CFR:

43.5 / 45.12 / 45.13) 4.4 1

295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 295019 Partial or Total Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 X

2.1.14 Knowledge of system status criteria which require the notification of plant personnel. (CFR: 43.5 / 45.12) 3.3 1

295026 Suppression Pool High Water Temp. / 5 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 X

EA2.04 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE:

(CFR: 41.10 / 43.5 / 45.13) Drywell pressure 4.2 1

295030 Low Suppression Pool Wtr Lvl / 5 X

EA2.03 Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL : (CFR: 41.10 / 43.5 / 45.13) Reactor pressure 3.9 1

295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 X

AA2.02 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Damper position 2.9 1

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ES-401 2

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 E

d Ab l Pl t E l ti Ti 1/G 1 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G K/A Topic(s)

IR K/A Category Totals:

4 3 Group Point Total:

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ES-401 3

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G K/A Topic(s)

IR 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 X

2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 3.8 1

295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 X

2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 3.8 1

295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 X

EA2.02 Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13) 3.1 1

500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:

1 2

Group Point Total:

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ES-401 3

Form ES-401-1 ES-401, Page 18 of 33 e:\\daec 2005\\daec 75 day submital outline\\sro exam nureg-1021 rev 9 form es-401-1 bwr examination outline.doc 5/5/2005 1:31 PM

ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 203000 RHR/LPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI X

A2.09 Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Low condensate storage tank level:

BWR-2,3,4 3.7 207000 Isolation (Emergency) Condenser 209001 LPCS 209002 HPCS 211000 SLC 212000 RPS X

A2.01 Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) RPS motor-generator set failure 3.9 1

215003 IRM 215004 Source Range Monitor 215005 APRM / LPRM X

2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies. (CFR: 43.5 /

45.11) 3.6 1

217000 RCIC 218000 ADS X

2.1.14 Knowledge of system status criteria which require the notification of plant personnel. (CFR: 43.5 / 45.12) 3.3 1

223002 PCIS/Nuclear Steam Supply Shutoff X

A2.05 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to 3.6 1

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ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Nuclear boiler instrumentation failures 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals:

3 2

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ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 201001 CRD Hydraulic X

A2.10 Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Low HCU accumulator pressure/high level 3.6 1

201002 RMCS X

A2.01 Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /

45.6) Rod movement sequence timer malfunctions 2.8 1

201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

X A2.05 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6) High 3.6 1

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ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR containment/drywell oxygen concentration 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals:

3 0

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ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: DAEC Date of Exam: 01/31/2005 RO SRO-Only Category K/A #

Topic IR IR 2.1.12 2.1.12 Ability to apply technical specifications for a system.

(CFR: 43.2 / 43.5 / 45.3) 4.0 1

2.1.25 2.1.25 Ability to obtain and interpret station reference materials such as graphs / monographs / and tables which contain performance data.

(CFR: 41.10 / 43.5 / 45.12) 3.1 1

2.1.

2.1.

2.1.

2.1.

1.

Conduct of Operations Subtotal 2

2.2.27 2.2.27 Knowledge of the refueling process.

(CFR: 43.6 / 45.13) 3.5 1

2.2.21 2.2.21 Knowledge of pre and post maintenance operability requirements. (CFR: 43.2) 3.5 1

2.2.

2.2.

2.2.

2.2.

2.

Equipment Control Subtotal 2

2.3.3 2.3.3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control room (e.g. / waste disposal and handling systems).

(CFR: 43.4 / 45.10) 2.9 1

2.3.9 2.3.9 Knowledge of the process for performing a containment purge.

(CFR: 43.4 / 45.10) 3.4 1

2.3.

2.3.

2.3.

2.3.

3.

Radiation Control Subtotal 2

2.4.46 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. (CFR: 43.5 / 45.3 / 45.12) 3.6 1

2.4.

2.4.

2.4.

2.4.

2.4.

4.

Emergency Procedures

/ Plan Subtotal 1

Tier 3 Point Total 7

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ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 ES-401, Page 26 of 33 e:\\daec 2005\\daec 75 day submital outline\\sro exam nureg-1021 rev 9 form es-401-3 generic knowledge and abiliities outline tier 3.doc Page 2 of 2 5/5/2005 1:35 PM

ES-301 Control Room/In-plant Systems Outline Form ES-301-2 Facility:__DAEC___________ Date of Examination:__1/31/05___

Exam Level (circle one): SRO-I Operation Test No.:__2005-01____

Control Room Systems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. CRD Exercise with a rod Overtravel. (201003-06)

D, A, S 1

b. Install Defeat #1 and use RCIC for Level Control. (217000-

12)

D, S, L 2

c. Isolate an MSIV at power. (239001-03)

N, S 3

d. Manual Start of Core Spray for injection. (209001-04)

N, S 4

e. Drain the Torus to Radwaste. AP to install defeat 13.

(219000-04)

N, A, S 5

f.

g. Install Defeat 4 with a Group 7 Isolation. (4000-02)

N, A, S 8

h. Establish Alternate Leakage Control IAW AOP 672.2.

(272000-03)

N, S 9

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

i. Shutdown of Regulating Transformer 1Y1A for maintenance. (AP requiring transfer of alternate RPS from 1Y16 to 1Y26) [262002-04]

N, A 6

j. Switch CRD Discharge Filters. (264000-08)

D, R 1

k. Establish Make-up Flow to RHRSW/ESW. (295018-01)

D, E, 8

All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate path (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow -power (N)ew or (M)odified form bank including 1(A)

(P)reious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1