ML102600038

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Draft - Outlines (Folder 2)
ML102600038
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/07/2010
From:
Public Service Enterprise Group
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML100560172 List:
References
TAC U01788, 50-354/10-301, ES-401, ES-401-1 50-354/10-301
Download: ML102600038 (32)
v • d • e


Text

ES-401 Written Examination Outline Form ES-401-1 Facility: Hope Creek Station Date of Exam: August 23, 2010 SRO-Only Points Tier Group K G Total A2 G* Total 1.

3 2 20 4 3 7 Emergency 2 1 1 1 7 2 1 3 Plant Evaluations Tier 4 3 27 6 4 10 Totals 1 2 2 26 2 3 5 2.

2 1 1 12 0 2 3 Plant Systems Tier 3 3 38 3 5 8 Totals

3. Generic Knowledge & Abilities 1 2 3 4 10 1 2 3 4 7 3 3 2 2 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 catHgory in Tier 3 of the SRO-only outline, the Tier Totals in each KiA 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 section D.1.b of ES-401, for guidance regarding 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 KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the HO and SRO-only portions, respectively.
6. Select SHO 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 KiA's

8. On the following pages, enter the KiA 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. 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, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KiAs that are linked to

~_________ 1~O~C~F~R~5~f.i~.4~3___________________________________________________________________~

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function I K1 I K21 K31 A1 I A2 E.-----LI____Kl_A_T_O_Pi_c(_S)_ _ _---'-I_fm_p_. ...L:_0#--,1 AA2.05 - Ability to determine and/or interpret the following i295018 Partial or Total as they apply to PARTIAL

.2.9 76

  • Loss of CCW / 8 OR COMPLETE LOSS OF COMPONENT COOLING WATER: ure AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL 295019 Partial or Total OR COMPLETE LOSS OF 3.6 77 i Loss of Inst. Air I 8 INSTRUMENT AIR:

ressure AA2.02 - Ability to determine and/or interpret the following as they apply to PARTIAL 295004 Partial or Total OR COMPLETE LOSS OF 3.9 78 Loss of DC Pwr I 6 D.C. POWER: Extent of partial or complete loss of D.C. ower EA2.01 - Ability to determine and/or interpret the following .

295030 Low Suppression as they apply to LOW 4.2 79 Pool Water Level / 5 SUPPRESSION POOL WATER LEVEL:

ion level 2.2.38 - Equipment Control:

295023 Refueling Knowledge of conditions and 4.5 *80

  • Accidents I 8 limitations in the facility license.

295037 SCRAM Conditions' 2.2.40 - Equipment Control:

  • Present and Reactor Power Ability to apply technical 4.7 81 iAbove APRM Downscale or specifications for a system.

Unknown /1 2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation / status that must be reported to

  • 295006 SCRAM / 'I 4.1 82 internal organizations or external agencies, such as the state, the NRC, or the transmission system

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AA2.02 - Ability to determine*

  • 600000 Plant Fire On-site 1
  • and interpret the following as 8 they apply to PLANT FIRE ON SITE: Da EK1.02 - Knowledge of the operational implications of the following concepts as 295031 Reactor Low Water. X they apply to REACTOR 3.8 40 Level 12 I LOW WATER LEVEL:

Natural circulation: Plant ific AK1.03 - Knowledge of the operational implications of 295006 SCRAM 1 1 . X the following concepts as 3.7 41 they apply to SCRAM:

control AK2.09 - Knowledge of the interrelations between 295019 Partial or Total PARTIAL OR COMPLETE 3.3 42 X

Loss of Inst. Air 1 8 LOSS OF INSTRUMENT AIR and the following:

Containment EK2.07 - Knowledge of the

  • 295024 High Drywell interrelations between HIGH 3.9 43 X

IPressure 1 5 DRYWELL PRESSURE and the foil  : PCISINSSSS EK2.01 - Knowledge of the 295025 High Reactor interrelations between HIGH Pressure 13 REACTOR PRESSURE and the fol  : RPS AK2.03 - Knowledge of the interrelations between LOSS 295021 Loss of Shutdown X OF SHUTDOWN COOLING 3.6 45 Cooling 14 and the following:

RHRlShutdown Cool EK3.02 - Knowledge of the reasons for the following 1295030 Low Suppression responses as they apply to 3 5 46 X

  • Pool Water Levell 5 LOW SUPPRESSION POOL . .

WATER LEVEL: HPCI c

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function AA 1.08 - Ability to operate and/or monitor the following 295016 Control Room as they apply to CONTROL 4.0 47 Abandonment / 7 ROOM ABANDONMENT:

Reactor Pressure EA 1.03 - Ability to operate and/or monitor the following 295038 High Off-site as they apply to HIGH OFF 3.7 48 Release Rate / 9 SITE RELEASE RATE:

Process liquid radiation monitori AA 1.02 - Ability to operate and/or monitor the following 295018 Partial or Total as they apply to PARTIAL 3.3 49 Loss of CCW / 8 OR COMPLETE LOSS OF COMPONENT COOLING WATER: loads AA1.0 1 - Abi Iity to operate and/or monitor the following 295005 Main Turbine as they apply to MAl N 3.1 50 Generator Trip / 3 TURBINE GENERATOR TRIP: Recirculation system:

Plant-Snor"T'"

AA2.02 - Ability to determine and/or interpret the following 295003 Partial or Complete as they apply to PARTIAL 4.2 51 Loss of AC /6 OR COMPLETE LOSS OF A.C. POWER: Reactor ower and level EA2.04 - Ability to determine and/or interpret the following as they apply to SCRAM 295037 SCRAM Conditions CONDITION PRESENT Present and Reactor Power AND REACTOR POWER 4.0 52 Above APRM Downscale or ABOVE APRM Unknown /1 DOWNSCALE OR UNKNOWN: Suppression tem rature EA2.03 - Ability to determine and/or interpret the following as they apply to 295026 Suppression Pool SUPPRESSION POOL 3.9 53 High Water Temp. 15 HIGH WATER TEMPERATURE: Reactor

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#lName Safety Function KJA Topic(s) 2.1.28 - Conduct of 700000 Generator Voltage Operations: Knowledge of and Electric Grid the purpose and function of 4.1 54 Disturbances major system components and controls.

AK3.02 - Knowledge of the reasons for the following 295023 Refueling responses as they apply to 3.4 55 Accidents I 8 REFUELING ACCIDENTS:

Interlocks associated with fuel handl 2.2.25 - Knowledge of the bases in Technical 295028 High Drywell Specifications for limiting 3.2 56 Temperature 15 conditions for operations and limits.

AK1.05 - Knowledge of the operational implications of the following concepts as 295004 Partial or Total Loss of DC Pwr I 6 x they apply to PARTIAL OR 3.3 57 COMPLETE LOSS OF D.C.

POWER: Loss of breaker nr",rCI"'Tion AA2.01 - Ability to determine andlor interpret the following 295001 Partial or Complete as they apply to PARTIAL Loss of Forced Core Flow OR COMPLETE LOSS OF 3.5 58 Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION: Powerlflow KIA Category Totals 342 Group Point Total: 2017

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#!Name Safety Function KIA Topic(s) \ Imp. I I Q#

AA2.02 - Ability to determine and/or interpret the following 295009 Low Reactor Water as they apply to LOW 3.7

  • 83 Level 12 REACTOR WATER LEVEL:

Steam flow/feed flow mismatch 2.4.45 - Emergency Procedures / Plan: Ability to 295002 Loss of Main prioritize and interpret the 4.3

  • 84 Condenser Vacuum / 3 significance of each annunciator or alarm.

EA2.02 - Ability to determine and/or interpret the following 295032 High Secondary as they apply to HIGH Containment Area SECONDARY

  • 3.5 85 Temperature / 5 CONTAINMENT AREA TEMPERATURE: Equipment AK1.02 - Knowledge of the operational implications of 295022 Loss of CRD Pumps /1 x the following concepts as 3.6 59 they apply to LOSS OF CRD PUMPS: Rea control AK2.01 - Knowledge of the interrelations between HIGH 295012 High Drywell DRYWELL TEMPERATURE i 3.4 60 Temperature / 5 and the following: Drywell ventilation EK3.02 - Knowledge of the reasons for the following 295036 Secondary responses as they apply to Containment High SECONDARY 2.8 61 Sump/Area Water Level/5 CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Reactor SCRAM AA 1.03 - Ability to operate and/or monitor the following 295009 Low Reactor Water as they apply to LOW 3.0 62 Level/2 REACTOR WATER LEVEL:

Recirculation system: Plant S ecific

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EA2.02 - Ability to determine and I or interpret the following as they apply to HIGH PRIMARY 500000 High CTMT CONTAINMENT 3.0 63 Hydrogen Conc. I 5 HYDROGEN CONCENTRATIONS:

295029 High Suppression 4.4 64 Pool Water Level/5 295010 High Drywell 3.6 65 Pressure / 5 Drywell floor and equipment drain sum KIA Category Totals Group Point Total: 7/3

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name A2.09 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET) ; and (b) based on those 264000 EDGs 4.1 86 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of A.C.

A2.07 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those 211000 SLC predictions, use 3.2 87 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve closures 2.4.50 - Emergency Procedures I Plan: Ability to verify system alarm 209001 LPCS 4.0 88 setpoints and operate controls identified in the 262001 AC maintenance activities, Electrical such as degraded power 4.2 89 Distribution sources, on the status of limiting conditions for s.

2.4.11 - Emergency 259002 Reactor Procedures I Plan:

Water Level Control 4.2 90 Knowledge of abnormal condition res.

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 K1.02 - Knowledge of the physical connections and/or cause- effect relationships between 215004 Source X SOURCE RANGE 3.4 1 Range Monitor MONITOR (SRM)

SYSTEM and the following: Reactor manual control K1.01 - Knowledge of the physical connections and/or cause- effect 262001 AC relationships between Electrical X 3.8 2 A.C. ELECTRICAL Distribution DISTRIBUTION and the following: Emergency K2.01 - Knowledge of electrical power supplies 2150031RM X 2.5 3 to the following: IRM channels/detectors A3.02 - Ability to monitor automatic operations of the REACTOR 259002 Reactor WATER LEVEL 3.4 4 Water Level Control CONTROL SYSTEM including: Changes in reactor water level K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC 218000 ADS X DEPRESSURIZATION 4.5 5 SYSTEM will have on following: Ability to rapidly depressurize the reactor K5.06 - Knowledge of the operational implications of the 239002 SRVs following concepts as 2.7 6 X they apply to RELI EF/SAFETY VALVES: Vacuum breaker 0

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

K4.02 - Knowledge of LOW PRESSURE CORE SPRAY SYSTEM 209001 LPCS x design feature(s) and/or 3.0 7 interlocks which provide for the following:

Prevents water hammer K4.04 - Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design 264000 EDGs x feature( s) and/or 2.6 8 interlocks which provide for the following: Field flash' K5.06 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE 215005 APRM /

LPRM x POWER RANGE 2.5 9 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

Assignment of LPRM's to c::n~~(,ITIC APRM channels K5.01 - Knowledge of the operational implications of the following concepts as they apply to STANDBY 211000 SLC x LIQUID CONTROL 2.7 10 SYSTEM: Effects of the moderator temperature coefficient of reactivity on the boron K6.01 - Knowledge of the effect that a loss or malfunction of the 262002 UPS following will have on the (AC/DC) x UNINTERRUPTABLE 2.7 11 POWER SUPPLY (A.C'/D.C.): A.C.

electrical

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 K6.05 - Knowledge of the effect that a loss or 400000 Com ponent X malfunction of the 2.8 12 Cooling Water following will have on the CCWS: Motors A 1.08 - Ability to predict and/or monitor changes in parameters associated with operating the HIGH 206000 HPCI PRESSURE COOLANT 4.1 13 INJECTION SYSTEM controls including:

System lineup: BWR 4

A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 203000 RHRlLPCI:

RHRlLPCI: INJECTION 3.9 14 Injection Mode MODE (PLANT SPECIFIC) controls including: Reactor A2.10 - Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING 205000 Shutdown MODE); and (b) based 2.9 15 Cooling on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions:

Valve

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name A2.01 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those 217000 RCIC 3.8 16 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation si nal A3.01 - Ability to monitor automatic operations of 263000 DC the D.C. ELECTRICAL Electrical DISTRIBUTION 3.2 17 Distribution 261000 SGTS 3.2 18 includi : Fan start 223002 A4.01 - Ability to PCIS/Nuclear manually operate and/or 3.6 19 Steam Supply monitor in the control Shutoff room: Valve closures A4.04 - Ability to manually operate and/or monitor in the control 212000 RPS 3.9 20 room: Bypass SCRAM instrument volume high level SCRAM si nal 2.4.35 - Emergency Procedures / Plan:

Knowledge of local 300000 Instrument auxiliary operator tasks 3.8 21 Air during emergency and the resultant operational effects.

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 System #fName KJA Topic(s) 2.2.39 - Equipment Control: Knowledge of 205000 Shutdown less than or equal to one Cooling 3.9 22 hour2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> technical specification action statements for ms.

K4.02 - Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or 212000 RPS X interlocks which provide 3.5 23 for the following: The prevention of a reactor SCRAM following a Ie com nent failure K5.03 - Knowledge of the operational implications of the following concepts as 217000 RCIC X they apply to REACTOR 2.6 24 CORE ISOLATION COOLING SYSTEM (RCIC): Differential re indication K6.02 - Knowledge of the effect that a loss or 262001 AC malfunction of the Electrical X following will have on the 3.6 25 Distribution AC. ELECTRICAL DISTRIBUTION: Offsite K4.09 - Knowledge of HIGH PRESSURE COOLANT INJECTION 206000 High SYSTEM Pressure Coolant deSign feature(s) and/or 3.8 26 X

Injection interlocks which provide for the following:

Automatic flow control:

4 KJA Category Totals 26/5

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KIA Topic(s)

A2.02 - Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those 290001 Secondary predictions, use 3.7 91 Containment procedures to correct, control, or mitigate the consequences of those abnormal conditions 272000 Radiation 4.0 92 Monitoring 241000 ReactorlTurbine 4.6 93 Pressure Regulator 259001 Reactor X 3.2 27 Feedwater and the following:

Condensate m K2.03 - Knowledge of 201001 CRD electrical power supplies X 3.5 28 Hydraulic to the following: Backup SCRAM valve solenoids K3.05 - Knowledge of the effect that a loss or malfunction of the 202001 RECIRCULATION X 3.3 29 Recirculation SYSTEM will have on following: Recirculation system MG sets: Plant cific

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KJA Topic(s) limp. I Q# I K4.03 - Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature( s) and/or 233000 Fuel Pool Cooling/Cleanup x interlocks which provide 2.8 30 for the following:

Maintenance of adequate pool tem rature K5.01 - Knowledge of the operational implications of the following concepts as they apply to 272000 Radiation RADIATION Monitoring x MONITORING SYSTEM:

3.2 31 Hydrogen injection operation's effect on process radiation indications: Plant K6.06 - Knowledge of the effect that a loss or malfunction of the 219000 RHRlLPCI: following will have on the Torus/Pool Cooling x RHRlLPCI: 3.7 32 Mode TORUS/SUPPRESSION POOL COOLING MODE: Suppression Pool A 1.10 - Ability to predict and/or monitor changes in parameters associated with operating the 226001 RHRlLPCI:

RHRlLPCI: 3.0 33 CTMT Spray Mode CONTAINMENT SPRAY SYSTEM MODE controls including: Emergency nerator load

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 2

. A2.07 - Ability to (a) predict the impacts of the following on the TRAVERSING IN-CORE PROBE; and (b) based on those predictions, use 215001 Traversing procedures to correct, 3.4 34 In-core Probe control, or mitigate the consequences of those abnormal conditions or operations: Failure to retract during accident conditions: Mark 1&1 Not-BWR1 A3.06 - Ability to monitor automatic operations of the MAIN TURBINE 245000 Main GENERATOR AND 2.5 35 Turbine Gen. / Aux.

AUXILIARY SYSTEMS including: Turbine lube oil re A4.06 - Ability to manually operate and/or 230000 RHRlLPCI: monitor in the control Torus/Pool Spray room: Valve logic reset 4.0 36 Mode following automatic initiation of LPCIIRHR in 215002 RBM 4.6 37 271000 Off-gas 3.3 38 KIA Category Totals Group Point Total: 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

~e Creek Generating Station Date: 08/23/2010

  • KA# Topic RO SRO-Only IR Q# IR Q#

Ability to explain and apply all system 2.1.32 3.8 66 limits and precautions.

Knowledge of procedures, guidelines, 2.1.37 or limitations associated with reactivity 4.3 67 management.

1. Conduct of Ability to interpret reference materials, 2.1.25 3.9 75 Operations such as graphs, curves, tables, etc.

2.1.41 t--

Knowledge of the refue~rocess. 3.7 94 Knowledge of conservative decision 2.1.39 4.3 99 making practices.

-- """:_.:Z, ..****. '.:i.::};;::

Subtotal 3 2 Ability to manipulate thB console controls as required to operate the 2.2.2 4.6 68 facility between shutdown and designated power levels.

Knowledge of less than or equal to one 2.2.39 hour technical specification action 3.9 73 statements for systems.

2.2.12 Knowledge of surveillance procedures. 3.7 74

2. Equipment Ability to perform pre-startup Control procedures for the facility, including 2.2.1 operating those controls associated 4.4 95 with plant equipment that could affect reactivity.

Knowledge of pre- and post-2.2.21 4.1 98 maintenance operability requirements.

Subtotal ~;\ 3 i*"">' ,".. , 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment 2.3.12 3.2 70 entry requirements, fuel handling responsibilities, access to locked high-radiation areas filte etc.

Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to 2.3.13 radiation monitor alarms, containment 3.4 71

3. Radiation entry requirements, fuel handling Control responsibilities, access to locked high radiation areas filters etc.

to control radiation releases. 4.3 96 Subtotal 1 Knowledge of EOP entry conditions and 2.4.1 4.6 69 immediate action ste .

Ability to recognize abnormal indications for system operating 2.4.4 parameters which are entry-level 4.5 72 conditions for emergency and abnormal

4. Emergency rocedures.

Procedures I ~~---+~~~~~~~~.----------~----~----~--~----

Plan Tier 3 Point Total:

ES-401 Record of Rejected KIA's Form ES-401-4 Ti J"o, ~ndom:b.selected Reason for Rejection I

(RO #1) - Knowledge of the physical connections and/or cause-effect relationships between SOURCE RANGE MONITOR (SRM) SYSTEM and the following: Rod Control and Information 2/1 215004/ K1.03 System: Plant Specific. This topic does not apply at HC.

Randomly selected K1.02 - Reactor manual control (RO #4) - Knowledge of electrical power supplies to the following: Feedwater Coolant Injection (FWCI) initiation logic:

FWCI/HPCI. FWCI does not apply at Hope Creek 2/1 2590021 K2.02 Randomly selected ,- A3.02 - Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including: Changes in reactor water level

{RO #6} - Knowledge of the effect that a loss or malfunction of the RELIEF/SAFETY VALVES will have on following: Ability to rapidly depressurize the reactor. Same topic as RO #5 2/1 239002 / K3.03 Randomly selected K5.06 - Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES: Vacuum breaker operation (RO #9) - K5.02 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM: Effects of voids on LPRM indication. Topic is GFES knowledge and is not referenced in system operating or lesson 2/1 215005 I K5.02 plan procedums.

Randomly selected K5.06 - Assignment of LPRM's to specific APRM channels (RO #2) K1.04 - Knowledge of the physical connections and/or cause- effect relationships between AC. ELECTRICAL DISTRIBUTION and the following: Uninterruptible power supply.

Similar to RO #11 topic K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 2/1 262001 / K1.04 UNINTERRUPTABLE POWER SUPPLY (AC.lD.C.): AC.

electrical power.

Randomly selected K1.01 - Emergency generators (RO #16) - A2,05 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 2f1 217000/ A2.05 those abnormal conditions or operations: D.C. power loss. D.C.

is oversampled. See questions 17, 57, 78.

Randomll selected A2.01 - System initiation signal

ES-401 Record of Rejected KIA's Form ES-401-4 (RO #20) - Ability to manually operate and/or monitor in the control room: Individual system relay status: Plant-Specific.

Does not apply at Hope Creek.

2/1 212000/ A4.08 Randomly selected A4.04 - Bypass SCRAM instrument volume high level SCRAM signal (RO #25) - Knowledge of the effect that a loss or malfunction of the following will have on the A.C. ELECTRICAL DISTRIBUTION: D.C. power. DC Topic is oversampled. See 2/1 262001 / K6.01 #17,57,78 Randomly selected K6.02 Offsite Power (RO #26) -Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Inadequate system flow. System is oversampled. See questions 10 & 87 2/1 2110001 A2.02 Randomly selElcted 206000 K4.09 - Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Automatic flow control: BWR-2,3,4 (RO #29) - Knowledge of the effect that a loss or malfunction of the RECIRCULATION SYSTEM will have on following: Isolation condenser: Plant-Specific. Does not apply at Hope Creek 2/2 202001 1 K3.12 Randomly selected K3.05 - Knowledge of the effect that a loss or malfunction of the RECIRCULATION SYSTEM will have on following: Recirculation system MG Sets: Plant-Specific (RO #39) - Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fighting. This does not apply at Hope Creek. A separate Fire Fighting department exists.

1 11 6000001 AK1.02 Randomly selected M2.05 - Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Ventilation alignment necessary to secure affected area (RO #45) - AK3.01 .. Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING:

Raising reactor water level. Same concept as RO #40.

1 /1 295021 1 AK3.01 Randomly selected AK2.03 - Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following:

RHRlShutdown Cooling (RO #47) - Knowledge of the reasons for the following responses 1 /1 2950161 AK3.01 as they apply 1.0 CONTROL ROOM ABANDONMENT: Reactor SCRAM. No p",ocedural guidance to support the reason for a scram

ES-401 Record of Rejected KIA's Form ES-401-4 Randomly selected AA1.08 - Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT:

Reactor Pressure (RO #49) - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Affected systems so as to isolate damaged 1 11 2950181 AA1.03 portions. Limited procedural guidance for discriminating question.

  • Randomly selected AA 1.02- System loads .

I (RO #54) 2.4.6 Emergency Procedures/Plan: Knowledge of EOP Mitigation Strategies (grid disturbances). No EOP mitigation strategies associated with grid disturbances.

1 /1 700000 I 2.4.6 Randomly selected 2.1.28 Conduct of Operations: Knowledge

  • of the purpose and function of major system components and controls.

I (RO #55) - Emergency Procedures / Plan: Knowledge of how abnormal operating procedures are used in conjunction with EOP's. Question #69 covers similar topic/system.

1/1 295023/2.4.8

  • Randomly selected K3.02 Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS:

Interlocks associated with fuel handling equipment.

(RO #65) - 2.4.41 Emergency Procedures I Plan: Knowledge of the emergency action level thresholds and classifications. This function is not performed by ROs at Hope Creek.

1/2 295010/2.4.41

  • Randomly selected AA 1.02 - Ability to operate and/or monitor the
  • following as they apply to HIGH DRYWELL PRESSURE: Drywell floor and equipment drain sumps (RO #56) - EqJipment Control: Knowledge of surveillance procedures. There are no surveillance procedures associated with High Drywell Temperature.

1/1 295028/2.2.12 Randomly selected 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety I- +____-+I_ _ _ _ _ _ _-+'Ii=m:,::it:=,s':-:'(.I,,=H':'.Sig..,.lh.:...:D:::.,~ Temperatur~},~~_~---::-:-:-----:--~~-::-----l (RO #39) Ability to determine and interpret the following as they lapply to PLANT FIRE ON SITE: Ventilation alignment necessary to secure affected area. Oversampled due to overlap with 1 11 6000001 AA2.05

  • operating exam.

I Randomly selected AA2.02- Damper pO!:lit~io~n~ _ _ _ _ _ _-i (SRO # 79) - Unable to produce a discriminating question at the SRO level.

1 11 295030 I 2.4.35 Randomly selected A2.01 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL

  • Suppression pool level

ES-401 Record of Rejected KJA's Form ES-401-4 (SRO #84) - Emergency Procedures / Plan: Abiiity to prioritize and interpret the significance of each annunciator or alarm. (Secondary Containment Ventilation Hi Rad). This topic was oversampled. See # 18, 1/2 295034/2.4.45 71,80.

Randomly selected 295002 - Loss of Main Condenser Vacuum (SRO #93) Conduct of Operations: Ability to interpret and execute procedure steps. (Radwaste). Procedure steps for Radwaste are performed by operators at the local radwaste control room and not 2/2 268000/2.1.20 directed by the SRO.

Randomly selected 241000 ReactorlTurbine Pressure Regulator (SRO #91) Ability to (a) predict the impacts of the following on the FUEL POOL COOLING & CLEANUP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Closed cooling waterfailure. Topic/system covered in RO exam - oversampled 2/2 233000 I A2.08 Randomly selected 290001 A2.02 - Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences cf those abnormal conditions or operations: Excessive out leakage (SRO #100) Knowledge of procedures relating to a security event (non-safeguards information). These procedures except for generic information are deSignated as confidential or safeguards. Could not 3 2.4.28 write a discriminating SRO question using non-safeguards information.

Randomly selected 2.4.25 - Knowledge of fire protection procedures

HC ILT 2010 NRC EXAM ES*301 Administrative Topics Outline Form ES-301-1

  • Facility: Hope Creek Date of Examination: 8/23/10 Examination Level: ~ RO D SRO Operating Test Number: NRC 2010 Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.18 Ability to make accurate, clear, concise logs, records, status boards and reports.

  • RO: 3.6 Conduct of Operations N,S,A Perform surveillance HC.RE.ST.ZZ-0001 Core Thermal Limits with 2 limits out of spec. (NEW)

I 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

RO: 4.1 Conduct of Operations D,R,P ZZ030 Generate Off Normal Report.

i (Shiftly Routine for Control Room NCO) (2009 NRC RO) 2.2.12 KnowlE~dge of surveillance procedures.

RO 3.7 Equipment Control D,S,A ZZ025 Perform an Accident Monitoring Instrumentation Channel Cheek.

295038 A 1.01 Ability to operate and/or monitor the I

  • following as they apply to HIGH OFF-SITE RELEASE IRATE: Stack gas monitoring system Radiation Control D,S RO: 3.9 ZZ020 Calculate Total Noble Gas Release Rate.

Emergency Plan NA NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required .

. *Type Codes & Criteria: (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (~ 3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~1)

(P)revious 2 exams (:51; randomly selected)

(A)lternate Path

HC ILT 2010 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility: Ho~e Creek Date of Examination: 8/23/2010 Examination Level: D RO ~ SRO Operating Test Number: NRC 2010 Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.18 Ability to make accurate, clear, concise logs, records, status boards and reports Conduct of Operations M,R SRO 3.8 (MODIFIED Bank) ZZ041 Verify DL-26 log requirements for resuming Core Alterations.

2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

Conduct of Operations D, R,A SRO 4.0 ZZ031 Initiate And Review System Lineup Sheets. (2 valves out of position) 2.2.23 Ability to track limiting conditions for operation and safety limits.

Equipment Control D,R SRO 4.6 ZZ029 Complete an Action Statement in the TSAS log 2.3.11 Ability to control radiation releases.

SRO: 4.3 D, P, R, ZZ032 Perform Leak Rate Measurement Data Sheet Radiation Control A (Review of completed surveillance determines math error made and actual leakage exceeds Tech Spec.

Determine required actions) (2009 NRC SRO) 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

Emergency Plan M,R SRO: 4.4 (MODIFIED Bank) ECG004 Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol Room, (S)imulator, or Class{R)oom

{D)irect from bank (:5 3 for HOs; :5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~1)

(P)revious 2 exams (:51; randomly selected)

(A)lternate Path

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Date of Examination: 8/23/10 Exam Level: RO !Kl SRO-I D SRO-U D Operating Test No.: NRC2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1JPM Title Type Code* Safety Function

a. AE009 Start a Secondary Condensate Pump (256000 A4.01) S,D,L 2
b. CH002 Respond To A Low Turbine Hydraulic Pressure (241000 A2.06) S,D, A 3
c. BJ006 Place HPCI In Full Flow Recirc (206000 A4.06) S,D, E,L 4
d. KL003 Operate The PCIG System During Post LOCAllsolation S,A,E, EN,N 5 Conditions (223001 A4.11)
e. EG008 Respond To A Safety Auxiliaries Cooling Water Malfunction S,D, E,A 6 (295018 AA 1.02)
f. SB004 Respond To A Control Rod System Malfunction (295015 S,D, E,A 7 AA1.02)
g. ED001 Manually Switch between Chill Water and The Reactor Auxiliary S,D,E 8 Cooling System (RACS) (295018 AA1.01)
h. GK002 Isolate Control Room HVAC (290003 A4.01} S,A, N 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO ..U)
i. SA001 Defeat ARI Interlocks (295037 EA1.03) D, E 1
j. BE002 Perform Torus Makeup Via Core Spray System (NRC2009) 0, E, R, P, L 2 (295030 EA 1.06)
k. KJ003 Manually Emergency Start A Diesel Generator From The Local D, L 6 Panel (295003 EA1.02)

@ All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 14-61 2-3 (C}ontrol room (D)irect from bank  ::;91::;8/s4 (E)mergency or abnormal in-plant  ;:::1/;:::1/;:::1 (EN}gineered safety feature - I - I ;::1 (control room system)

(L}ow-Power 1 Shutdown 2!1/;::1/2!1 (N)ew or (M)odified from bank including 1(A)  ;:::2/;:::2/2!1 (P)revious 2 exams s 31 ::s; 3 1 s 2 (randomly selected)

(R)CA  ;::1/;::1/2!1 (S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Date of Examination: 8/23/10 Exam Level: RO D SRO-I [RJ SRO-U D Operating Test No.: NRC2010 I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) i System 1 JPM Title Type Code* Safety Function

a. AE009 Start a Secondary Condensate Pump (256000 A4.01) S, D, L 2 I
  • b. CH002 Respond To A Low Turbine Hydraulic Pressure (241000 A2.06) S,D,E,A 3
  • c. BJ006 Place HPCI In Full Flow Recirc (206000 A4.06) S, D, L 4
d. KL003 Operate The PCIG System During Post LOCAllsolation S,A,E,EN,N 5 Conditions (223001 A4.11)
e. EG008 Respond To A Safety Auxiliaries Cooling Water Malfunction S,D,E,A 6 (295018 AA 1.02)
f. SB004 Respond To A Control Rod System Malfunction (295015 S,D,E,A 7 AA1.02)

'g. NA -

h. GK002 Isolate Control Room HVAC {290003 A4.01} S,A,E,N 9 I

In-Plant Systems@ (3 for RO); (3 for SRO-I); {3 or 2 for SRO..U}

i. SA001 Defeat ARllnterlocks (295037 EA1.03) D,E 1
j. BE002 Perform Torus Makeup Via Core Spray System (NRC2009) D,E, R,P,L 2 (295030 EA 1.06)
k. KJ003 Manually Emergency Start A Diesel Generator From The Local D, E, L 6 Panel (295003 EA 1.02)

.@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-II SRO-U (A)ltemate path 4-6 I 4-6/ 2-3 (C)ontrol room (D)irect from bank  ::;9/::;8/::;4 (E)mergency or abnonmal in-plant ~1/~1/~1 (EN)gineered safety feature - / - I ~1 (control room system)

(L)ow-Power I Shutdown ~1/1:!1/~1 (N)ew or (M)odified from bank including 1(A) ~2/1:!2/~1

    • (P)revious 2 exams S 3 I::; 3/ S 2 (randomly selected)
1/1
!1/1:!1 II (R)CA

" (S)imulator I i

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Date of Examination: 8/23/10 Exam Level: RO 0 SRO-I 0 SRO-U [8] Operating Test No.: NRC2010 I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I .IPM Title Type Code* Safety I

I Function

a. NA -

lb. NA -

  • c. BJ006 Place HPCI In Full Flow Recirc (206000 A4.06) S,D,E,L 4
d. KL003 Operate The PCIG System During Post LOCAllsolation i S, A, E, EN, N 5 Conditions (223001 A4.11)

EG008 Respond To A Safety Auxiliaries Cooling Water Malfunction S,D,E,A 6 Ie.

(295018 AA1.02) i NA I:

I h.

NA NA i

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

i. SA001 Defeat ARI Interlocks (295037 EA 1.03) D,E 1
j. BE002 Perform Torus Makeup Via Core Spray System (NRC2009) D,E, R,P,L 2 (295030 EA 1.06)
k. NA

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; ali 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

I I

  • Type Codes Criteria for RO I SRO-II SRO-U (A)ltemate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank s9/s8/S4 (E)mergency or abnormal in-plant  ;:;:1/;:;:1/;:;:1 (EN)gineered safety feature - / - / ;:;:1 (control room system)

(L)ow-Power / Shutdown  ;:;:1/;:;:1/;:;:1 (N)ew or (M)odified from bank including 1(A)  ;:;:2/;:;:2/;:;:1 (P)revious 2 exams s 3 / s 3 / s 2 (randomly selected)

(R)CA  ;:;:1/;:;:1/;:;:1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: J.- Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: Rx Power is at 90%.

Turnover:

Swap SJAE's for planned maintenance and raise reactor power to 95% using Group 9B Move Sheet. Hold at 95% for RE data collection.

11 Event Malf. Event Type* Event No. No. Description 1 NA R (RO) I Raise Reactor Power From 90% To 95% With Control N (SRO) Rods 2 NA N (PO) I Swap Steam Jet Air Ejectors I I i 3 I NM11D I (RO) I APRM 0 Fails Upscale (TS SRO)

I (SRO) 4 MS09D I (SRO) Steam line header pressure transmitter N076D fails (TS SRO) 5 5A92 F C (PO) Steam Jet Air Ejector Malfunction (HV-20168 Fails I C (SRO) Closed) i 6 MC01 C (ALL) Loss Of Main Condenser Vacuum (Variable Air Leak)

Manual Scram 7 EG12 M (ALL) i Loss Of Offsite Power On Main Generator Trip

~G07B I EDG 8 Failure

! 8 . DG07A C(RO) I EDG A Fails To Auto Start C (SRO) i 9 RC01 C (PO) I RGIC Overs peed C (SRO) i i

i I

I * (N}ormal, (R)eactivity, (I }nstrument, {C}omponent, {M}ajor APPENDIX D, Page 38 of 39

Appendix 0 Scenario Outline Form ES-O-1 Facility: Hope Creek Scenario No.: .£. Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 100% reactor power.

RCIC is tagged for planned maintenance.

Turnover: Perform Turbine Bypass Valves - Monthly.

lL1vent Malf. E~ Event No. No. Description 1 NA N (PO) Perform Turbine Bypass Valves Monthly N (SRO) 2 RZ02E I (SRO) RRCS Pressure Transmitter PT-N403E Failure - Low (TS SRO) 3 FW12C R(RO) 6C Feedwater Heater Tube Leak C (PO) Reduce Reactor Power To 80%

C (SRO) 4 FW29C I (SRO) Feedwater Level Sensor N004C Failure (TS SRO) 5 RR5B C (RO) Recire Pump B Dual Seal Failure RR6B C (SRO) 6 3A43 B C(RO) Recirc Pump B Discharge Valve Fails To Close C (SRO) 7 CD03 C (ALL) Manual Scram With 2 Rods Out 8 NA M (ALL) Hig!1 Drywell Pressure 9 TC01 C (ALL) Turbine Bypass Valve Fails Full Open Uncontrolled Cool down

  • (N)ormal, (R)eactivity, (I}nstrument, (C)omponent, (M)ajor APPENDIX 0, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: .l... Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 84.5% reactor power.

Turnover: Raise reactor power to 89.5% using reactor recirc.

Place "An Containment H2/02 Analyzer in service for surveillance.

Malf. Event Type* Event No. Description 1 NA N (PO) Place Containment H2/02 Analyzer In Service.

2 NA R(RO) Raise Reactor Power Using Recire.

N (SRO) 3 AD02LO C (PO) Stuck Open SRV ilL" (TS SRO)

C (SRO) 4 CW10A C (SRO) "A" SACS Pump Trip With 0 Fail To Auto Start (TS SRO)

CW15D 5 CW09 C (PO) Spurious TACS Isolation C (SRO) 6 5AS3D C (ALL) TACS Valve Does Not Re-Open Manual Scram 7 HP07 M (ALL) HPCI Steam Line Leak (Variable) To oryweII With Loss FW30A Of Feedwater And Downcomer Break/Emergency Depressurization FW30B FW30C PC04 8 RH04B C (PO) "B" RHR Pump Trip 9 RC05 I (PO) RCIC Flow Transmitter Failure

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, r APPENDIX D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: -+/-. Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 90% Power Turnover: Reduce power to 84.5% and remove A RFPT from service for planned maintenance.

II Event Malf. Event Type* Event No. No. Description 1 NA R(RO) Reduce Reactor Power Using Recirc To 84.5%.

N (SRO) 2 NA N (PO) Remove RFPT "A" From Service.

3 NM12C I (RO)

  • Recirc Flow Unit Failure Downscale. (TS SRO)

I (SRO) 4 FW01B C (ALL) Primary Condensate Pump Trip with Partial Runback RR30B Failure. (TS SRO) 5 TU1508 C (ALL) Main Turbine Vibrations 6 RP07 M (ALL) Manual Main Turbine Trip ATWS Half Core 7 FW11 C (PO) SULCV Fails Closed C (SRO) 8 SL01A C (RO) !lA' SLC Pump Failure I

i I

9 MS15 C (RO) MSIV Spurious Closure I I II * {N}ormal, {R)eactivit~, {I}nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

ADDenallXO Scenario Outline Form ES-O-1 Facility: Hope Creek Scenario No.: 2. Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 95% reactor power. B EHC Pump tagged for planned maintenance.

Turnover: Lower reactor power to 90% using Reactor Recirc Pumps for control rod pattern adjustment.

Swap SSW pump alignment to remove D SSW Pump from service for planned maintenance.

De;~~~:ion Event Malf. Event Type*

il No. No.

1 NA R (RO) Reduce Reactor Power With Reactor Recirc N(SRO) 2 NA N (PO) Swap Service Water Pumps 3 CW11B C (PO) Service Water Pump Malfunction (TS SRO)

CW05D C (SRO) 4 RR08B C (RO) Single Reactor Recirc Pump Runaway C (SRO) 5 RR26B2 C (RO) Reactor Recirc Pump Trip (TS SRO)

C (SRO) 6 CR01 C (ALL) Fuel Failure With Manual Scram I

7 PC06 M (ALL) Torus Leak/Emergency Depressurization

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39
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