ML022770523
| ML022770523 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/12/2002 |
| From: | Hunt W Susquehanna |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Cont R | |
| References | |
| 50-387/02301, 50-388/02301, ES-401-1 50-387/02301, 50-388/02301 | |
| Download: ML022770523 (32) | |
Text
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, SI) l Facility: SSES Date of Exam: 08112102 Exam Level: SRO K/A Category Points Tier Group Point K K K K lK K A A A A G Totall l1 2 3 4 l5 6 1 2 3 4 *l 1.~~~ _ _ _ ___ ___ ___
- 1. 1 4 4 5 11l _ 4 l5 _ _ 4 l 26 l Emergency & 2 3 3 2 3 4 2 17 Abnormal __ _ _ _ _ _ _ _
PantTir 7 7 796 4 Evolutions Totals 1 2 1 3 2 2 2 2 2 2 1 4 23 2.
Plant 2 1 1 1 1 1 2 1 1 1 1 2 13 Systems 3 0 0 l 1 0 l 1 0 l 0 1 1 0 0 l 1 4 Tier 3 2 5 3 4 4 3 4 3 2 7 40 l ____________ _ l T otals l ll ll ll l
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 l1 17 l___4 _ 4 _ _4 _ 5 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the categoryltier.
6.* The generic K/As 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.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
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ES-401 BWR SRO Examination OutlineForm ES-401-1 (R8, SI) 9m - ,4
.o A 1 DIP.,+ . Ti.#.
17;- 4 11 -, .- 1 EIAPE # Name ! Safety Function K K K A A G K/A Topic(s) Imp. Point 1 2 3 1 2 __s 295003 Partial or Complete Loss of AC Pwr 16 X X AK2.01 Station batteries 3.3 2 2.1.33 Ability to recognize indications for system operating 4.0 parameters which are entry-level conditions for technical specifications (SRO14]
295006 SCRAM /I X X AK1.03 Reactivity control 4.0 2
_ AA1.04 Recirculation system 3.2 295007 High Reactor Pressure /3 X X AK2.02 Reactor power 3.8 2 AK3.06 Reactorlturbine pressure regulating system operation 3.8 295009 Low Reactor Water Level /2 X AA2.03 Reactor water cleanup blowdown rate [SRO15] 2.9 1 295010 High Drywell Pressure / 5 X X AK2.01 Suppression pool level 3.3 2 AA1.02 Drywell floor and equipment drain sumps 3.6 295013 High Suppression Pool Temp. /5 X X AA2.02 Localized heating/stratification [SR009] 3.5 2 2.4.31 Knowledge of annunciators alarms and indications, and use 3.4 of the response instructions 295014 Inadvertent Reactivity Addition I 1 X AK3.02 Control rod blocks 3.7 1 295015 Incomplete SCRAM / I =_=_= =_=
295016 Control Room Abandonment / 7 X X AA2.04 Suppression pool temperature 4.1 2 2.1.14 Knowledge of system status criteria which require the 3.3
___ ___notification of plant personnel [SR005]
295017 High Off-site Release Rate 19 X X AK1.02 Protection of the general public 4.3 2 2.4.30 Knowledge of which events related to system 3.6 I_ operations/status should be reported to outside agencies [SRO19]
295023 Refueling Accidents Cooling Mode /8 _ _
295024 High Drywell Pressure /5 X X EK1.01 Drywell integrity: Plant-Specific 4.2 2 l EK3.09 Auxiliary building isolation: Plant-Specific 3.6 295025 High Reactor Pressure /3 295026 Suppression Pool High Water Temp. / 5 X X EK3.03 Suppression pool spray: Plant-Specific 3.8 2
___ EA2.02 Suppression pool level 3.9 295030 Low Suppression Pool Water Level / 5 X EA1.02 RCIC: Plant-Specific 3.5 1 295031 Reactor Low Water Level / 2 X X EK1.01 Adequate core cooling 4.7 2 l EA2.02 Reactor power [SRO08] 4.2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown /1I 295038 High Off-site Release Rate / 9 X EK3.02 System isolations 4.2 1 500000 High Containment Hydrogen Conc. /5 X X EK2.06 Wetwell spray system 3.4 2 l EA1.01 Primary containment hydrogen instrumentation 3.3 K/A Category Totals: l4 l4 I 4 5 144 Group Point Total: 26
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ES-401 BWR SRO Examination OutlineForm ES-401-1 (R8, SI)
Emeraencv and Abnormal Plant Evnlijtinns - Tier 1Grntnn 2 E/APE #/ Name / Safety Function K K K A A G K/A Topic(s) Imp. Points
_ _ __ _ _ _ _ _ _ 1 2 3 1 2 _
295001 Partial or Complete Loss of Forced Core X AK3.02 Reactor power response 3.8 1 Flow Circulation /1 & 4 295002 Loss of Main Condenser Vacuum 1 3 295004 Partial or Total Loss of DC Pwr /6 X AK1.05 Loss of breaker protection 3.4 1 295005 Main Turbine Generator Trip /3 X AA1.01 Recirculation system: Plant-Specific 3.3 1 295008 High Reactor Water Level /2 295012 High Drywell Temperature /5 X AA2.01 Drywell temperature [SRO21] 3.9 1 295018 Partial or Total Loss of CCW / 8 X X AK2.01 System loads 3.4 2 AK3.06 Increasing cooling water flow to heat exchangers 3.3 295019 Partial or Total Loss of Inst. Air /8 X X AA1.02 Instrument air system valves: Plant-Specific 3.1 2 2.4.6 Knowledge of symptom based EOP mitigation strategies 4.0
[SR022_
295020 Inadvertent Cont. Isolation /5 & 7 X X AK1.04 Bottom head thermal stratification 2.8 2
__ AK2.06 HPCI: Plant-Specific 3.8 295021 Loss of Shutdown Cooling /4 _4. -
295022 Loss of CRD Pumps I1 295028 High Drywell Temperature /5 X EK2.02 Components internal to the drywell 3.3 1 295029 High Suppression Pool Water Level /5 X 2.2.25 Knowledge of bases in technical specifications for limiting 3.7 1
__ conditions for operations and safety limits [SRO12]
295032 High Secondary Containment Area Temperature /5 295033 High Secondary Containment Area X EA2.02 Equipment operability [SRO02] 3.2 1 Radiation Levels /99 295034 Secondary Containment Ventilation High X EA2.02 Cause of high radiation levels [SRO17] 4.2 1 Radiation /99 295035 Secondary Containment High X X EK1.01 Secondary containment integrity 4.2 2 Differential Pressure / 5
___ _ __ ___ __ _ _ _ _ _EAI.02 SBGT/FRVS 3.8 295036 Secondary Containment High X EA2.01 Operability of components in the area [SRO16] 3.2 1 Sump/Area Water Level /5 600000 Plant Fire On Site / 8 K/A Category Point Totals: 3 l 3 l2 1 3 14 12 l Group Point Total: l17
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ES-401BWR SRO Examination OutlineForm ES-401-1 (R8, SI)
Plant Systems - Tier 2lGrouD 1 System # Name K K K K K K A A A A G K/A Topic(s) Imp. Points
_ _ __ _ _ _ _ _ _ 1 2 3 4 5 6 1 2 3 4 _ _ _ _ _ _ _ _ _ _ _
202002 Recirculation Flow Control _ X A3.03 Scoop tube operation 3.0 1 203000 RHR/LPCI: Injection Mode X X K6.06 Suppression pool 3.9 2 A1.09 Component cooling water system 2.9 206000 HPCI X A3.01 Turbine speed 3.5 1 209001 LPCS 211000 SLC __ = __ _
212000 RPS __=_=_=_=_=_=_=_=_=__
215004 Source Range Monitor ___
215005 APRM I LPRM 216000 Nuclear Boiler Instrumentation X K5.10 Indicated level versus actual during 3.3 1 vessel heatups and cooldowns 217000 RCIC X 2.1.32 Ability to ex(plain and apply system 3.8 1 217000 R ___________ X limits and precautions 218000 ADS X X K3.02 Ability to rapidly depressurize the 4.6 2 reactor 4.0 2.1.33 Ability to recognize indications for system operating parameters which are entry-level cond ions for technical specifications [SRO13]
223001 Primary CTMT and Auxiliaries X X K2.09 Drywell cooling fans 2.9 2 K4.03 Containmentldrywell isolation 3.8 223002 PCIS/Nuclear Steam Supply Shutoff X X K3.14 Recirculation system: Plant- 3.0 2 Specific 3.6 K4.03 Manual initiation capability: Plant-
________________________________Specific 226001 RHR/LPCI: CTMT Spray Mode X = A4.09 Pump discharge pressure 2.7 1 239002 SRVs X A2.02 Leaky SRV 3.2 1 241000 Reactor/Turbine Pressure Regulator X X K5.03 Reactor power vs. reactor pressure 3.6 2 2.2.25 Knowledge of bases in technical 3.7 specifications for limiting conditions for
___ _ _operations and safety limits [SRO25]
259002 Reactor Water Level Control X A1.02 Reactor feedwater flow 3.5 1 261000 SGTS X A2.13 High secondary containment 3.7 1 exhaust radiation ____
262001 AC Electrical Distribution X X K1.01 Emergency generators 4.3 2 K3.02 Emergency generators 4.2 264000 EDGs X 2.1.14 Knowledge of system status 3.3 1 criteria which requires the notification of
__ __ _ _ __ _ _I__ _ _ _ I__ plant personnel__SRO24] I_ __ _
290001 Secondary CTMT x x K1.07 Turbine building ventilation (steam 3.1 2 tunnel): Plant-Specific
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_ _ l l l lK6.01Reactor building ventilation: Plant- 3.6 l KIA Category Point Totals: 2 1 l 3 l 2 l 2 l 2 l 2 l 2 l 2 1 l 4 l Group PointTotal: l 23
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ES-401BWR SRO Examination OutlineForm ES-401-1 (R8, SI)
Plant Systems - Tier 2/Group 2 System # Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 _ _ _ _ _ _ _ _ _ _ _ _ _
201001 CRD Hydraulic 201002 RMCS 201004 RSCS X K6.02 Rod direction information 3.2 1 201006 RWM _ ___
202001 Recirculation ____X A3.07 Pump trips: Plant-Specific 3.3 1 204000 RWCU 205000 Shutdown Cooling _____
214000 RPIS _
215002 RBM X K3.01 Reactor manual control system 3.5 1 215003 IRM _
219000 RHR/LPCI: Torus/Pool Cooling Mode _
230000 RHR/LPCI: Torus/Pool Spray Mode X K4.07 Prevention of water hammer 3.2 1 234000 Fuel Handling Equipment X A1.03 Core reactivity level 3.9 1 245000 Main Turbine Gen. and Auxiliaries X K6.01 Gland seal 2.9 1 259001 Reactor Feedwater 262002 UPS (AC/DC) X A4.01 Transfer from alternate source to 3.1 1 preferred source 263000 DC Electrical Distribution X A2.01 Grounds 3.2 1 271000 Offgas X X K1.01 condenser air removal 3.1 2 2.4.6 Knowledge symptom based EOP 4.0 mitigation strategies [SRO23]
272000 Radiation Monitoring X 2.4.30 Knowledge of which events related 3.6 1 to system operations/status should be reported to outside agencies [SRO18]
286000 Fire Protection _____
290003 Control Room HVAC X K5.01 Airborne contamination (eg. 3.5 1 Radiological, toxic gas, smoke) control 300000 Instrument Air I I 400000 Component Cooling Water IXX _ K2.02 CCW valves 2.9 1 KIA Category Point Totals: i Ii Ii [l I i 1 2 K I lI 1 1. 2 Group Point Total: I 13
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ES-401BWR SRO Examination OutlineForm ES-401-1 (R8, SI)
Plant Systems - Tier 2/Group 3 System # Name K K K K K K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points
_ __ _ _ _ _ _ _ _ 1 2 3 4 5 _
201003 Control Rod and Drive Mechanism = = = = =__==_=_
215001 Traversing In-core Probe X 2.4.49 Ability to perform without 4.0 1 reference to procedure those actions that require immediate operation of
__sy svstem components and controls 233000 Fuel Pool Cooling and Cleanup X K3.05 Fuelpool water fission product 2.8 1
__________________________________concentration 239001 Main and Reheat Steam 256000 Reactor Condensate X X K5.03 Heat exchanger level operation 2.7 2 A2.09 Low feedwater heater level 2.8 268000 Radwaste 288000 Plant Ventilation 290002 Reactor Vessel Internals _ _ _
K/A Category Point Totals: Group Point Total: 4 Plant-Specific Priorities System / Topic Recommended Replacement for... Reason Points 217000 Reactor Core Isolation Cooling System-A2.04 AC power loss SBO high on PRA for SSES I Plant-Specific Priority Total (limit 10):
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 (R8, SI)
Facility: SSES Date of Exam: 08/12/02 Exam Level: SRO Category K/A # Topic Imp. Points 2.1.11 Knowledge of less than one hour technical 3.8 1 specification action statements for systems
[SRO04]
2.1.13 Knowledge of facility requirements for 2.9 1 controlling vital/controlled access [SRO11]
Conduct of 2.1.28 Knowledge of the purpose and function of 3.3 1 Operations major system components and controls 2.1.23 Ability to perform specific system and 4.0 1 integrated plant procedures during different modes of plant operation l Total 4 2.2.3 (multi-unit) Knowledge of the 3.3 1 design/procedural/and operational; differences between units [SRO03]
2.2.19 Knowledge of maintenance work order 3.1 1 requirements [SRO07]
2.2.24 Ability to analyze the affect of maintenance 3.8 1 Equipment on LCO status Control 2.2.30 Knowledge of RO duties in the control room 3.3 1 during fuel handling such as alarms from fuel handling area/communication with fuel storage facility/systems operated from the control room in support of fueling operations/and supporting instrumentation Total 4 2.3.3 Knowledge of SRO responsibilities for 2.9 1 auxiliary systems that are outside the control room (eg. Waste disposal and handlina systems) [SRO201 2.3.1 Knowledge of 10CFR: 20 and related facility 3.0 1 Radiation radiation control requirements [SRO06]
Control 2.3.11 Ability to control radiation releases 3.2 1 2.3.9 Knowledge of the process for performing a 3.4 1 containment purge Total 4
2.4.1 Knowledge of EOP entry conditions and 4.6 I immediate action steps [SRO01]
2.4.16 Knowledge of EOP implementation 4.0 1 hierarchy and coordination with other support procedures Emergency 2.4.21 Knowledge of the parameters and logic 4.3 1 Procedures/ used to assess the status of safety Plan functions including:
2.4.47 Ability to diagnose and recognize trends in 3.7 1 an accurate and timely manner utilizing the appropriate control room reference material 2.4.27 Knowledge of fire in the plant procedures 3.5 1
_____________ .1 Total I 5
Tier 3 Point Total (RO/SRO) 13/17
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, SI)
Facility: SSES Date of Exam: 08/12102 Exam Level: RO K/A Category Points Tier Group Point K K K K K K A A A A G Total l1 2 3 4 5 6 I A
- 1. 1 3 3 34 00 1 Emergency & 2 3 4 4 3 3 2 19 Abnormal 3 1 0 Evolutions Tier 7 4 3 36 Totals 1 2 2 3 2 3 2 3 3 2 3 3 28
- 2. 2 3 23 2 0 2 l 1 2 0 19 Plant Systems 3 0 0 1 l 1 0 0 1 0 1 0 0 4 Tier 5 4 6 5 5 5 4 5 4 5 3 51
____ ____ Totals _ _ _ _
l______at__1_
- 3. Generic Knowledge and Abilities
__Cat c 1 2IlCat 3IlCat 4I1I 2 l 13
_ _____3 _ _ _ _ _ _
Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
6.* The generic 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.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. KlAs below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Emergency and Abnormal Plant Evolutions - Tier 1/GrouDp 1 =
EIAPE # Name / Safety Function K K K A A G K/A Topic(s) Im Points 1 2 3 1 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
295005 Main Turbine Generator Trip /3 X AA1.01 Recirculation system: Plant-Specific [BOTH 6] 3.1 1 295006 SCRAM /I1 X X AK1.03 Reactivity control [BOTH 8] 3.7 2 AA1.04 Recirculation system [BOTH 7] 3.1 295007 High Reactor Pressure / 3 X X AK2.02 Reactor power [BOTH 10] 3.8 2 AK3.06 Reactor/turbine pressure regulating system operation [BOTH 91 3.7 295009 Low Reactor Water Level /2 _2__ .
295010 High Drywell Pressure/ 5 X X AK2.01 Suppression pool level [BOTH 12] 3.2 2 AAI.02 Drywell floor and equipment drain sumps [BOTH 11] 3.6 295014 Inadvertent Reactivity Addition / 1 X _ AK3.02 Control rod blocks [BOTH 38] 3.7 1 295015 Incomplete SCRAM / _ __.
295024 High Drywell Pressure /5 X X EKI.01 Drywell integrity: Plant-Specific [BOTH 37] 4.1 2 EK3.09 Auxilary Building isolation: Plant-Specific [BOTH 46] 3.1 295025 High Reactor Pressure /3 295031 Reactor Low Water Level /2 X = = = = EKI.01 Adequate core cooling [BOTH 01] 4.6 1 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown /1 500000 High Containment Hydrogen Conc. /5 - X X EK2.06 Wetwell spray system [BOTH 72] 3.0 2 EA1.01 Primary containment hydrogen instrumentation [BOTH 53] 3.4 KIA Category Totals: 3L 31 3 1 4 0 0 Group Point Total: 13
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
C- - - - -- -A Ah.-.1..l DIP-ntF 4. - Ti- 4I rf-. -n 2 E/APE #/ Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295001 Partial or Complete Loss of Forced Core X AK3.02 Reactor power response [BOTH 33] 3.7 1 Flow Circulation /1 & 4 295002 Loss of Main Condenser Vacuum / 3 295003 Partial or Complete Loss of AC Pwr / 6 = X AK2.01 Station batteries [BOTH 48] 3.2 1 295004 Partial or Complete Loss of DC Pwr /6 X AK1.05 Loss of breaker protection [BOTH 14] 3.3 1 295008 High Reactor Water Level /2 295012 High Drywell Temperature /5 295013 High Suppression Pool Temp. /5 X 2.4.31 Knowledge of annunciators alarms and indications, and use 3.3 1 of the response instructions [BOTH 32]
295016 Control Room Abandonment/ 7 X X AA2.04 Suppression pool temperature [BOTH 54] 3.9 2 2.4.6 Knowledge symptom based EOP mitigation strategies [RO14] 3.1 295017 High Off-site Release Rate /9 X X AK1.02 Protection of the general public [BOTH 16] 3.8 2 AA1.10 RPS [RO03] 3.6 295018 Partial or Complete Loss of CCW / 8 X X AK2.01 System loads [BOTH 17] 3.3 2 AK3.06 Increasing cooling water flow to heat exchangers [BOTH 73] 3.3 295019 Part. or Comp. Loss of Inst. Air / 8 X AA1.02 Instrument air system valves: Plant-Specific [BOTH 47] 3.3 1 295020 Inadvertent Cont. Isolation /5 & 7 X X AK1.04 Bottom head thermal stratification [BOTH 71] 2.5 2 AK2.06 HPCI: Plant-Specific [BOTH 70] 3.8 295022 Loss of CRD Pumps /I1 295026 High Suppression Pool Water Temp. /5 X X EK3.03 Suppression pool spray: Plant-Specific [BOTH 49] 3.5 2 EA2.02 Suppression pool level [BOTH 13] 3.8 295028 High Drywell Temperature /5 X X EK2.02 Components internal to the drywell [BOTH 51] 3.2 2 EA2.05 Torus/suppression chamber pressure: Plant-Specific [RO22] 3.6 295029 High Suppression Pool Water Level / 5 295030 Low Suppression Pool Water Level / 5 X EA1.02 RCIC: Plant-Specific [BOTH 50] 3.4 1 295033 High Sec. Cont. Area Rad. Levels /9 295034 Sec. Cont. Ventilation High Rad. /99 X X _
295038 High Off-site Release Rate / 9 X =_=-_EK3.02 System isolations [BOTH 36] 3.9 1 600000 Plant Fire On Site /8 K/A Category Point Totals: l 3 l I4 lI4 l]3 l 3 l 2 Group Point Total: l 19
I
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Emergency and Abnormal Plant Evolutions - Tier I/Group 3 E/APE # Name ! Safety Function K K K A A G K/A Topic(s) Imp. Points
_ __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ 1 2 3 1 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _
295021 Loss of Shutdown Cooling /4 X 21.32 Abilty to explain and apply system limits and precautlons 3.1 1 295023 Refueling Accidents /8 X AA2.01 Area radiation levels [RO15] 3.6 1 295032 High Secondary Containment Area Temperature /5 295035 Secondary Containment High X X EK1.01 Secondary containment integrity [BOTH 55] 3.9 2 Differential Pressure / 5 EA1.02 SBGT/FRVS [BOTH 56] 3.6 295036 Secondary Containment High Sump/Area Water Level / 5 11I II I I I I I I 4
4 I . .
1- - - t-1 - -4 -
4 4..
4_4 K/A Category Point Totals: I 1 1l 0 ° 1 [1 1 11 l Group Point Total: l 4
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Plant Systems - Tier 2/Group 1 System # I Name K K K K K K A A A A G K/A Topic(s) Imp. Points
_ _ __ _ _ _ _ _ _ 1 2 3 4 5 6 1 2 3 4 _ _ _ _ _ _ _ _ _ _ _ _ _ _
201001 CRD Hydraulic 201002 RMCS X A4.05 Rod select matrix [RO05] 3.1 1 202002 Recirculation Flow Control _ X A3.03 Scoop tube operation [BOTH 18] 3.1 1 203000 RHR/LPCI: Injection Mode X X K6.06 Suppression pool [BOTH 58] 3.8 2 Al.09HCComponent cooling water system 2.9
_ __ _ __ _ __ __ __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _[B OT H 6 5] _ _ _ _ _ _
206000 HPCI X X K2.01.System valves [RO25] 3.2 2
_ A3.01 Turbine speed [BOTH 64] 3.6 209001 LPCS X X K1.14 Reactor vessel [RO16] 3.7 2 A4.05 Manual initiation controls [RO17] 3.8 211000 SLC X 2.1.33 Ability to recognize indications and 3.4 1 system operating, parameters which are entry-level cond ions for technical specifications [ROo2]
212000 RPS X 2.4.4 Ability to recognize abnormal for 4.0 1 system operating parameters which are entry-level condl ions for emergency and abnormal operating procedures [RcO18_] _ _
215003 IRM X A4.04 IRM back panel switches, meters 3.1 1 and indicating lights [RO06]
215004 SRM 215005 APRM / LPRM X A2.03 Inoperative trip (all causes) [RO07] 3.6 1 216000 Nuclear Boiler Instrumentation X K5.10 Indicated level versus actual during 3.1 1 vessel heatups or cooldowns [BOTH 19] g 217000 RCIC X X 2.1.32 Ability to explain and apply system 3.4 2 limits and precautions [BOTH 0] 3.5 K3.03 Decay heat removal [RO20]
218000 ADS X X K3.02 Ability to raf idly depressurize the 4.5 2 reactor [BOTH 35 4.1 A1.04 Reactor pressure [R013] 4.1 223001 Primary CTMT and Auxiliaries X X K2.09 Drywell cooling fans: Plant-Specific 2.7 2
[BOTH 21 3.7 K4.03 Containmentldrywell isolation
_ _ _ _ _ _ _ _ _ _ _[B O T H 22]
223002 PCIS/Nuclear Steam Supply Shutoff X X K3.14 Recirculation system: Plant- 3.0 2 Specific [BOTH 57] 3.5 K4.03 Manual ini~tiation capability: Plant-
_________________________________Specific [BOTH 2] __ ____
239002 SRVs X X K1.06 Dr welI instrument air/drywell 3.4 2 pneumaics: Plant-Specific [RU19] 3.1
_ A2.02 Leaky SRV [BOTH 2]
241000 Reactor/Turbine Pressure Regulator X Ix K5.03 Reactor power vs. reactor pressure 3.5 2
[BOTH 61]
2.6
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I I K6.02 DC electrical power [RO21]
259001 Reactor Feedwater 259002 Reactor Water Level Control X X K5.03 Water level measurement [RO10] 3.1 2 A1.02 Reactor feedwater flow [BOTH 34] 3.6 261000 SGTS X A2.13 High secondary exhaust radiation 3.4 1
-I II I I[BOTH 6]
264000 EDGs _I I rul K/A Category Point Totals: _2 3 12 -2 - T3 T _
_2 _ Point
_3 _ Total:
_3 __3 _2 __3 __Group 28
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Plant Systems - Tier 2/Group 2 System # Name K K K K K K A A A A G K/A Topic(s) Imp. Points
_ _ __ _ _ _ _ _ _ 1 2 3 4 5 6 1 2 3 4 _ _ _ _ _ _ _ _ _
201003 Control Rod and Drive Mechanism l l l l ll l l___
201004 RSCS X K6.02 Rod direction information [BOTH 3.1 1 201006 RWM ________=__= =
202001 Recirculation X A3.07 Pump trips: Plant-Specific [BOTH 41 3.3 1 204000 RWCU ___
205000 Shutdown Cooling 214000 RPIS 215002 RBM X K3.01 Reactor manual control system 3.3 1
[BOTH 59]1__ ___
219000 RHR/LPCI: Torus/Pool Cooling Mode 226001 RHR/LPCI: CTMT Spray Mode X A4.09 Pump discharge pressure [BOTH 3] 2.8 1 230000 RHR/LPCI: Torus/Pool Spray Mode X X K2.02 Pumps [RO09] 2.8 2 K4.07 Prevention of water hammer [BOTH 3.1 66] _ _ _ _ _ _ _
239001 Main and Reheat Steam =_=_=_=_=_=_=_=_=_=_=
245000 Main Turbine Gen. and Auxiliaries X K6.01 Gland seal [BOTH 74] 2.8 1 256000 Reactor Condensate X X K5.03 Heat exchanger level operation 2.6 2
[BOTH 41] 2.8 A2.09 Low feedwater heater level [BOTH
]60 262001 AC Electrical Distribution X X K1.01 Emergency generators [BOTH 62] 3.8 2
_ K3.02 Emergency generators [BOTH 5] 3.8 262002 UPS (AC/DC) X A4.01 Transfer from alternate source to 2.8 1
__ preferred source [BOTH 67]
263000 DC Electrical Distribution X A2.01 Grounds [BOTH 25] 2.8 1 271000 Offgas X K1.01 condenser air removal system 3.1 1
__ [BOTH 26]
272000 Radiation Monitoring _______
286000 Fire Protection 290001 Secondary CTMT X X K1.07 Turbine building ventilation (steam 3.0 2 tunnel): Plant-Specific [BOTH 75] 3.5 K6.01 Reactor building ventilation: Plant-
._ Specific [BOTH 69]
290003 Control Room HVAC X K5.01 Airborne contamination (e.g. 3.2 1 radiological, toxic gas, smoke) control 300000Instrumen i[BOTHr _
300000 Instrument Air____________________
400000 Component Cooling Water X XI K2.02 CCW valves [BOTH 45] 2.9 2
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K4.01 Automatic start of standby pump 3.4 l K C P T l 1 0 l 1 l 2 l ROuI] IP IKJA Categor Point Totals: 13 12 12 12 12 13 10 12 1 1 2 0 1Group Point Total: 1 19
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Plant Systems - Tier 2/Group 3 System # Name K K K K K K A A A A G K/A Topic(s) Imp. Points
_ __ _ _ _ _ _ _ _ 1 2 3 4 5 6 1 2 3 4 215001 Traversing In-core Probe X _ A3.03 Valve operation [RO12] 2.5 1 233000 Fuel Pool Cooling and Cleanup X K3.05 Fuel pool water fission product 2.6 1
____ _____ concentration_[BOTH_42] _ _ _ _
234000 Fuel Handling Equipment X _ A1.03 Core reactivity level [BOTH 43] 3.4 1 239003 MSIV Leakage Control _ _
268000 Radwaste _
288000 Plant Ventilation X K4.03 Automatic starting and tripping of 2.8 1 290002 Reactor Vessel Internals _ fn _ _ _ ___
K/A Category Point Totals: l l[ 0 l 1 1 l 0 l 0 i GroupPointTotal: lII 4 Plant-Specific Priorities System I Topic Recommended Replacement Reason Points for...
217000 Reactor Core Isolation Cooling System-A2.04 AC power loss SBO high on PRA for SSES 1 Plant-Specific Priority Total: (limit 10)
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 (R8, S1)
Facility: SSES Date of Exam: 08/12102 Exam Level: RO Category K/A # Topic Imp. Points 2.1.28 Knowledge of the purpose and function of 3.2 1 major system components and controls
[BOTH 23]
2.1.23 Ability to perform specific system and 3.9 1 Conduct of integrated plant procedures during different Operations modes of plant operation [BOTH 40]
2.1.1 Knowledge of the conduct of operations 3.7 1 requirements [RO24]
Total 3 2.2.24 Ability to analyze the affect of maintenance 2.6 1 on LCO status [BOTH 15]
2.2.30 Knowledge of RO duties in the control room 3.5 1 during fuel handling such as alarms from fuel handling area/communication with fuel Equipment storage facility/systems operated from the Control control room in support of fueling operations/and supporting instrumentation
[BOTH 39]
2.2.22 Knowledge of limiting conditions for 3.4 1 operations and safety limits [RO01]
__ _ __ _ _ _ Total 3 2.3.11 Ability to control radiation releases [BOTH 2.7 1 27] _ _ _
2.3.9 Knowledge of the process for performing a 2.5 1 Radiation containment purge [BOTH 28]
Control 2.3.2 Knowledge of facility ALARA program 2.5 1
[RO08] l Total 3 Emergency 2.4.16 Knowledge of EOP implementation 3.0 1 Procedures/ hierarchy and coordination with other Plan ______
support procedures [BOTH 29]
- - - t 1 2.4.21 Knowledge of the parameters and logic 3.7 1 used to assess the status of safety functions including: Reactivity control
[BOTH 52]
2.4.47 Ability to diagnose and recognize trends in 3.4 1 an accurate and timely manner utilizing the appropriate control room reference material
[BOTH 30]
2.4.27 Knowledge of fire in the plant procedures 2.9 1
[BOTH 31]
Total 4 Tier 3 Point Total (RO/SRO) 13/17
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ES-401 Record of Rejected K/As Form ES-401 -10 (R8, SI)
SUSQUEHANNA STEAM ELECTRIC STATION Tier / Randomly Selected Reason for Rejection Group K/A Line Out in Attached Various NUREG 1123, Rev. 2 Lineout of all K/As not applicable to SSES design per letter PLA005439 PLI A14-13 from Jeff Helsel (PPL) to for SSES Alan Blarney (NRC) dated Feb 4th, 2002. These items were rejected because the line item does not pertain to the design of the Susquehanna Steam Electric Station. Additional justification is provided for the following specific K/A line items per A. Blarney request.
- 1. 201001 A4.02 SSES design has no control room indication or control, valves are manual local.
- 2. 201001 A4.05 SSES does not have a Cooling Water Press Control valve.
- 3. 201002 A3.04/A4.04 SSES does not have a timer alarm or test switch in its design.
- 4. 202002 K4.04 Load following circuit is disabled.
- 5. 211000 K6.04 and 6.05 No connection or interrelation between CS or HPCI and SLC. RCIC covered by 295037 EAI.10.
- 6. 206000 K5.03 SSES design uses Bailey controller, covered by K5.05 Turbine Speed Controller.
- 7. 209001 A4.07 SSES design uses Condensate Transfer for keep fill not a separate pump.
- 8. 256000 A3.09 SSES design uses cascading drain system with no drain tank level controller, drain tank flooded.
- 9. 217000 K1.08 SSES design uses Condensate Transfer for keep fill not a separate pump.
- 10. 218000 K1.05 SSES remote S/D panels do not effect ADS logic only individual valve control switches for 3 valves.
- 11. 241000 A3.17 SSES design does not provide for turbine runback: direct turbine trip w/o runback Tierl and Generic K/As Tier 2 Non-system Generic K/As suppressed per NRC Suppression Guidance Letter, 'Clarification of Guidance Regarding the Elimination of Inappropriate Knowledge and Abilities (K/As) on Written Operator Licensing Examinations' All <2.5 Importance All K/A that are less than 2.5 and applicable to SSES design will not be selected for examination with exception Rating of K/A 217000 A2.04. SSES PRA has identified SBO as a core damage event and therefore this K/A may be considered as a plant specific priority per ES-401 Changes made after initial outline submittal during exam development Tier 1/GP3 295021 AK2.07 Random generated replacement 295021 2.1.32 due to difficulty writing >LODI question to original K/A RO_
Tier 2/GPI 215003 KI.05 Random generated replacement 206000 K2.01 due to original K/A not being applicable to SSES for display RO control Tier2/GP3 233000 K2.02 Random generated replacement 288000 K4.03due to oversampling of RHR K2 power supply K/A RO I Tier 3 RO 2.1.16 Random generated replacement 2.1.1 due to difficulty writing >LODI question to original K/A and overlap with simulator tasks
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Tier 2/GPI 217000 K2.04 Random generated replacement 217000 2.1.32 due to difficulty writing >LODI question to original K/A RO__ _ _ _ _ _ _ _
Tier 2IGP1 217000 K2.04 Random generated replacement 264000 2.1.14 due to difficulty writing >LODI question to original K/A SRO Tier 2/GP2 271000 KI.02 Random generated replacement 271000 K1.01 due to difficulty writing >LOD1 question to original K/A RO Tier 21GP2 271000 KI.02 Random generated replacement 271000 K1.01 due to difficulty writing >LODI question to original K/A SRO I _ _ _ _ _I_
Tier 11GP2 295021 2.1.32 Random generated replacement 295033 EA2.02 due to original K/A not appropriate for SRO only question SRO I Tier 2IGP1 261000 2.4.49 Random generated replacement 241000 2.2.25 due to original K/A not appropriate for SRO only question SRO 1 Admini Topics 2.4.39 Replaced with 2.4.27 due to significant overlap between original and question A.4.b.RO in same topic (i.e. Emergency Plan)
ES-301 I (RO) l 157M [23cSe/z o Il.L..,
R/ 2 21 '/31 J,_,A6 ds e E/ J) JPM.
ES-301 Administrative Topics Outline Form ES-301-1(R8, SI)
Facility: SSES Date of Examination: 08/12/02 Examination Level (circle one 3 Operating Test Number: A-SRO Administrative Topic/Subject Describe method of evaluation:
Description 1. ONE Administrative JPM, OR
- 2. TWO Administrative Questions A. 1 CONDUCT OF OPS Requirements to maintain a license 2.1.1 (3.8)
Question - A.l.a.SRO Discovery of mispositioned control rod 2.1.20 (4.2)
Question - A. 1.b. SRO Action when less than required staffing at shift turnover 2.1.4 (3.4)
Question - A. 1.c. SRO Working hour restrictions 2.1.1 (3.8)
Question - A. 1.d.SRO A.2 EQUIPMENT CONTROL JPM-Review failed surveillance and determine actions 2.2.24 (3.8)
SRO A2 JPM A.3 RADIATION CONTROL Authorizing exceeding station/NRC limits 2.3.4 (3.1)
Question - A.3.a.SRO Control of Locked High Radiation Areas 2.3.10 (3.3)
Question - A.3.b.SRO A.4 EMERGENCY PLAN JPM Fill out classification paperwork SRO A4 3PM NUREG-1021, Revision 8
ES-301 Administrative Topics Outline Form ES-301-1(R8. Sl)
Facility: SSES Date of Examination: 08/12/02 l Examination Level (circle one s Operating Test Number: A-RO Administrative Topic/Subject Describe method of evaluation:
Description 1. ONE Administrative JPM, OR
- 2. TWO Administrative Questions A. 1 CONDUCT OF OPS Requirements to maintain a license 2.1.1 (3.7)
Question - A. l .a.RO Discovery of mispositioned control rod 2.1.20 (4.3)
Question - A. l.b.RO Requirements for temporary relief 2.1.3 (3.0)
Question - A. 1.c.RO Requirements for temp mod of procedure 2.1.21 (3.1)
Question - A. l .d.RO A.2 EQUIPMENT CONTROL JPM-Review failed surveillance and determine actions 2.2.24 (2.6)
RO A2 1PM A.3 RADIATION CONTROL Stay time limits 2.3.1 (2.6)
Question - A.3.a.RO Requirements for High Radiation entry 2.3.10 (2.9)
Question - A.3.b.RO A.4 EMERGENCY PLAN Action in the event of a fire on-site 2.4.27 (3.0)
Question - A.4.a.RO Notification requirements for an ALERT declaration 2.4.43 (2.8)
Question - A.4.b.RO NUREG-1021, Revision 8
n ,n0 c \
Control Room Systems rn on - 4 ES-301 Porm Eb-,50-2 tKis, Si) and Facility Walk-Through Test Outline Facility: SSES Date of Examination: 08/12/02 Exam Level (circle one): RCQSROl) )SRO(U) Operating Test No.: B-SRO-I B.1 Control Room Systems System I JPM Title Type Safety Code* Function
- a. 239001 (4.0) Main Steam Line Isolation and Quick N,S 3 Recovery in Accordance with ON- 81-001
- b. 259002 (3.7) Respond to a Failure of "A" RFPT M,S,A 2 SPD/CTUDemand Signal in Accordance with ON-145-001
- d. 209001 (3.8) Perform Manual Startup Component of M,S,A 2 Core Spray System in Accordance with OP-151 -001
- f. 211000 (4.1) Initiate the SBLC System in Accordance D,S,A 1 with OP-153-001 with RWCU F004 Valve Failing to Isolate
- g. 206000 (4.1) Recovery from a Manual Closure of HPCI D,S,A 2 Isolation Valves with an Initiation Signal Present with a Steam Leak Developing B.2 Facility Walk-Through
- a. 295037 (3.713.9)/ Connect SLC System Storage Tank to D,R 4,1 RCIC System in accordance with ES-150-002
- b. 262001 (3.4) Place the Vital AC Un-interruptible Power D 6 Supply AC System in Service in Accordance with OP-157-001
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
ES-301 Control Room Systems Form ES-301-2 (R8, S1) and Facility Walk-Through Test Outline Facility: SSES Date of Examination: 08/12/02 Exam Level (circle one): RO / SRO( O( Operating Test No.: B-SRO-U B.1 Control Room Systems System / JPM Title Type Safety Code* Function
- a. 239001 (4.0) Main Steam Line Isolation and Quick N,S 3 Recovery in Accordance with ON-181-001 b.
c.
- d. 209001 (3.8) Perform Manual Startup Component of M,S,A 2 Core Spray System in Accordance with OP-151-001 e.
- f. 211000 (4.1) Initiate the SBLC System in Accordance D,S,A 1 with OP-1 53-001 with RWCU F004 Valve Failing to Isolate 9.
B.2 Facility Walk-Through
- a. 295037 (3.7/3.9)/ Connect SLC System Storage Tank to D,R 4,1 RCIC System in accordance with ES-1 50-002
- b. 262001 (3.4) Place the Vital AC Un-interruptible Power D 6 Supply AC System in Service in Accordance with OP-1 57-001 c.
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
ES-301 Control Room Systems Form ES-301-2 (R8, SI) and Facility Walk-Through Test Outline Facility: SSES __ Date of Examination: 08/12/02 Exam Level (circle one) ROijSRO(l) SRO(U) Operating Test No.: B-RO lB.1 Control Room Systems System / JPM Title Type Safety Code* Function
- a. 239001 (4.0) Main Steam Line Isolation and Quick N,S 3 Recovery in Accordance with ON-1 81-001
- b. 259002 (3.7) Respond to a Failure of "A" RFPT M,S,A 2 SPD/CTUDemand Signal in Accordance with ON-145-001
- d. 209001 (3.8) Perform Manual Startup Component of M,S,A 2 Core Spray System in Accordance with OP-151 -001
- f. 211000 (4.1) Initiate the SBLC System in Accordance D,S,A I with OP-1 53-001 with RWCU F004 Valve Failing to Isolate
- g. 206000 (4.1) Recovery from a Manual Closure of HPCI D,S,A 2 Isolation Valves with an Initiation Signal Present with a Steam Leak Developing B.2 Facility Walk-Through
- a. 295037 (3.7/3.9)1 Connect SLC System Storage Tank to D,R 4,1 RCIC System in accordance with ES-150-002)
- b. 262001 (3.4) Place the Vital AC Un-interruptible Power D 6 Supply AC System in Service in Accordance with OP-157-001
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, room, (S)imulator, (L)ow-Power, (R)CA IC)ontrol
Appendix D Scenario Outline Form ES-D-1 (R8, SI)
Facility: SSES Scenario No.: I- Op-Test No.: CI_
Examiners: Operators: US - #21 #41 #6 PCOM - #11 #31 #5 PCOP - #9/#1/#11 Initial Conditions: 100% Rated Power B Emergency Diesel Generator was started and synchronized to the bus for surviellence testing 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago, RCIC Out Of Service due to oil system contamination.-
Turnover: Shutdown the B Emergency Diesel Generator Continue normal operations Event Malf. No. Event Event No. Type* Description 1 N Unload and secure B EDG 2 BRO3 I EDG B output breaker trips on overcurrent 3 RP158008A C Trip of RPS A MG Set motor 4 RDI 55008 C Control rod scrams when RPS A de-energizes (fuse) 5 RDI 55006 C Control rod sticks at position 10 6 R 20% Power reduction due stuck rod 7 RR1 64010 Small Leak in Drywell 8 C HPCI auto Start Failure 9 MS183007 M A MSL leak inside drywell 10 MV07 C DW Spray Valve F021 Fail to Open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Facility: SSES Scenario No.: 2 Op-Test No.: Cl_
Examiners: Operators: US-#1/#31 #5 PCOM - #7/ #10/#11 PC-#2#4/ #6 Initial Conditions: 100% Rated Power High Pressure Coolant Injection is Inoperable due to a failed governor valve Turnover: Swap operating CRD pumps Event Malf. No. Event Event No. Type* Description I N Secure A CRD pump and Start B CRD pump 2 R Power Control requests power drop of 100 MWe I 3 FW145009A C Trip of RFPT A 4 NM178012D I Recirc flow Unit failure downscale 5 PM03 C Loss of CRD Flow I INOP Accumulator I
6 RP158003 M Failure to scram-RPS relays fail to de-energize 7 PM03 C SLC System Failure I 8 TC193001 C Main turbine trip 9 RCI 50002 i RCIC Speed Controller Failure 10 BRO5 C Loss of Aux bus IIA/B I I I I
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Facility: SSES Scenario No.: 3 Op-Test No.: Cl Examiners:_ Operators: : US - #71 #X/ #8 PCOM - #91 #41#6 POOP - #1/ #31 #5 Initial Conditions: 50% Rated Power Standby Liquid pump lB is Inoperable while Maintenance investigates a high motor vibration Turnover: Transfer SUB 10 to SUT 10 then continue power ascension Event Malf. No. Event Event No. Type* Description I N Transfer SUB IO to SUT 10 I
2 R Continue power ascension to raise power 3 TRO2 I B Feedwater Flow Transmitter Fails Low 4 TInadvertent HPCI Isolation Due to Failed Room TH2I 4 Temperature Instrument 5 IA118002 C Loss of Instrument Air 6 RRI640O1A M Recirc loop B suction Rupture DBA 0-40%
7 RLOI C AUTO ADS Logic Failure 8 MVO6:HVI5 C Loop B RHR Injection Valve Fails to Open 1FOI 5B 1
1 1
i 4 4 I I t
I + 4
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form Appendix 0 Scenario Outline Form ES-D-1 (R8, S1)
Facility: SSES Scenario No.: 4_ Op-Test No.: CI1 Examiners: Operators: : US-#8_
PCOP - #2 Initial Conditions: 90% Rated Power B EHC pump is OOS for breaker mainte RHR Loop A has just been secured from Suppression Pool Cooling and RHRSW pump I 1A is running for vibration data Turnover: Secure RHRSW pump 1A once data has been taken Event Malf. No. Event Event No. Type* Description I N Secure RHRSW Pump 1A 2 TRO2 I RHRSW Radiation Monitor Fails Upscale 3 PM03 C Loss of Isolate Bus Duct Cooling 4 R Power reduction to lower generator current to <19,000
______amps 5 EG198004 C Generator Lockout/Turbine Trip 6 RP158007 M RPS B Failure to Trip - ATWS
___ B 7 L153001 C SLC Squibb Valves Fail
_____A/B 8 PM03 C B EHC Pump Trip
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
of cs^\
Anpendix D Scenario Outline Form ES-D-1 (Kt$, bl Aooendix D Scenario Outline Form lb-U-1 IKs, 1)
Facility: SSES Scenario No.: 5 (SPARE) Op-Test No.: C1 Examiners: Operators:SRO-I /SRO-U SRO-I Initial Conditions: 100% Rated Power B CRD pump is OOS for breaker maintenance 1B Condensate pump has possible ground Turnover: Reduce power and shutdown 1B Condensate pump Event Malf. No. Event Event No. Type* Description I R Reduce reactor power for pump removal 2 N Secure 1B Condensate pump 3 l "A" Narrow Range level instrument fails upscale 4 RR1 79003 C Fuel clad failure ramped 5 RP158007 I Failure of a RPS to trip - Half scram failure A
6 MS183008 M MSL leak Inside Turbine Building I 7 C "D" MSL failure to isolate - stem binding i i I
4 1 1-
_____ L 4 4 +
I- 4 ________________________________________________________________________
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor