ML16337A144

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2016 Dresden Nuclear Station Initial License Examination Outline Files - Form ES-401-1
ML16337A144
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/01/2016
From: Palagi B
NRC/RGN-III/DRS/OLB
To:
Exelon Generation Co
Shared Package
ML16257A678 List:
References
SVPLTR 16-0019
Download: ML16337A144 (9)
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Text

  • ES-401 Facility Name: Dresden BWR Examination Outline Date of Exam : 08/08/2016 RO KIA Category Points FORM ES-401-1 SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *
1. 1 3 4 3 3 4 3 20 4 3 7 Emergency &

Abnormal 2 1 1 1 N/A 2 1 N/A 1 7 1 2 3 Plant Evolutions Tier Totals 4 5 4 5 5 4 27 5 5 10 1 2 3 3 3 3 2 2 2 2 2 2 26 3 2 5 2.

Plant 2 1 1 1 1 1 1 1 1 2 1 1 12 0 1 2 3 Systems Tier Totals 3 4 4 4 4 3 3 3 4 3 3 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 1 3 3 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable KIA 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 KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category) .
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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KlAs 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 KIA categories.

7.* The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings

(!Rs) 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, !Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic KIAs

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE #I Name I Safety Function IR #

295001 Partial or Complete Loss of Forced 0 3.2 Core Flow Circulation I 1 & 4 2 0 Kno.,..edge of the operational implications of the following concepts as they apply to 295003 Partial or Complete Loss of AC I 6 Partial or Complete Loss of AC: Effect of battery discharge rate on capacity 2.7 0 Kno.,..edge of the interrelations between Partial or Total Loss of DC Pwr and the 295004 Partial or Total Loss of DC Pwr I 6 following: D.C. bus loads 3.3 3

0 Kno.,..edge of the reasons for the following responses as they apply to Main Turbine 295005 Main Turbine Generator Trip I 3 Generator Trip: Bypass valve operation 3.8 7

0 Ability to operate and/or monitor the following as they apply to SCRAM: Recirculation 95006 SCRAM I 1 system 3.1 4

Ability to determine and/or interpret the following as they apply to Control Room 295016 Control Room Abandonment I 7 Abandonment: Reactor water level 4.2 295018 Partial or Total Loss of CCW I 8 Ability to interpret and execute procedure steps. 4.6 Ability to determine and/or interpret the following as they apply to Partial or Total Loss 95019 Partial or Total Loss of Inst. Air I 8 of Inst. Air: Status of safety-related instrument air system loads (see AK2.1-AK2.19) 3.6 0 Ability to operate and/or monitor the following as they apply to Loss of Shutdown 295021 Loss of Shutdown Cooling I 4 Cooling: Alternate heat removal methods 3.7 4

0 Kno.,..edge of the reasons for the following responses as they apply to Refueling 95023 Refueling Ace I 8 Accidents: Interlocks associated with fuel handling equipment 3.4 2

1 Kno.,..edge of the interrelations between High Drywall Pressure and the following:

95024 High Drywell Pressure I 5 Containment spray logic: Plant-Specific 3.8 5

0 Kno.,..edge of the operational implications of the following concepts as they apply to 295025 High Reactor Pressure I 3 High Reactor Pressure: Pressure effects on reactor power 3. 9 1

295026 Suppression Pool High Water 0 Kno.,..edge of the interrelations between Suppression Pool High Water Temp. and the emp. I 5 1 following : Suppression pool cooling 3. 9 295027 High Containment Temperature I 5 0 0 , ,.,.,..,...,...*,.. Kno.,..edge of the reasons for the following responses as they apply to High Drywall 295028 High Drywell Temperature I 5 Temperature: Emergency depressurization 3.6 1

0 Ability to operate and/or monitor the following as they apply to Low Suppression Pool 95030 Low Suppression Pool Wtr Lvl I 5 Wtr Lvl: ECCS systems (NPSH considerations): Plant-Specific 3.6 1

Ability to determine and/or interpret the following as they apply to Reactor Low Water 295031 Reactor Low Water Level I 2 Level: Adequate core cooling 4.6 295037 SCRAM Condition Present and Ability to evaluate plant performance and make operational judgments based on Reactor Power Above APRM Downscale or operating characteristics, reactor behavior. and instrument interpretation. 4.4 Unknown I 1 Ability to determine and/or interpret the following as they apply to High Off-site 95038 High Off-site Release Rate I 9 Release Rate: Off-site 3.3 0 Kno.,..edge of the operational implications of the following concepts as they apply to 00000 Plant Fire On Site I 8 1 *~wn::x11 Plant Fire On Site: Fire Fighting 2.9 2

700000 Generator Voltage and Electric Grid Kno.,..edge of the purpose and function of major system components and controls. 4.1 Disturbances I 6 3 4 3 3 Group Point Total: 2 ES-401, Page 34 of 50

ES-401 3 Form ES-401-1

  • ES-401 11--~~~~~~~~~~~~~~~..,..-~.---,,--.~"""""

E/APE #I Name I Safety Function 95002 Loss of Main Condenser Vac I 3 K K 2 3 0

4 BWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

K A 1

...... ...~~~~~~~~~~~~~~~~~~~~~~-.~~-.~~41 KIA Topic(s)

Kno.,,edge of the reasons for the follo.,,ng responses as they apply to Loss of Main Condenser Vac: Bypass valve closure Form ES-401-1 IR 3.4 95007 High Reactor Pressure I 3 0 0 Ab ility to operate and/or monitor the following as they apply to High Reactor Water 95008 High Reactor Water Level I 2 Level: Reactor water level control: Plant-Specific 3.7 1

95009 Low Reactor Water Level I 2 0 295010 High Drywell Pressure I 5 0 95011 High Containment Temp I 5 0 95012 High Drywell Temperature I 5 0 95013 High Suppression Pool Temp. I 5 0 95014 Inadvertent Reactivity Addition I 1 0 Ability to determine and/or interpret the following as they apply to Incomplete SCRAM:

95015 Incomplete SCRAM I 1 Control rod position 4.1 95017 High Off-site Release Rate I 9 0 95020 Inadvertent Cont. Isolation I 5 & 7 0 95022 Loss of CRD Pumps I 1 0 95029 High Suppression Pool Wtr Lvl I 5 Kno.,,edge of conditions and limitations in the facility license. 3.6 95032 High Secondary Containment Area 0

emperature I 5 295033 High Secondary Containment Area 0 Kno.,,edge of the operational implications of the following concepts as they apply to 3.9 Radiation Levels I 9 2 High Secondary Containment Area Radiation Levels: Personnel protection 95034 Secondary Containment Ventilation 0 Kno.,,edge of the interrelations between Secondary Containment Ventilation High 3.9 High Radiation I 9 6 Radiation and the following : PCIS/NSSSS: Plant-Specific 95035 Secondary Containment High 0

Differential Pressure I 5 95036 Secondary Containment High 0

Sump/Area Water Level I 5 0 Ability to operate and/or monitor the following as they apply to High CTMT Hydrogen 500000 High CTMT Hydrogen Cone. I 5 Cone.: Primary containment hydrogen instrumentation 3.4 1

KIA Category Totals: 2 Group Point Total: 7 ES-401, Page 35 of 50

ES-401 4 Form ES-401-1

  • ES-401 System # I Name 203000 RHR/LPCI: Injection Mode 1 2 3 4 5 6 1 BWR Examination Outline Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A 1.1 i

A A 3 4

..~

Q j

KIA Topic(s)

Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Form ES-401-1 IR 4.2 1

205000 Shutdown Cooling 0

2 ~

'I Knowledge of the physical connections and/or cause-effect relationships between Shutdown Cooling and the following: Reactor water level 3.6 1 0 Knowledge of electrical power supplies to the following: Turbine control circuits:

206000 HPCI 4 ~: - -

BWR-2, 3, 4 2.5 1 I\ Knowledge of the effect that a loss or malfunction of the Isolation (Emergency) 207000 Isolation (Emergency) 0 Condenser will have on following: Reactor water level (EPG's address the 3.8 1 Condenser 2

- - isolation condenser as a water source): BWR-2, 3 Knowledge of the physical connections and/or cause-effect relationships 1 0 between LPCS and the following: ECCS room coolers; Knowledge of LPCS 209001 LPCS design feature(s) and/or interlocks which provide for the following: Line break 2.9; 3 2 2 4 detection 209002 HPCS 0

~

Knowledge of electrical power supplies to the following: Explosive valves; 0 0 3.1; 211000 SLC Knowledge of the operational implications of the following concepts as they 2 2 4 apply to SLC: Explosive valve operation 3.1 Knowledge of the effect that a loss or malfunction of the RPS will have on 0 0 3.7; 212000 RPS following : RPS logic channels; Knowledge of the effect that a loss or 2 5 1 malfunction of the following will have on the RPS: A.G. electrical distribution 3.6 0 Ability to predict and/or monitor changes in parameters associated with 215003 IRM operating the IRM controls including: RPS status 3.6 1 3

  • 215004 Source Range Monitor 215005 APRM I LPRM 0

6 t-- -

Knowledge of Source Range Monitor design feature(s) and/or interlocks which provide for the following: IRM/SRM interlock; Ability to (a) predict the impacts of the following on the Source Range Monitor; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded Ability to monitor automatic operations of the APRM I LPRM including:

Annunciator and alarm signals 3.2; 2.7 3.2 2

1 217000 RCIC 0

-0 Ability to manually operate and/or monitor in the control room: ADS valve tail 218000 ADS 3.5 1

  • ~-:; 6 pipe temperature 223002 PCIS/Nuclear Steam Supply

~

Kno'Nledge of annunciator alarms, indications, or response procedures. 4.2 1 Shutoff 0 Ability to manually operate and/or monitor in the control room: Lights and 239002 SRVs 3.6 1

'** 7 I~ alarms 0

Ability to monitor automatic operations of the Reactor Water Level Control 259002 Reactor Water Level Control

..: 3 l*tl including: Changes in main steam flow 3.2 1 Ability to (a) predict the impacts of the following on the SGTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the I~

261000 SGTS 3.4 1

,, consequences of those abnormal conditions or operations: High secondary containment ventilation exhaust radiation Knowledge of the operational implications of the following concepts as they

~

262001 AC Electrical Distribution 0 0 iJ apply to AC Electrical Distribution: Breaker control; Ability to predict and/or 2.6; 2

2 5 monitor changes in parameters associated 'Nith operating the AC Electrical 3.2 Distribution controls includino: Breaker lineuos 0

~

Knowledge of the effect that a loss or malfunction of the following will have on 262002 UPS (AC/DC) 3 ~ the UPS (AC/DC): Static inverter 2.7 1 Knowledge of the operational implications of the following concepts as they 0

263000 DC Electrical Distribution 1

"':~ I~" apply to DC Electrical Distribution: Hydrogen generation during battery 2.6 1 charoino 0 Knowledge of EDGs design feature(s) and/or interlocks which provide for the 264000 EDGs 1) following: Local operation and control 3.3 1 7

0 300000 Instrument Air 2 i;,;." Knowledge of the effect that a loss or ma~unction of the Instrument Air will have on following: Systems having pneumatic valves and controls 3.3 1 I :;~

0 ~

~00000 Component Cooling Water Knowledge of electrical power supplies to the following: CCW pumps 2.9 1 1 '.;

KIA Cate g o ry Totals: 2 3 3 3 3 2 2 .J 2 2 t..3 Group Point Total: 26 ES-401, Page 36 of 50

ES-401-1 5 Form ES-401-1

1 K

2 K

3 K

4 K

5 K

6 A

1 BWR Examination Outline Plant Systems - Tier 2/Group 2 (RO)

A 3

A 4

l'i

~

KIA Topic(s)

Form ES-401-1 IR #

0 0

201003 Control Rod and Drive Mechanism 0 .,, ll Knowledge of the effect that a loss or malfunction of the following will have on 3 .3 1 1 :i.l the Control Rod and Drive Mechanism: Control rod drive hydraulic system 201004 RSCS 0 ra

f -

201005 RCIS 0 Ability to predict and/or monitor changes in parameters associated with 201006RWM operating the RWM controls including: Latched group indication: P-Spec(Not* 2 .9 1

-~ BWR6)

~02001 Recirculation 0 202002 Recirculation Flow Control 204000 RWCU

- - 0 0

~14000 RPIS 0

~

~Ability 215001 Traversing In-core Probe 0 to (a) predict the impacts of the following on the RBM; and (b) based on those predictions, use procedures to correct. control , or mitigate the 215002 RBM 3.1 1 consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR*3, 4, 5

-~ Ability to monitor automatic operations of the Nuclear Boiler Inst. including:

0

~16000 Nuclear Boiler Inst.

Relationship between meter/recorder readings and actual parameter values: 3.4 1 1

Plant-Specific 219000 RHR/LPCI: Torus/Pool Cooling 0

Mode 0

223001 Primary CTMT and Aux.

~

-~1*:

~26001 RHR/LPCI: CT MT Spray Mode

~30000 RHR/LPCI: Torus/Pool Spray Mode

-0 4

Ability to manually operate and/or monitor in the control room : Minimum flow valves 3 .1 0

1

~33000 Fuel Pool Cooling/Cleanup 0

~34000 Fuel Handling Equipment 0 239001 Main and Reheat Steam Ability to locate and operate components, including local controls. 4.4 1 239003 MSIV Leakage Control 0 Knowledge of the physical connections and/or cause-effect relationships 241000 ReactorfTurbine Pressure Regulator 3

8

~ between ReactorfTurbine Pressure Regulator and the following: PCIS/NSSSS: 2 .7 1 I<  ! Plant-Specific 1-;

~45000 Main Turbine Gen. I Aux.

~ 0 0

256000 Reactor Condensate Knowledge of electrical power supplies to the following: System pumps 2.7 1 1

0 Knowledge of the effect that a loss or malfunction of the Reactor Feedwater will 259001 Reactor Feedwater 3 .~ have on following: HPCI: Plant-Specific 3 .3 1 268000 Radwaste 0 0

- - Knowledge of Offgas design feature(s) and/or interlocks which provide for the 271000 Offgas 2.7 1 6 following: Decay of fission product gases to particulate daughters 272000 Radiation Monitoring 0

1 .__

Knowledge of the operational implications of the following concepts as they apply to Radiation ~itoring : Hydrogen injection operation's effect on process radiation indications: Plant-Specific 3.2 1 286000 Fire Protection .~ ~ 0

! 0 Ability to monitor automatic operations of the Plant Ventilation including:

288000 Plant Ventilation 3.8 1 r 1 ' Isolation/initiation signals 290001 Secondary CTMT ~. ~ 0 290003 Control Room HVAC I*! 0 290002 Reactor Vessel Internals -~ .*~ 0

~

KIA Category Totals: 1 1 1 1 1 1 1 l.l 2 1 .J Group Point Total : 12 ES-401, Page 37 of 50

ES-401 2 Form ES-401-1

  • ES-401 11-~~~~~~~~~~~~~~~-r-~r---,~-,-~...,.l!lll E/APE #I Name I Safety Function 95001 Partial or Complete Loss of Forced 1 2 BWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

K K K A 3 1

-~~~~~~~~~~~~~~~~~~~~~~-.-~~..-~--n KIA Topic(s)

Form ES-401-1 IR #

0 ore Flow Circulation / 1 & 4 Ability to determine and/or interpret the following as they apply to Partial 95003 Partial or Complete Loss of AC I 6 3.7 or Complete Loss of AC: Cause of partial or complete loss of A.C. power 95004 Partial or Total Loss of DC Pwr / 6 Ability to apply Technical Specifications for a system. 4.7 95005 Main Turbine Generator Trip I 3 0 95006 SCRAM I 1 0 95016 Control Room Abandonment 17 0 95018 Partial or Total Loss of CCW / 8 0 Ability to determine and/or interpret the following as they apply to Partial 95019 Partial or Total Loss of Inst. Air I 8 3.6 or Total Loss of Inst. Air: Instrument air system pressure 295021 Loss of Shutdown Cooling I 4 0 95023 Refueling Ace I 8 0 295024 High Drywell Pressure I 5 0 95025 High Reactor Pressure I 3 0 295026 Suppression Pool High Water Knowledge of EOP mitigation strategies. 4.7 emp. / 5 95027 High Containment Temperature I 5 0 Ability to determine and/or interpret the following as they apply to High 295028 High Drywell Temperature I 5 4.1 Drywell Temperature: Drywall temperature 95030 Low Suppression Pool Wtr Lvl / 5 0 95031 Reactor Low Water Level I 2 0 95037 SCRAM Condition Present Ability to recognize abnormal indications for system operating parameters nd Reactor Power Above APRM that are entry-level conditions for emergency and abnormal operating 4.7 Downscale or Unknown I 1 procedures.

95038 High Off-site Release Rate I 9 0 Ability to determine and/or interpret the following as they apply to Plant 00000 Plant Fire On Site I 8 3.8 Fire On Site: Need for emergency plant shutdown 700000 Generator Voltage and Electric Grid 0

Disturbances I 6 KIA Category Totals: 0 0 0 0 7 ES-401, Page 34 of 50

E/APE #I Name I Safety Function K

1 K

2 K A 3 1 3

BWR Examination Outline Emergency and Abnonnal Plant Evolutions - Tier 1/Group 2 (SRO)

~~~~~~~~~~~~~~~~~~~~~~~~~~--n KIA Topic(s)

Form ES-401-1 Fann ES-401-1 IR #

295002 Loss of Main Condenser Vac I 3 Ability to prioritize and interpret th e significance of each annunciator or alarm. 4.3 295007 High Reactor Pressure I 3 0 95008 High Reactor Water Level/ 2 0 Ability to determine and/or interpret the followi ng as they apply to Low Reactor Water 295009 Low Reactor Water Level I 2 Level: Steam flowlfeedflow mismatch 3.7 95010 High Drywall Pressure I 5 0 295011 High Containment Temp I 5 0 95012 High Drywall Temperature/ 5 0 295013 High Suppression Pool Temp. / 5 0

  • 95014 Inadvertent Reactivity Addition/ 1 95015 Incomplete SCRAM / 1 95017 High Off-site Release Rate I 9 0

0 0

95020 Inadvertent Cont. Isolation I 5 & 7 0 295022 Loss of CRD Pumps / 1 Knowledge of abnormal condition procedures. 4.2 95029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0

emperature I 5 95033 High Secondary Containment Area 0

Radiation Levels I 9 95034 Secondary Containment Ventilation 0

High Radiation I 9 295035 Secondary Containment High Differential Pressure I 5 0

95036 Secondary Containment High Sump/Area Water Level/ 5 0

500000 High CTMT Hydrogen Cone. I 5 0 0 0 0 0 Group Point Total: 3 ES-401, Page 35 of 50

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES -401-1 Plant Systems - Tier 2/Group 1 (SRO)

  • System#/ Name 203000 RHR/LP Cl: Injection 205000 Shutdown Cooling Mode K K K K K K A 1 2 3 4 5 6 1 1;

.l A A 3 4

  • '~

1**

rial KIA Topic(s)

Ability to (a) predict the impacts of the following on the RHR/LPCI : Injection Mode; and (b) based on those predictions, use procedures to correct, control ,

or mitigate the consequences of those abnormal conditions or operations:

Valve closures IR 3.3 0

1

~

Knowledge of how abnormal operating procedures are used in conjunction with 206000 HPCI EOPs.

4.5 1 I*

~ Ability to (a) predict the impacts of the following on the Isolation (Emergency) 207000 Isolation (Emergency) Condenser; and (b) based on those predictions, use procedures to correct, control , or mitigate the consequences of those abnormal conditions or 4.0 1 Condenser operations: Insufficient shell side makeup flow: BWR-2, 3 209001 LPCS 0 209002 HPCS 0 211000SLC fl 0 212000 RPS 0 215003 IRM r Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

4.6 1 215004 Source Range Monitor 0

Ability to (a) predict the impacts of the following on the ADS ; and (b) based on those predictions, use procedures to correct, control , or mitigate the consequences of those abnormal conditions or operations: ADS failure to initiate 4.2 0

0 1

223002 PCIS/Nuclear Steam Supply 0

Shutoff 239002 SRVs l:i 0

~

I~

259002 Reactor Water Level Control 1-'

0 I> ~'

261000 SGTS

~~ 0

!cir, 262001 AC Electrical Distribution 0 1.~

262002 UPS (AC/DC) . 0 263000 DC Electrical Distribution 1 I r~ 0 264000 EDGs t:~ 0 300000 Instrument Air H ~i 0

[ ,~ ~';

400000 Com ponent Cooling Water 0 1*~

KIA Category Totals: 0 0 0 0 0 0 0

~ 0 0 ~ Group Point Total : 5 ES-401, Page 36 of 50

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)

K K K K K K A A A

!System# I Name 1 2 3 4 5 6 1 'I 3 4 c KIA Topic(s) IR #

1201001 CRD Hydraulic I 0

1201002 RMCS 0 1201003 Control Rod and Drive Mechanism *, 0 1201004 RSCS 0

?01005 RCIS 0 201006 RWM J 0 Ill 202001 Recirculation

II!

Kno'Medge of limiting conditions for operations and safety limits. 4.7 1 202002 Recircu lation Flow Control ' *~ 0 204000 RWCU I u  :

0

?14000 RPIS 0 b

215001 Traversing In-core Probe 0

,' 1;~

215002 RBM 0

  • I '

216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling Mode  ;;' 0 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode

. 0 230000 RHR/LPCI: Torus/Pool Spray Mode f> 0 Ability to (a) predict the impacts of the follo...;ng on the Fuel Pool

~

Cooling/Cleanup; and (b) based on those predictions , use procedures to correct, 233000 Fuel Pool Cooling/Cleanup control, or mitigate the consequences of those abnormal conditions or 2.9 1 operations: A.C. electrical power failures

  • r:* ~;.- ~1 ~ [t. ~

234000 Fuel Handling Equipment

<< ~...,

""J ~

J 0

239001 Main and Reheat Steam , 0 239003 MSIV Leakage Control ~ ,; 0 241000 Reactor/Turbine Pressure Regulator *j 0 245000 Main Turbine Gen. I Aux. ' l!M Ability to diagnose and recognize trends in an accurate and timely manner I~ utilizing the appropriate control room reference material.

4.2 1 256000 Reactor Condensate  ; 0 259001 Reactor Feedwater

  • i 0 268000 Radwaste

. ~

0 271000 Offgas ~

0 272000 Radiation Monitoring 0 286000 Fire Protection ~ I"' 0 i

288000 Plant Ventilation 0 290001 Secondary CTMT

.. . 0 290003 Control Room HVAC ' 0 290002 Reactor Vessel Internals 0 0 0 0 0 0 0 0 1 0 0 3 Group Point Total: 3 ES-401, Page 37 of 50

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