ML022700392
| ML022700392 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/20/2002 |
| From: | Hunt W Susquehanna |
| To: | Alan Blamey Division of Reactor Safety I |
| Conte R | |
| References | |
| 50-387/02301, 50-388/02301, ES-202-2, ES-301-1, ES-301-2, ES-301-5, ES-301-6, ES-401-1, ES-401-10, ES-401-5, ES-402-2, ES-D-1 50-387/02301, 50-388/02301 | |
| Download: ML022700392 (51) | |
Text
February 20, 2002 *
Mr. Alan Blamey fl_-
USNRC Chief Examiner J J USNRC Region 1 Ad TM 475 Allendale Road King of Prussia, PA 19406-1415 Susquehanna Learning Center Examination Outline PLA 005447 File A14-13D
Dear Alan:
Enclosed are the Written and Operating Examination Outlines for the Susquehanna Steam Electric Station operator examination currently scheduled for August 2002. This information is being provided in accordance with NUREG 1021 Operating Examination Standards for Power Reactors, Rev 8, Supplement 1.
Included are the following completed Examiner Standard forms:
- ES-201-2 Examination Outline Quality Checklist
- ES-401-5 Generic Knowledge and Abilities Outline (Tier 3)
- ES-D-1 Scenario Outline
- ES-301-6 Competencies Checklist
- ES-401 -10 Record of Rejected K/As Susquehanna Steam Electric Station requests that the enclosed materials be withheld from public disclosure until after the August 2002 examination process is complete.
If you have any questions, please feel free to contact me at 570-542-3619.
Sincerely, Walter W. Hunt SSES Training Manager Response: No
Enclosures:
Written and Operating Examination Outlines cc: J. M. Helsel Ops Letter File Nuc Records-Site jmexamoutlines JM/WWH/vah
May 23, 2002 p I .
Mr. Alan Blamey TM USNRC Chief Examiner USNRC Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Susquehanna Learning Center Examination Outline PLA 005485 PLI A14-13D
Dear Alan:
Enclosed are the revised portions of the Written and Operating Examination Outlines for the Susquehanna Steam Electric Station operator examination scheduled for August 2002. As per your request, only those forms that were modified from the original 'draft' submittal dated February 20, 2002 are included. Please remove the applicable forms, and replace with those provided in this transmittal. This information is being provided in accordance with NUREG 1021 Operating Examination Standards for Power Reactors, Rev 8, Supplement 1.
Included are the following completed Examiner Standard Forms:
- ES-201-2 Examination Outline Quality Checklist
- ES-301-6 Competencies Checklist
- ES-D-1 Scenario Outline Susquehanna Steam Electric Station requests that the enclosed materials be withheld from public disclosure until after the August 2002 examination process is complete.
If you have any questions, please feel free to contact me at 570-542-3619.
Sincerely, Walter W. Hunt Manager - Nuclear Training Response: No Enclosures cc: J. M. Helsel Ops Letter File Nuc Records-Site jmnrcexamoutlineletter2 JDM/WWH/vah
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, SI)
Facility: SSES Date of Exam: 08112102 Exam Level: SRO KIA Category Points Tier Group I Point K K K K K K A A A A G Total A 2 3 4 5 6 1 2 3 41 3 Plant Toitear 7 7 7 v., .
7 ,
.8 0'L7 43 1 2 23 l2l2 l22 l22 l1 l3 l23l 2.I l l l l l l l I Plant 2 1 1 1 l1 l1 l2l1 l1 l1l1 l2 l 13 Systems 3 0 0.1 l0 l l.0
.1 l.0 l 1 l0 l0 l.1 l 4 Tioearl 3 3 5 l3 4 4 l3 4 l3 2 6 l 40 l
- 3. Generic Knowledge and Abilities l___
Cat1 _lCat2 Cat3 lCat 4ll 17 Note: 1. Ensure that at least two topics from every K/A category are sampled l within each tier (i.e., the "Tier Totals" in each K/A category shall not bel less than two).l
- 2. The point total for each group and tier in the proposed outline must l match that specified in the table. The final point total for each group l and tier may deviate by +/-1 from that specified in the table based on NRCl revisions. The final exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or l three K/A topics from a given system unless they relate to plant-specificl priorities.
- 4. Systems/evolutions within each group are identified on the associated l outline.l
- 5. The shaded areas are not applicable to the category/tier.l 6.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of thei K/A Catalog, but the topics must be relevant to the applicable evolutionl or system.l
- 7. On the following pages, enter the K/A numbers, a brief description of l each topic, the topics' importance ratings for the SRO license level, andl 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 ES401-1 (RB, SI)
Fmarnonev andI Ahnnrmal Plant Eunlutinns - Tier lGr.min I
..... . .... *1 E/APE # / Name / Safety Function K K K A A G KIA Topic(s) Imp. Point
__ _ __ _ _ _ _ _ _ 1 2 3 1 2 S 295003 Partial or Complete Loss of AC Pwr /6 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 296006 SCRAM /I1 X X AK1.03 Reactivity control 4.0 2
_ AA1.04 Recirculation system 3.2 296007 High Reactor Pressure 13 X X AK2.02 Reactor power 3.8 2
_ I_ AK3.06 Reactor/turbine pressure regulating system operation 3.8 296009 Low Reactor Water Level /2 X AA2.03 Reactor water cleanup blowdown rate 2.9 1 296010 High Drywell Pressure / X X AK2.01 Suppression pool level 3.3 2 I___AA1.02 Drywell floor and equipment drain sumps 3.6 296013 High Suppression Pool Temp. /6 X X AA2.02 Localized heating/stratification 3.6 2 2.4.31 Knowledge of annunciators alarms and indications, and use 3.4 of the response instructions 296014 Inadvertent Reactivity Addition / I X AK3.02 Control rod blocks 3.7 1 296016 Incomplete SCRAM /1 296016 Control Room Abandonment / 7 X X AA2.04 Suppression pool temperature 4.1 2 2.1.14 Know ledge of system status criteria which require the 3.3 notification of plant personnel 296017 High Off-site Release Rate / 9 X X AK1.02 Protection of the general public 4.3 2 2A.30 Knowledge of which events related to system 3.6 operations/status should be reported to outside agencies 295023 Refueling Accidents Cooling Mode /8 296024 High Drywell Pressure / 6 X X EKI.01 Drywell integrity: Plant-Specific 4.2 2 EK3.09 Auxiliary building isolation: Plant-Specific 3.6 296026 High Reactor Pressure /3 296026 Suppression Pool High Water Temp. /6 X X EK3.03 Suppression pool spray: Plant-Specific 3.8 2 EA2.02 Suppression Pool level 3.9 296030 Low Suppression Pool Water Level / 6 X EA1.02 RCIC: Plant-Specific 3.6 1 296031 Reactor Low Water Level /2 X X EK1.01 Adequate core cooling 4.7 2 EA2.02 Reactor power 4.2 296037 SCRAM Condition Present and Power Above APRM Downscale or Unknown II 295038 High Off-site Release Rate /9 X EK3.02 System isolations 4.2 1 600000 High Containment Hydrogen Conc. / 6 X X EK2.00 Wetwell spray system 3.4 2
_ _ EAI.01 Primary containment hydrogen instrumentation 3.3 K/A Category Totals: l l [14 1 514 [ Group PointTotal: l 261
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ES401 BWR SRO Examination OutlineForm ES.401-1 (RB, SI)
FI-I ------- A Annnn*O DI.*t fu ..
Ti-
-r.F.. n. 9 E/APE # Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 296001 Partial or Cormplete Loss of Forced Core X AK3.02 Reactor power response 3.8 1 Flow Circulation /I & 4 ______
296002 Loss of Main Condenser Vacuum /33 _ _ _
296004 Partial or Total Loss of DC Pwr /6 X _ = = AK1.06 Loss of breaker protection 3.4 1 296006 Main Turbine Generator Trip /3 X AA1.01 Recirculation system: Plant-Specific 3.3 1 296008 High Reactor Water Level /2 _ _
296012 Hiah Drywell Temperature / X X AA2.01 Drywell temperature 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 296019 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 295020 Inadvertent Cont. Isolation / 6 & 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 _ _ X 2.1.32 Ability to explain and apply system limits and precautions 3.8 1 295022 Loss of CRD Pumps / I _ _
295028 High Drywell Temperature / 6 X EK2.02 Components internal to the drywell 3.3 1 295029 High Suppression Pool Water Level /6 X 2.2.25 Knowledge of bases in technical specifications for limiting 3.7 1 conditions for operations and safety limits________
295032 High Secondary Containment Area Temperature / 6 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High X EA2.02 Cause of high radiation levels 4.2 1 Radiation /9 295035 Secondary Containment High X X EK1.01 Secondary containment integrity 4.2 2 Differential Pressure /6 EA1.02 SBGT/FRVS 3.8 295036 Secondary Containment High X EA2.01 Operability of components in the area 3.2 1 Sump/Area Water Level / 6 600000 Plant Fire On Site / 8 K/A Category Point Totals: 3 2 3 Group Point Total: 17
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ES401BWR SRO Examination OutlineForm ES401-1 (R8, SI)
Plant Systems - Tier 2/Groun I 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 3.6 1 209001 LPCS ___
211000 SLC _ _
212000 RPS _ _
216004 Source Range Monitor _ _ =_=_=_=
216000 Nuclear Boiler Instrumentation X K5.10 Indicated level versus actual during 3.3 1
___ _ _ vessel heatups and cooldowns 217000 RCIC X X K2.04 Gland seal compressor (vacuum 2.6 2 pump) 3.8 2.1.32 Ability to explain and apply system
___ 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 entry4evel condtions for technical
__ specifications 223001 Primary CTMT and Auxiliaries X X K2.09 Drywell cooling fans 2.9 2
_ K4.03 Containment/drvwell 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 K5.03 Reactor power vs. reactor pressure 3.6 1 259002 Reactor Water Level Control __X X A1.02 Reactor feedwater flow 3.5 1 261000 SGTS X X A2.13 High secondary containment 3.7 2 exhaust radiation 4.0 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system
__ _ _ _components and controls 262001 AC Electrical Distribution X X K1.01 Emergency generators 4.3 2
_ K3.02 Emergency generators 4.2 264000 EDGs
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290001 Secondary CTMT X X KI.07 Turbine building ventilation (steam 3.1 2 tunnel): Plant-Specific 3.6 K6.01 Reactor building ventilation: Plant-Specific Ttl l 23 IKA Categor Point Totals: 12 12 13 12 12 12 12 12 12 11 3 FGroup Point Total: 1 23
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ES-401BWR SRO Examination OutlineForm ES-401-1 (RS, 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 206000 Shutdown Cooling 214000 RPIS == ===
216002 RBM X K3.01 Reactor manual control system 3.6 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 246000 Main Turbine Gen. and Auxiliaries X = K6.01 Gland seal 2.9 1 269001 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 K1.02 Process radiation monitoring 3.3 2 2.4.6 Knowledge symptom based EOP 4.0 mitigation strategies P 4.0 272000 Radiation Monitoring X 2t4.30 Knowledge of which events related 3.6 1 to system operations/status should be reported to outside agencies 286000 Fire Protection = =_=_=_= =_=_== =_=
290003 Control Room HVAC X K6.01 Airborne contamination (eg. 3.6 1 300000IInstrumentAir_ Radiological. toxic gas, smoke) control l300000 Instrument Air = =__________________
_== = =_=
400000 Component CoolinaWater = X - - K2.02 CCW valves 2.9 1 K/A Category Point Totals: 1- 1 11 1 1 2 l11[1 1 l1 l2 l Group Point Total: - 13
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ES401 BWR 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 6_ __ _ _ _
201003 Control Rod and Drive Mechanism _ _ _
216001 Traversing In-core Probe X 2.4.49 Ability to perform without 4.0 1 reference tprcdethse actions that require immediate oheration of
- - _ system components and controls 233000 Fuel Pool Cooling and Cleanup X K3.06 Fuel pool water fission product 2.8 1
_____concentration 239001 Main and Reheat Steam 256000 Reactor Condensate X X K6.03 Heat exchanger level operation 2.7 2
_ A2.09 Low feedwater heater level 2.8 268000 Radwaste _
288000 Plant Ventilation _
290002 Reactor Vessel Internals _
KIA Category Point Totals: =E _ - 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): l
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, SI)
Facility: SSES Date of Exam: 08112102 Exam Level: RO I K/A Category Points l Tier Group Point K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 1.33-X--
.....0-f000 4 0 ;;g;000000013l 1~~~~~~. ... ...... _,..
C-0 Emergency & 2 3 4 4 -........ 3 3 ......... 2 19 Abnormal .. ... .....
Plant 3 1 1 0 1 .. 0. 4 Evolutions Tier.. 7 8 7 .. 8 4.._ 2 3
-.......... . I I. I.I.I..
l 1 l3l2 l3l2 l3l2 l3l3 l2 l3 l2 l 28 l
- 2. __ _ _ _
l 2 Totals l3l2 l2l2 .........
l2l3 l0l2 l1 l2 l0 l 19 Systems l 3 l0 l1 l1l0 l0l0 l1l0 l1l0 l0 l 4 Tier 76 5 6 4 5 l 5 4 l l.4 .5 l.5 l.2 51 2 2 Cat 1 Cat2 Cat3 Cat4 1
- 3. Generic Knowledge and Abilities c I 2 l C 13 1 3 3 1 3 4 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. 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 RO Examination OutlineForm ES-401-2 (Re, SI)
Emergency and Abnormal Plant Evolutions - Tier 1lGroup 1 __
E/APE #/ Name / Safety Function K K K A A G K/A Topic(s) Imp. Points
_ _ __ _ _ _ _ _ _ _ _ _ _ 1 2 3 1 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _
296006 Main Turbine Generator Trip / 3 X AA1.01 Recirculation system: Plant-Specific 3.1 1 296006 SCRAM I I X X AKI.03 Reactivity control 3.7 2
_ AA1.04 Recirculation system 3.1 295007 High Reactor Pressure /3 X X AK2.02 Reactor power 3.8 2
_ AK3.06 Reactor/turbine pressure regulating system operation 3.7 295009 Low Reactor Water Level 12 296010 High Drywell Pressure /6 X X AK2.01 Suppression pool level 3.2 2
___ AAI.02 Drywell floor and equipment drain sumps 3.6 296014 Inadvertent Reactivity Addition I X _ AK3.02 Control rod blocks 3.7 1 296016 Incomplete SCRAM I 1 296024 High Drywell Pressure /5 X X EK1.01 Drywell integrity: Plant-Specific 4.1 2
_ _ EK3.09 Auxilary Building isolation: Plant-Specific 3.1 296026 High Reactor Pressure /3 296031 Reactor Low Water Level /2 X EK1.01 Adequate core cooling 4.6 1 296037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 500000 High Containment Hydrogen Conc. /6 X X EK2.06 Wetwell spray system 3.0 2
_ EA1.01 Primary containment hydrogen instrumentation 3.4 K/A Category Totals: 3 3 3 4 0 0 Group Point Total: = 13
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Fmarnanru andi Ahnnmnal Pl2nt FunEltinns - Tier l/Mromn 2 E/APE # Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
296001 Partial or Complete Loss of Forced Core X AK3.02 Reactor power response 3.7 1 Flow Circulation / I & 4 296002 Loss of Main Condenser Vacuum /3 296003 Partial or Complete Loss of AC Pwr /6 X AK2.01 Station batteries 3.2 1 296004 Partial or Complete Loss of DC Pwr /6 X AK1.06 Loss of breaker protection 3.3 1 296008 High Reactor Water Level /2 295012 High Drywell Temperature IS 295013 High Suppression Pool Temp. /6 X 2.4.31 Knowledge of annunciators alarms and indications, and use 3.3 1 of the response instructions 296016 Control Room Abandonment /7 X X AA2.04 Suppression pool temperature 3.9 2
_ _ 2.4.6 Knowledge symptom based EOP mitigation strategies 3.1 296017 High Off-site Release Rate / 9 X X AK1.02 Protection of the general public 3.8 2 AA1.10 RPS 3.6 295018 Partial or Complete Loss of CCW / 8 X X AK2.01 System loads 3.3 2 AK3.06 Increasing cooling water flow to heat exchangers 3.3 295019 Part. or Comp. Loss of Inst. Air / 8 X AA1.02 Instrument air system valves: Plant-Specific 3.3 1 296020 Inadvertent Cont. Isolation /6 & 7 X X AK1.04 Bottom head thermal stratification 2.6 2 AK2.06 HPCI: Plant-Specific 3.8 295022 Loss of CRD Pumps / 1 296026 High Suppression Pool Water Temp. / 6 X X EK3.03 Suppression pool spray: Plant-Specific 3.5 2 EA2.02 Suppression pool level 3.8 295028 High Drywell Temperature / 6 X X EK2.02 Components internal to the drywell 3.2 2 EA2.06 Torus/suppression chamber pressure: Plant-Specific 3.6 296029 High Suppression Pool Water Level /6 _
296030 Low Suppression Pool Water Level / 5 _ X EA1.02 RCIC: Plant-Specific 3.4 1 295033 High Sec. Cont. Area Rad. Levels /9 298034 Sec. Cont. Ventilation High Rad. /9 _
295038 High Off-site Release Rate /9 X EK3.02 Svstem isolations 3.9 1 600000 Plant Fire On Site /8 ___
K/A Category Point Totals: 3 4 4 3 2 Group Point Total: = 19
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ES.401 BWR RO Examination OutlineForm ES401-2 (R8, SI)
Fm rn. .. :a...A An.,.. l la.nt .vT.s,.dId,,... _ .a E/APE # Name / Safety Function K K K A A G KIA Topic(s) Imp. Points 1 2 3 1 2 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
296021 Loss of Shutdown Cooling /4 X AK2.07 Reactor recirculation 3.1 1 296023 Refueling Accidents /8 X AA2.01 Area radiation levels 3.6 1 296032 High Secondary Containment Area Temperature /5 296036 Secondary Containment High X X EKI.01 Secondary containment integrity 3.9 2 Differential Pressure /56 EAI.02 SBGT/FRVS 3.6 ___
295036 Secondary Containment High Sump/Area Water Level /6
. . .-t . . . .
I I t- .- . . . - .4 4- .4 . .--4 -- . - .
_II 4 4 K/A Category Point Totals: I 1I 1 0I II II I 0 Group Point Total: 1 4
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, S1)
Plant Systems - Tier 2/Group 1 ____ _ ____ _ _____
System #/Name 1K K K 6 A A A K/A Topiczs) Imp. Points 201001 CRD Hydraulic 201002 RMCS X A4.06 Rod select matrix 3.1 1 202002 Recirculation Flow Control ____X A3.03 Scoop tube operation 3.1 1 203000 RHR/LPCI: Injection Mode X X K6.06 Suppression pool 3.8 2
_ A1.09 Component cooling water system 2.9 206000 HPCI X A3.01 Turbine speed 3.6 1 209001 LPCS X X K1.14 Reactor vessel 3.7 2 A4.05 Manual initiation controls 3.8 211000 SLC X 2.1.33 Ability tp recognize indications and 3.4 1 systemn ope rat in a ameters which are ehtr -eveJ condqions for technical specitncations 212000 RPS X 2.4.4 Ability to recognize abnormal for 4.0 1 system oeperatinggparamneters which are ehtr -leV I cond ions for emergency and abn_6ral operating procedures 216003 IRM X X Kl.p04 isplay control system: Plant- 3.3 2 Specic 3.1 A4404 dRM back Panel switches, meters andicatinglImphs 215004 SRM 215005 APRM / LPRM I X = = A2.03 Inoperative trip (all causes) 3.6 1 216000 Nuclear Boiler Instrumentation X K6.10 Indicated level versus actual during 3.1 1 vessel heatups or cooldowns 217000 RCIC X X K2.04 Gland seal compressor (vacuum 2.6 2 pump) 3.5 K3.03 Decay heat removal 218000 ADS X X K3.02 Ability to rapidly depressurize the 4.5 2 reactor 4.1 A1.04 Reactor pressure 223001 Primary CTMT and Auxiliaries X X K2.09 Drywell cooling fans: Plant-Specific 2.7 2 K4.03 Containment/drywell isolation 3.7 223002 PCIS/Nuclear Steam Supply Shutoff X X IS3.14.Recirculation system: Plant- 3.0 2 b~eCITIC3.5
_K4.03flanual initiation capability: Plant-239002 SRVs X X KI.06 Dr~ywelL instrument air/drywell 3.4 2 pneumatics: Plant-Specific 3.1
__ A2.02 Leaky SRV 241000 Reactor/Turbine Pressure Regulator X X K6.03 Reactor power vs. reactor pressure 3.6 2 K6.02 DC electrical power 2.6
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259001 Reactor Feedwater =_ = = =
I=II_ = == = _
269002 Reactor Water Level Control X X K6.03 Water level measurement 3.1 2
___ A1.02 Reactor feedwater flow 3.6 261000 SGTS ==X A2.13 High secondary exhaust radiation 3.4 1 264000 EDGs I I K/A Category Point Totals: _ _ 3 1 _ 3 _ 3 _ Group Point Total: = 28
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ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Plant Systems - Tier 2/Group22 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 ___ _
201004 RSCS X K6.02 Rod direction information 3.1 1 201006 RWM 202001 Recirculation X A3.07 Pump trips: Plant-Specific 3.3 1 204000 RWCU 206000 Shutdown Cooling 214000 RPIS 215002 RBM X K3.01 Reactor manual control system 3.3 1 219000 RHR/LPCI: Torus/Pool Cooling Mode 226001 RHRILPCI: CTMT Spray Mode X A4.09 Pump discharge pressure 2.8 1 230000 RHR/LPCI: Torus/Pool Spray Mode X X K2.02 Pumps 2.8 2 K4.07 Prevention of water hammer 3.1 239001 Main and Reheat Steam 245000 Main Turbine Gen. and Auxiliaries X K6.01 Gland seal 2.8 1 266000 Reactor Condensate X X K6.03 Heat exchanger level operation 2.6 2 A2.09 Low feedwater heater level 2.8 262001 AC Electrical Distribution X X K1.01 Emergency generators 3.8 2 K3.02 Emergency generators 3.8 262002 UPS (AC/DC) X A4.01 Transfer from alternate source to 2.8 1 preferred source 263000 DC Electrical Distribution X A2.01 Grounds 2.8 1 271000 Offgas X K1.02 Process radiation monitoring 3.1 1 272000 Radiation Monitoring 286000 Fire Protection _
290001 Secondary CTMT X X K1.07 Turbine building ventilation (steam 3.0 2 tunnel): Plant-Specific 3.5 K6.01 Reactor building ventilation: Plant-Specific 290003 Control Room HVAC X K6.01 Airborne contamination (e.g. 3.2 1 Iradioloical toxic qas. smoke) control 300000 Instrument Air _
400000 Component Cooling Water X X K2.02 CCW valves 2.9 2
_ _ K4.01 Automatic start of standby pump 3.4 KJA Category Point Totals: l3 12 [2 l2 12 l3 l0 l2 l1 l2 l0 Group Point Total: - 19
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ES401 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_ _
216001 Traversing In-core Probe X A3.03 Valve operation 2.6 1 233000 Fuel Pool Cooling and Cleanup X X K2.02 RHR pumps 2.8 2 K3.06 Fuel pool water fission product 2.6
____ _ _ _ _ _ concentration __
234000 Fuel Handling Equipment X _ A1.03 Core reactivity level 3.4 1 239003 MSIV Leakage Control 268000 Radwaste 288000 Plant Ventilation _____ _
290002 Reactor Vessel Internals K/A Category Point Totals: 0 I 1 [ O O I01il O 0 lo0 Group Point Total: 4 Plant-Specific Priorities System / 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) 11
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 (R8, S1)
Facility: SSES Date of Exam: 08112/02 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 2.1.13 Knowledge of facility requirements for 2.9 1 controlling vital/controlled access ll Conduct of 2.1.28 Knowledge of the purpose and function of 3.3 1 Operations major system components and controls l 2.1.23 Ability to perform specific system and 4.0 1 integrated plant procedures during different modes of plant operation Total 4 2.2.3 (multi-unit) Knowledge of the 3.3 1 designlproceduralland operational; differences between units 2.2.19 Knowledge of maintenance work order 3.1 1 requirements 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 operationsiand supporting instrumentation I Total 4 2.3.3 Knowledge of SRO responsibilities for 2.9 I auxiliary systems that are outside the control room (eg. Waste disposal and handling systems) 2.3.1 Knowledge of 10CFR: 20 and related facility 3.0 1 Radiation radiation control requirements 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 1 immediate action steps 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 Total 5 Tier 3 Point Total (ROISRO) 1 13/17
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 (R8, SI)
Facility: SSES Date of Exam: 08112102 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 2.1.23 Ability to perform specific system and 3.9 1 Conduct of integrated plant procedures during different Operations modes of plant operation 2.1.16 Ability to operate plant phonelpaging 2.9 1 system/and two-way radio Total 3 2.2.24 Ability to analyze the affect of maintenance 2.6 1 on LCO status 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 2.2.22 Knowledge of limiting conditions for 3.4 1 operations and safety limits Total _ 3 2.3.11 Ability to control radiation releases 2.7 1 laitin 2.3.9 Knowledge of the process for performing a 2.5 1 Raitol containment purge IControl 2.3.2 Knowledge of facility ALARA program 2.5 1 Total 3 2.4.16 Knowledge of EOP implementation 3.0 1 hierarchy and coordination with other l_ support procedures 2.4.21 Knowledge of the parameters and logic 3.7 1 Emergency used to assess the status of safety Procedures/ functions including:
Plan 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 2.4.27 Knowledge of fire in the plant procedures 2.9 1 l Total 4 Tier 3 Point Total (RO/SRO) 13/17
ES-301 Administrative Topics Outline Form ES-301-1 (R8, SI)
Facility: SSES Date of Examination: 08/12/02 Examination Level (circle one): RO gk Operating Test Number: A-SRO Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 CONDUCT OF Requirements to maintain license-2.1.1 (3.8)
OPS Discovery of mispositioned control rod-2.1.20 (4.2)
Action when less than required staffing at shift turnover-2.1.4 (3.4)
Working hour restrictions-2.1.1 (3.8)
A.2 EQUIPMENT JPM - Review failed surveillance test and determine action-CONTROL 2.2.24 (3.8)
A.3 RADIATION Authorizing exceeding station/NRC limits-2.3.4 (3.1)
CONTROL Actions for Locked High Rad door found open on tour-2.3.10 (3.3)
A.4 EMERGENCY JPM - Fill out classification paperwork-2.4.40 (4.0)
PLAN
ES-301 Administrative Topics Outline Form ES-301-1 (R8, S1)
Facility: SSES Date of Examination: 08/12/02 Examination Level (circle one) RO9SRO Operating Test Number: A-RO Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 CONDUCT OF Requirements to maintain license-2.1.1 (3.7)
OPS Discovery of mispositioned control rod-2.1.20 (4.3)
Requirements for temporary relief-2.1.3 (3.0)
Requirements for temp mod of procedure2.1.21 (3.1)
A.2 EQUIPMENT JPM - Review failed surveillance test and determine action-CONTROL 2.2.24 (2.6)
A.3 RADIATION Stay time limits-2.3.1 (2.6)
CONTROL Requirements for High Rad entry-2.3.10 (2.9)
A.4 EMERGENCY Action if an ALERT is announced while in RB performing a PLAN task-2.4.39 (3.3)
Notification Requirements for an ALERT Declaration-2.4.43 (2.8)
ES-301 Control Room Systems Form ES-301-2 (R8, Sl) and Facility Walk-Through Test Outline I
Facility: SSES Date of Examination: 08/12102 Exam Level (circle one): RgO SRO(U Operating Test No.: B-SRO-l B.1 Control Room Systems System I JPM Title Type Safety Code* Function
- a. 239001 - Equalize and Reopen MSIVs N,S 3 ON-184-001
- b. 259002 - Respond to a Failure of "A" RFPT M,S,A 2 SPDICTLIDEMAND Signal ON-145-001
- c. 215004 - Respond to an SRM Failure N,S,L 7 Alarm Response
- d. 209001 - Manually Initiate Core Spray with Initiation M,S,A 2 Logic Failure OP-1 51 -001
- e. 223002 - Bypass MSIVICIG interlocks with CIG Isolation M,S,A 8 Occurring OP-184-001
- f. 211000 - Initiate Standby Liquid Control with RWCU D,S,A I Valve Failure to Isolate OP-153-001
- g. 206000 - HPCI Recovery from Isolation Valve Closure D,S,A 2 with Initiation Signal Present and a Steam Leak Developing OP-152-001 B.2 Facility Walk-Through
- a. 230000 - Line up Unit 2 Suppression Chamber Spray M,R 5 using Fire Protection Water without Electrical Power Available ES-01 3-001
- c. 223001 - Start a Unit 2 Hydrogen Recombiner M 5 OP-273-001 I
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate 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(I) Operating Test No.: B-SRO-U B.1 Control Room Systems System / JPM Title Type Safety Code* Function
- a. 239001 - Equalize and Reopen MSIVs N,S 3 ON-184-001 b.
c.
- d. 209001 - Manually Initiate Core Spray with Initiation M,S,A 2 Logic Failure OP-151-001 e.
- f. 211000 - Initiate Standby Liquid Control with RWCU D,S,AI Valve Failure to Isolate OP-1 53-001 g.
B.2 Facility Walk-Through
- a. 230000 - Line up Unit 2 Suppression Chamber Spray M,R 5 using Fire Protection Water without Electrical Power Available ES-01 3-001
- 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, SI) and Facility Walk-Through Test Outline . .
Facility: SSES Date of Examination: 08/12/02 Exam Level (circle one)R SRO(I) / SRO(U' Operating Test No.: B-RO B.1 Control Room Svstems System I JPM Title Type Safety Code* Function
- a. 239001 - Equalize and Reopen MSIVs N,S 3 ON- 84-001
- b. 259002 - Respond to a Failure of "A" RFPT M,S,A 2 SPDICTLUDEMAND Signal ON-145-001
- c. 215004 - Respond to an SRM Failure N,S,L 7 Alarm Response
- d. 209001 - Manually Initiate Core Spray with Initiation M,S,A 2 Logic Failure OP-1 51-001
- e. 223002 - Bypass MSIV/CIG interlocks with CIG Isolation M,S,A 8 Occurring OP-184-001
- f. 211000 - Initiate Standby Liquid Control with RWCU D,S,A 1 Valve Failure to Isolate OP-153-001
- g. 206000 - HPCI Recovery from Isolation Valve Closure D,S,A 2 with Initiation Signal Present and a Steam Leak Developing OP-152-001 B.2 Facility Walk-Through
- a. 230000 - Line up Unit 2 Suppression Chamber Spray M,R 5 using Fire Protection Water without Electrical Power Available ES-01 3-001
- c. 223001 -Start a Unit 2 Hydrogen Recombiner M 5 OP-273-001
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Itemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
Appendix D Scenario Outline Form ES-D-1 (R8, SI)
Facility: SSES Scenario No.: _ Op-Test No.: CI_
Examiners: Operators: US - #21 #4/ #6
_PCOM - #1 i #3 x#5 PCOP - #9/#1 0I#1l 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 I 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 RD155008 C Control rod scrams when RPS A de-energizes (fuse) 5 RD155006 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
For ES-- TO Si) 0 Scenario Ouln Scnai to -A \
Appendix D Apeni FO Outline Form ESAM (KU, 51)
Facility: SSES Scenario No.: 2 Op-Test No.: C1 Examiners: .
Operators: US - #1/ #3/ #5 PCOM -#71 #1O/#11 PCOP - #21 #41 #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 1 N Secure A CRD pump and Start B CRD pump 2 R Power Control requests power drop of 100 MWe 3 FW145009A C Trip of RFPT A 4 NM178012D I Recirc flow Unit failure downscale 5 PM03 C Loss of CRD Flow / INOP Accumulator 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 RC150002 I RCIC Speed Controller Failure 10 BRO5 C Loss of Aux bus 1A/B I i i I
I 4 +
L _________________________________________________________________
I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 (R8, Appendix 0 Scenario Outline Form ES-D-1 (R8, SI) 51)
Facility: SSES Scenario No.: 3 Op-Test No.: Ci1 Examiners: Operators:: US - #71 #X/ #8 PCOM - #91#41#6 PCOP -#1/#31 #5 Initial Conditions: _ 50% Rated Power Standby Liquid pump IB is Inoperable while Maintenance investigates a high motor vioration Turnover: Transfer SUB 10 to SUT 10 then continue power ascension Event Malf. No. Event Event No. Type* Description I N Transfer SUB 10 to SUT 10 I
2 R Continue power ascension to raise power 3 TRO2 I B Feedwater Flow Transmitter Fails Low 4 TH02 l I Inadvertent HPCI Isolation Due to Failed Room Temperature Instrument 5 lA118002 C Loss of Instrument Air 6 RRI 6401A M Recirc loop B suction Rupture DBA 0-40%
7 RLOI C AUTO ADS Logic Failure 8 MV06:HVI5 C Loop B RHR Injection Valve Fails to Open I F OI 5 B_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
t 1-
-I r
t *1-rI1I r(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Facility: SSES Scenario No.: 4 Op-Test No.: C1 Examiners:_ Operators:: US - #8 PCOM --#2 Initial Conditions: 90% Rated Power B EHC pump is OOS for breaker maintenance 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* l Description 1 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 SL53001 C SLC Squibb Valves Fail 8 PM03 C B EHC Pump Trip 4 +
(R)eactivity, (I)nstrument, (C)omponent, (M)ajor
- (N)ormal, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
I- , I Appendix D Scenario Outline F-orm ES-D-1 (8 1 Appendix D Scenario Outline Facility: SSES Scenario No.: 5 (SPARE) Op-Test No.: C1 Examiners: Operators:SRO-I ISRO-U SRO-I RO 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 1 R Reduce reactor power for pump removal 2 N Secure 1B Condensate pump 3 l "A" Narrow Range level instrument fails upscale 4 RRI 79003 C Fuel clad failure ramped 5 RP158007 I Failure of a RPS to trip - Half scram failure A_
6 MS1 83008 M MSL leak Inside Turbine Building I 7 C "D" MSL failure to isolate - stem binding
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
February 4, 2002 Mr. Alan Blarney pp :;^ ~
USNRC Chief Examiner TM US NRC Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Susquehanria Learning Center Bases for Suppression of K/As For the SSES NRC Examination PLA 005439 PLI A14-13
Dear Alan:
Per our discussion on January 28, 2002, SSES has reviewed your comments regarding suppression of K/As in NUREG 1123, Rev. 2, and in documentation on Form ES-401-10, Record of Rejected K/As. As you are aware, this discussion was a follow-up to letter PLA005433/PLI A 14-13 from Jeff Helsel (PPL) dated January 17, 2002. That letter provided a markup of NUREG-1 123 indicating all K/A's that SSES proposed to suppress for future NRC examinations. Our discussion on January 28, 2002, indicated general acceptance of the submitted markup copy of NUREG-1 123 with few exceptions. Those exceptions and associated resolutions are addressed in this letter.
As discussed, generic K/As not applicable to Tier I and Tier 2 of the SRO/RO exam outlines will be suppressed per the NRC 'Clarification of Guidance Regarding the Elimination of Inappropriate Knowledge and Abilities (K/As) on Written Operator Licensing Examinations' letter. As per the direction provided in the referenced letter, K!A 2.4.30 will not be suppressed. However, it should be noted that the RO outline will not select this K/A due to an importance rating less than 2.5.
As per NRC guidelines, K/As wvith importance ratings less than 2.5 will not be selected unless proper justification is provided. K/As with an importance rating less than 2.5 and having a '*'
next to the rating were reviewed and determined to be a valid rating for SSES with one exception:
K/A 217000 A2.04 (importance rating of 2.3 for RO and SRO) as described below:
- 217000 A2.04 will be UNSUPPRESSED due to SSES PRA identifying SBO as a core damage event. This K/A will be listed as a plant specific priority per ES-40 1.
The majority of the proposed items required no additional clarification beyond that provided in the initial letter. Those items that the Chief Examiner did request additional information were discussed and resolved as follows:
- 201001 A4.02 will remain suppressed due to SSES design not including control room control or indications for these manual valves.
- 201001 A4.05 will remain suppressed due to SSES design not including a cooling Water Pressure Control Valve.
- 201002 A3.04 will remain suppressed due to SSES design not including an alarm for this malfunction in the control room.
- 201002 A4.04 will remain suppressed due to SSES design not including a test switch for this malfunction in the control room.
- 202002 K4.04 will remain suppressed due to SSES design not including a connection to the load following circuit.
- 202001 A2.07 will be UNSUPPRESSED since speed can be determined on a back panel indicator and could relate to the procedure driven flow mismatch.
- 211000 K6.04/6.05 will remain suppressed due this relation to RCIC for alternate boron injection being covered by 295037 EA I.10.
- 206000 Kl.13 will be UNSUPPRESSED due to SSES design having interconnection between HPCI drains and the main condenser.
- 206000 Kl.15 will be UNSUPPRESSED since the system drain valves are air operated, however this K/A will not be selected due to importance rating less than 2.5.
- 206000 K5.03 will remain suppressed due to SSES design not including GEMAC controllers, however design includes BAILEY controllers covered by 206000 K5.05.
- 209001 A4.07 will remain suppressed due to SSES design not including a system fill pump, instead SSES uses a connection to Condensate Transfer covered by 295031 EA1.08.
- 256000 A3.09 will remain suppressed due to SSES design not including indication of drain tank level or having a level control device.
- 217000 KI.08 will remain suppressed due to SSES design not including a system fill pump, instead SSES uses a connection to Condensate Transfer covered by 295031 EAI.08.
- 217000 A2.06 will be UNSUPPRESSED due to SSES design using air operated valves in the drain lines, however this K/A will not be selected due to importance rating less than 2.5.
- 218000 KI.05 will remain suppressed due to SSES design not including ADS logic or circuit control being provided at the Remote Shutdown Panels-
- 241000 A3.06 will be UNSUPPRESSED since SSES design does include a direct scram from EHC low oil pressure (via TCV fast closure).
- 241000 A3.17 will remain suppressed due to SSES design not including turbine runbacks, stator cooling causes a direct trip of turbine without a runback.
- 262001 KI.06 will be UNSUPPRESSED due to SSES design using a portable diesel to provide power.
A revised Form ES-401-10, Record of Rejected K/As, a revised markup of NUREG-1021 indicating suppressed (lined-out) items, and a listing of suppressed items are included as attachments to this letter for NRC record. Those items that are lined-out are considered not applicable to SSES design and are therefore suppressed. Items that have an importance rating less than 2.5 but are applicable to SSES design are not lined-out even though they will not be selected as an examination item (wvith the exception of K/A 217000 A2.04 as noted above).
If you have any questions, please feel free to call me at (570) 542-3510 or Jeff Morris at (570) 542-3678.
Sincefely, J. . Helsel Supervisor Operations Instruction Response: No Attachment cc: W. W. Hunt Ops Letter File Nuc Records - Site jmplaOO5439suppressionofKAs JDM/JMH/cae
ES-401 Record of Rejected K/As Form ES-401 -1 0 (R8, S1)
SUSQUEHANNA STEAM ELECTRIC STATION Tier/ Randomly Selected Reason for Rejection IGroup 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. Blamey 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 EA1.10.
- 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 l _ considered as a plant specific priority per ES-401
(
ES-401 Record of Rejected WAS 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 EA1.10.
- 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
(
PPI SUSQUEHANNA STEAM ELECTRIC STATION The attached list of K&As (16 pages) have been determined to be NOT APPLICABLE to the design of the Susquehanna Steam Electric Station and as a result, will be suppressed during the generation of NRC licensed operator examinations.
Ki - Knowledge of the physical connections and/or cause-effect relationships between and the following:
K2 - Knowledge of electrical power supplies to the following:
K3 - Knowledge of the effect that a loss or malfunction of the will have on the following:
K4 - Knowledge of design feature(s) and/or interlock(s) which provide for the following:
K5 - Knowledge of the operational implications of the following concepts as they apply to the:
K6 - Knowledge of the effect that a loss or malfunction of the following will have on the:
Al - Ability to predict and/or monitor changes in parameters associated with operating the controls including:
A2 - Ability to (a) predict the impacts of the following on the and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
A3 - Ability to monitor automatic operations of the including:
A4 - Ability to manually operate and/or monitor in the control room:
E/AKI - Knowledge of the operational applications of the following concepts as they apply to the:
E/AK2 - Knowledge of the interrelations between and the following:
E/AK3 - Knowledge of the reasons for the following as they apply to:
E/AAl - Ability to operate and/or monitor the following as they apply to:
E/AA2 - Ability to determine and interpret the following as they apply to:
(
CATEGORY K/A DESCRIPTION REACTIVITY CONTROL 201001 K1.04 Head spray:BWR-3 K1.05 Feedwater [or reactor water cleanup]-CRD return to vessel: Plant-Specific K3.04 Head spray:BWR-3 Al.04 Head spray flow:BWR-3 A4.02 CRD pump discharge valve A4.05 Cooling water header pressure control valve 201002 K4.06 Emergency In rod insertion A3.04 Rod movement sequence timer malfunction alarm: Plant-Specific A4.04 Timer malfunction test switch: Plant-Specific 202002 K1.04 Reactor/turbine pressure regulating system: Plant-Specific K1.12 Recirculation flow control valves: Plant-Specific K2.02 Hydraulic power unit: Plant-Specific K3.06 Recirculation flow control valve position: Plant-Specific K4.04 Automatic load following: Plant-Specific K4.08 Automatic flow control valve positioning: BWR 5,6 K4.09 Minimum and maximum flow control valve position setpoints: BWR 5,6 K6.06 Reactor/turbine pressure regulating system: Plant-Specific K6.07 APRM signal input: BWR 5,6 Al.08 Recirculation FCV position: BWR 5,6 A2.08 FCV lockup: BWR5,6 A3.01 Flow control valve operation: BWR 5,6 A4.02 Hydraulic power unit: BWR 5,6 202001 K1.04 Reactor/turbine pressure regulating system: Plant-Specific K1.24 Isolation condenser: Plant-Specific K2.04 Hydraulic power unit oil pumps: Plant-Specific K3.02 Load following capabilities: Plant-Specific K3.12 Isolation condenser: Plant-Specific K4.15 Slow speed pump start: Plant-Specific I
(
202001 continued K4.17 Fast speed pump start: Plant-Specific K5.08 E/P converters: Plant-Specific K5.09 Hydraulically operated valves: Plant-Specific A1.08 Recirculation FCV position: BWR 5,6 A2.23 Suppression pool level: BWR 2,3,4 A2.25 Recirculation flow control valve lockup: Plant-Specific A3.06 Flow control valve position: BWR 5,6 A3.08 Pump downshift: BWR 5,6 201005 ALL RCIS 211000 K1.10 HPCI: Plant-Specific K6.04 Core spray system: Plant-specific K6.05 HPCI: Plant-Specific A1.05 Pump amps: Plant-Specific REACTOR WATER INVENTORY CONTROL 206000 K4.15 Low speed turning of the turbine rotor: BWR-2,3,4[P-Spec]
K4.16 Minimizing fission product concentration in the condensate storage tank [valve closures on system initiation]: BWR-2,3,4[P-Spec]
K5.03 GEMAC controllers: BWR-2,3,4[P-Spec]
A4.11 Turning gear: BWR-2,3,4[P-Spec]
209002 ALL HPCS 209001 K5.03 Testable check valve operation K5.06 Recirculation operation: Plant-Specific [BWR- 1]
K6.09 Fire protection: BWR-1 A2.11 Loss of fire protection: BWR-1 A4.06 Testable check valves A4.07 Fill pump A4.14 Containment level: BWR-l
__ __ _ _ _ _ _ _ _ _ J _ _I I _ _ _ _ _ _ _ _ _ _ _ _ _ _
2
256000 KI.09 Offgas condenser: Plant-Specific K 1.12 Isolation condenser: Plant-Specific K1.14 RHR [LPCI]: Plant-Specific K1.15 HPCS: Plant-Specific K 1.21 Steam seal evaporator: Plant-Specific K1.24 Radwaste system: Plant-Specific K3.07 Isolation condenser: Plant-Specific K3.12 HPCS: Plant-Specific K4.01 Condensate and/or booster pump auto start: Plant-Specific K4.11 Isolation of SJAE's on low flow: Plant-Specific A3.09 Feedwater heater drain tank level: Plant-Specific A4.14 Feedwater heater drain tank level: Plant-Specific 217000 K1.05 Residual heat removal system K1.08 Line fill pump: Plant-Specific 259001 KI.15 RHR: Plant-Specific K 1.18 Fire protection system [emergency cooling]: Plant-Specific KI.19 Redundant reactivity control system: Plant-Specific K2.01 Reactor feedwater pump(s): Motor-Driven-Only K3.10 HPCS: Plant-Specific K4.01 Auto start of RFP's: Plant-Specific K4.07 RFP motor cooling: Motor-Driven-Only K4.10 Feedpump runbacks; Plant-Specific K6.08 Reactor feedwater pump motor ventilation: Motor-Driven-Only K6.13 Redundant reactivity control: Plant-Specific Al.03 RFP motor amps: Motor-Driven-Only A3.01 RFP auto start: Plant-Specific A3.02 Motor amps: Motor-Driven-Only A3.07 FWRV position A3.11 Reactor feedpump runbacks; Plant-Specific A4.08 FWRV position
_ _ _ _ _ _ _ _ _ _ _ I __ I _ ___________
3
204000 K 1.13 RHR system: Plant-Specific K4.08 Reducing reactor pressure upstream of low pressure piping: LP-RWCU K5.01 Electro/Pneumatic converter operation K5.06 Pressure controllers A2.02 Pressure control valve failure: LP-RWCU A3.01 System pressure downstream of the pressure regulating valve: LP-RWCU 259002 K1.09 P sat/T sat [compensation]
K1.10 Emergency generator(s): FWCIIHPCI KI.11 Drywell pressure: FWCIIHPCI KI.12 Emergency condensate transfer pump: FWCJIHPCI K2.02 Feedwater coolant injection [FWCI] initiation logic: FWCIIHPCI K4.03 Reactor feedpump runout protection: MDFP K4.05 P sat/T sat [compensator]
K4.07 TDRFP 20% power interlock: TDRFP K4.11 DP control: Plant-Specific K4.13 FWRV lockup K4.15 Automatic initiation of feedwater system upon receipt of an ECCS initiation signal:
FWCI/HPCI K4.16 Dedication of feedwater string(s) to ECCS: FWCIHPCI K5.08 Heat removal mechanisms: FWCI K5.09 Adequate core cooling: FWCI K6.06 Reactor pressure/temperature input [for water level input compensation]
K6.07 Drywell pressure input: FWCI Al.05 FWRV/startup level control position: Plant-Specific Al.06 Feedwater string(s) for FWCI: FWCI A2.04 RFP runout condition: Plant-Specific A2.08 Receipt of an ECCS initiation signal: FWCI A2.09 FWCI system failure alarm: FWCI A3.01 Runout flow control: Plant-Specific A3.07 FWRV lockup A3.08 FWCI system initiation: FWCI A3.09 Transfer of system from flow control to level control mode: FWCI A4.04 FWRV lockup reset controls 4
259002 continued A4.05 Runout flow control reset controls: Plant-Specific A4.08 Manually initiate FWCI: FWCI 203000 K4. 11 Loop selection logic: Plant-Specific A2.15 Loop selection logic failure: Plant-Specific A3.07 Loop selection: Plant-Specific REACTOR PRESSURE CONTROL 218000 K1.05 Remote shutdown system: Plant-Specific 239001 K1.05 Moisture separator reheaters: Plant-Specific K1.13 Main steam isolation valve leakage control: Plant-Specific K1.14 Positive leakage control system: Plant-Specific K1.20 Residual heat removal system: Plant-Specific K1.21 Isolation condenser system: Plant-Specific K2.02 Main steam line shutoff valves [guard valves]: Plant-Specific K3.12 Isolation condenser: Plant-Specific K3.13 Moisture separator reheaters: Plant-Specific K3.14 Residual heat removal system: Plant-Specific K4.03 Insures that steam released from a steam line break will not bypass suppression pool:
BWR-6 K4.11 Positive sealing of the MSIV's when shutdown: Plant-Specific K5.04 Definition and reason for steam blanketing of moisture separator reheaters: Plant-Specific K5.07 Hydraulic operated MSIV's K6.07 MSIV leakage control K6.10 ADS/low low set: Plant-Specific A1.03 Reheat steam pressure: Plant-Specific A1.04 Reheat temperature: Plant-Specific A3.03 Moisture separator reheat steam supply: Plant-Specific A3.04 Isolation of Moisture separator reheater: Plant-Specific
_ _ _ _ _ _ __ _ _ _I I _ ___________
.4- 4 5
241000 K1.23 Recirculation flow control system: Plant-Specific KI.34 EGC system: Plant-Specific K1.35 Low pressure stop and control valves: Plant-Specific K1.36 Primary water system: Plant-Specific K1.37 Turbine stress evaluator: Plant-Specific K3.21 Recirculation flow control system: Plant-Specific K3.28 Low pressure stop and control valves: Plant-Specific K3.30 EGC: Plant-Specific K4.11 Load following: Plant-Specific K4.12 Recirculation flow control: Plant-Specific K5.07 Unitized actuator operation: Fermi-Only K6.04 Recirculation flow control system: Plant-Specific K6.18 Low pressure stop and control valves: Plant-Specific K6.19 Primary water system: Plant-Specific A2.25 Loss of primary water system: Plant-Specific A3.14 Grid load following: Plant-Specific A3.15 Recirculation pump flow control: Plant-Specific A3.17 Turbine runback 239002 K1.09 Drywell pressure [for safety valves which discharge to the drywell airspace]: Plant-Specific K4.01 Insures that only one or two safety/relief valves reopen following the initial portion of a reactor isolation event [LLS logic]: Plant-Specific K4.02 Minimizes containment fatigue duty cycles resulting from relief valve cycling during decay-heat-dominant period late in an isolation transient [LLS logic]: Plant-Specific K4.07 Minimum steam pressure required to keep SRV open or to open SRV A3.09 Low low set logic: Plant-Specific HEAT REMOVAL from REACTOR CORE 206000 SEE REA CTOR WA TER INVENTORY CONTROL 209002 ALL HPCS
_ _ _ _ _ _ _ _ _ _ _ _ I _ _ _ I ____________
6
I 207000 ALL ISOLATION CONDENSER 209001 SEE REACTOR WATER INVENTORY CONTROL 239001 SEE REACTOR PRESSURE CONTROL 245000 K2.03 Amplidyne: Plant-Specific K2.05 Air seal oil pumps: Plant-Specific A3.12 Automatic turbine control: Plant-Specific A4.13 Generator power factor: Plant-Specific 217000 SEE REACTOR WA TER INVENTOR Y CONTROL 202001 SEEREACTIVITY CONTROL 203000 SEE REA CTOR WA TER INVENTORY CONTROL 205000 K1.09 Auxiliary steam supply: Plant-Specific K1.11 Nitrogen: Plant-Specific K 1.12 Isolation condenser: Plant-Specific K4.01 High temperature isolation: Plant-Specific K6.06 Auxiliary steam supply: Plant-Specific K6.07 Nitrogen: Plant-Specific A2.02 Low shutdown cooling suction pressure: Plant-Specific CONTAINMENT INTEGRITY 223001 K1.13 HPCS: Plant-Specific K2.01 Atmosphere containment/atmospheric dilution compressors: Plant-Specific K2.03 Pumpback compressors: Plant-Specific K2.04 Combustible gas mixing compressors: Mark III K2.06 Hydrogen igniters: Plant-Specific K2.08 Containment cooling air handling units: Plant-Specific K2.10 Drywell chillers: Plant-Specific K4.06 Maintains proper containment/secondary containment to drywell differential pressure 7
223001 continued K5.02 Guard pipe operation: Mark III K5.04 Horizontal vent operation: Mark III K5.06 Hydrogen igniter operation: Plant-Specific K5.15 Moisture content measurement: Plant-Specific K6.02 Containment cooling: Mark III K6.07 Hydrogen igniter system: Plant-Specific K6.10 Containment vacuum relief system: Mark III Al.03 Containment pressure: Mark IIl Al.04 Containment temperature: Mark III Al.11 Reactor building to suppression chamber differential pressure; Plant-Specific A2.06 High containment pressure: Mark III A2.13 High containment temperature: Mark III A2.14 Low containment to annulus pressure: Mark III A3.07 Containment/drywell differential pressure: Mark III A4.01 Containment relief valves: Mark III A4.02 ACAD compressors: Plant-Specific A4.06 Containment pressure: Mark III A4.14 Hydrogen igniters: Plant-Specific 223002 K1.05 Isolation condenser: Plant-Specific K1.15 High pressure core spray: Plant-Specific K1.18 Reactor building drainage system: Plant-Specific Kl.21 Circulating water: Plant-Specific Kl.23 River water makeup: Plant-Specific K3.13 Isolation condenser: Plant-Specific K3.23 High pressure core spray: Plant-Specific K3.27 Circulating water K3.29 River water makeup 290002 K1.06 HPCS: Plant-Specific K1.07 Isolation condenser: Plant-Specific K1.18 Loss parts monitoring: Plant-Specific K6.12 Isolation condenser: Plant-Specific K6.16 Loss parts monitoring 8
290002 continued K6.19 HPCS: Plant-Specific [BWR-5,6]
219000 K1.02 Condensate storage tank K6.05 Condensate storage tank: Plant-Specific Al.05 Condensate storage tank level: Plant-Specific A1.10 Containment air temperature: Mark-Ill A4.10 Condensate storage tank level: Plant-Specific 226001 K 1.10 Containment [spray penetration]: Mark III K4.09 Automatic containment spray initiation: BWR-6 K6.09 Reactor building to suppression chamber vacuum breakers: Plant-Specific A4.17 Manual initiation controls: BWR-6 A4.18 Automatic system initiation reset: BWR-6 230000 K6.09 Reactor building to suppression pool vacuum breakers 290001 K1.05 Auxiliary building ventilation: Plant-Specific K1.06 Auxiliary building isolation: BWR-6 K4.04 Auxiliary building isolation: BWR-6 K5.01 Vacuum breaker operation: BWR-4 K5.02 Flow measurement: BWR-3 K6.05 Auxiliary building ventilation: Plant-Specific K6.09 AC power: BWR-6 Al.02 High area temperature: BWR-6 A2.06 Auxiliary building isolation: BWR-6 A4.03 Auxiliary building differential pressure: Plant-Specific A4.04 Auxiliary building area temperature: Plant-Specific A4.05 Fuel building differential pressure: Plant-Specific A4.06 Fuel building area temperature: Plant-Specific A4.08 Radwaste building area temperature: Plant-Specific I __ I _ ___________
t i +
9
ELECTRICAL 264000 K2.03 Turning gear [et engine]: Plant-Specific K2.04 Ignition system [jet engine]: Plant-Specific K6.04 Turning gear U[et engine]: Plant-Specific K6.05 Ignition system failure [jet engine]: Plant-Specific Al.07 Gas generator temperature: Plant-Specific A1.08 Gas generator speed: Plant-Specific 262002 A2.04 Abnormal battery operation: BWR- I INSTRUMENTATION 215005 Kl.09 Reactor recirculation system: BWR-5,6 K1.11 Rod control and information system: Plant-Specific K 1.15 Redundant reactivity control system: Plant-Specific K3.02 Reactor recirculation system: BWR-5,6 K3.04 Rod control and information system: Plant-Specific A1.06 Recirculation flow control valve position: Plant-Specific 215003 K1.03 Rod control and information system: Plant-Specific K3.03 Rod control and information system: Plant-Specific 216000 K1 .04 High pressure core spray system: Plant-Specific KI.. 1 MSIV leakage control system: Plant-Specific K 1.15 Isolation condenser: Plant-Specific K I. 18 Analog trip system: Plant-Specific K2.01 Analog trip system: Plant-Specific K3.04 High pressure core spray system: Plant-Specific K3.11 MSIV leakage control system: Plant-Specific K3.15 Isolation condenser: Plant-Specific K3.18 Analog trip system: Plant-Specific K3.28 Loose parts detection in the primary system: Plant-Specific K5.05 Vessel vibration measurement [loose parts monitor]
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10
(
212000 K1.07 Relief/safety valves [low-low-set logic]: Plant-Specific K1.11 Condenser vacuum K4.06 Select rod insertion: Plant-Specific A2.13 Low condenser vacuum: Plant-Specific A4.03 Provide manual select rod insertion: Plant-Specific 201005 ALL RCIS 214000 K1.06 RCIS: Plant-Specific K3.04 RCIS: Plant-Specific A3.04 RCIS: Plant-Specific A4.01 RCIS rod action bypass switches 201004 A3.02 Rod select bottom lamp dimmer logic: BWR4,5 201006 K1.03 Reactor water level control [feed flow]: P-Spec [Not BWR-6]
K1.08 Reactor power [turbine first stage pressure]: P-Spec [Not BWR-6]
K6.02 Reactor water level control input: P-Spec [Not BWR-6]
A2.06 Loss of reactor water level control input: P-Spec [Not BWR-6]
215004 K1.03 Rod control and information system: Plant-Specific K3.03 Rod control and information system: Plant-Specific PLANT SERVICE SYSTEMS 286000 K1 .02 Isolation condenser: Plant-Specific Ki.06 Auxiliary steam system: Plant-Specific K1.08 Intake canals: Plant-Specific K1.11 Screen wash system: Plant-Specific K5.08 Gas refrigeration: Plant-Specific K6.04 Diesel fuel transfer system: Plant-Specific K6.05 Screen wash system: Plant-Specific I_____ _ I
+ 4 11
234000 K1.06 RC&IS: Plant-Specific K1.07 Fuel transfer tube system: Mark III K1.08 Fuel pools configuration: Mark III K3.02 RC&IS: Plant-Specific K4.05 Movement of fuel via fuel transfer tube: Mark m11 K6.03 RC&IS: Plant-Specific K6.05 Upper fuel pool water inventory: Mark III K6.06 Fuel transfer tube interlocks: Mark III 300000 K2.02 Emergency air compressor K5.04 Service air refusal valve K6.04 Service air refusal valve RADIOACTIVITY RELEASE 239003 ALL MSIV LEAKAGE CONTROL 271000 K2.01 Glycol pumps K6.12 Glycol system K6.13 Plant exhaust: BWR-1 272000 K1 .07 Isolation condenser: Plant-Specific Kl.11 Reactor building overhead crane: Plant-Specific K 1.15 Filter building: Plant-Specific K1.20 Auxiliary building: Plant-Specific K1.22 Fuel building: Mark III K3.07 Reactor building overhead crane operation: Plant-Specific K3.08 Auxiliary building ventilation: Plant-Specific A3.05 Refuel floor overhead crane operation interrupt: Plant-Specific 233000 K1.10 Containment drainage system: Plant-Specific K4.08 Pool cooling during loss of coolant accident: BWR-6 Al.11 Suppression pool chemistry: BWR-6 A2.17 Fuel transfer tube drain tank high level/low level: BWR-6 12
261000 K1.05 Radwaste system: Plant-Specific K6.07 Primary containment atmosphere sampling system: Plant-Specific A1.06 Drywell and suppression chamber differential pressure: Mark I A2.15 High area radiation on refuel bridge: Plant-Specific EMERGENCY PLANT EVOLUTIONS 295024 EK1.02 Containment building integrity: Mark III EK2.02 HPCS: Plant-Specific EK2.09 Suppression pool makeup: Plant-Specific EK2.14 Containment pressure: Mark III EK2.19 Feedwater and condensate: Plant-Specific EK2.20 DC distribution: Plant-Specific EK3.03 Containment venting: Mark III EA1.02 HPCS: Plant-Specific EA1.09 Suppression pool makeup: Plant-Specific EA1.18 Containment ventilation system: Mark III EA1.21 Recirculation system [LPCI loop select logic]: Plant-Specific EA1.22 DC distribution: Plant-Specific EA2.07 Containment radiation levels: Mark III EA2.09 Containment pressure: Mark III EA2.10 Containment temperature: Mark III 295025 EK2.02 Isolation condenser: Plant-Specific EK2.03 RRCS: Plant-Specific EK3.04 Isolation condenser initiation: Plant-Specific EK3.07 RRCS initiation: Plant-Specific EK3.09 Low-low set initiation: Plant-Specific EA1.06 Isolation condenser: Plant-Specific EA1.08 RRCS: Plant-Specific 13
IT 295026 EK2.05 Containment pressure: Mark III 295027 ALL Mark III Only 295029 EK2.03 HPCS: Plant-Specific EK2.04 Suppression pool cleanup system: Plant-Specific EA1.02 HPCS: Plant-Specific 295030 EK2.05 HPCS: Plant-Specific EK2.06 Suppression pool makeup: Mark III EK3.04 HPCS operation: Plant-Specific EK3.05 Suppression pool makeup operation: Mark III EA1.03 HPCS: Plant-Specific EAI.04 Suppression pool makeup: Mark III 295031 EK2.07 High pressure core spray: Plant-Specific EK2.I0 Redundant reactivity control: Plant-Specific EA1.04 High pressure core spray: Plant-Specific EA1.09 Isolation condenser: Plant-Specific 295034 EK2.05 Fuel building ventilation: Mark Im EK3.04 Fuel building ventilation: Plant-Specific EA1.05 Fuel building ventilation: Plant-Specific 295037 EK2.02 RRCS: Plant-Specific EK2.12 Rod control and information system: Plant-Specific EA1.02 RRCS: Plant-Specific EAI.08 Rod control and information system: Plant-Specific 295038 EK2.11 MSIV leakage control: Plant-Specific EK2.12 Feedwater leakage control: BWR-6
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14
! (
ABNORMAL PLANT EVOLUTIONS 295001 AK2.05 LPCI loop select logic: Plant- Specific AK2.08 Standby liquid control: BWR-1 AA1.04 Rod control and information: BWR-5&6 AA1.08 Standby liquid control: BWR-1 295002 AK2.09 Vacuum drag (low conductivity drain): Plant-Specific AK2.10 Reactor recirculation system: Plant Specific AK3.01 Reactor SCRAM: Plant-Specific AK3.08 Recirculation system run-backs: Plant-Specific 295003 AK2.05 Isolation condenser: Plant-Specific AK3.07 Initiation of isolation condenser: Plant-Specific 295004 AK3.03 Reactor SCRAM: Plant-Specific 295005 AK2.06 Seal steam evaporator: Plant-Specific AK2.09 Feedwater-HPCI actuation: BWR-2 AK3.08 Feedwater-HPCI actuation: BWR-2 295006 AK3.05 Direct turbine generator trip: Plant-Specific 295007 AK3.01 Isolation condenser operation: Plant-Specific AK3.05 Low pressure system isolation AA 1.01 Isolation condenser: Plant-Specific 295008 AK1 .04 Containment integrity: Alis-Chalmers AK2.01 RPS: Plant-Specific AK2.07 HPCS: Plant-Specific AK3.02 Reactor SCRAM: Plant-Specific AK3.07 HPCS isolation: Plant-Specific AK3.09 HPCS injection valve closure: Plant-Specific AA1.06 HPCS: Plant-Specific
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15
I (
295009 AK3.02 Reactor feedpump runout flow control: Plant-Specific 295010 AK1.02 Submergence vent control: Mark EI AK2.03 Drywell/containment differential pressure: Mark-rn AA2.04 Drywell humidity: Plant-Specific AA2.05 Drywell air cooler drain flow: BWR-6 295011 ALL Mark Ell only 295012 AA2.03 Drywell humidity: Plant-Specific 295014 AK2.09 Rod control and information system: Plant-Specific AAl.04 Rod control and information system: Plant-Specific 295015 AK2.03 Rod control and information system: Plant-Specific AA1.04 Rod control and information system: Plant-Specific 295016 AA1.09 Isolation/emergency condenser(s): Plant-Specific 295017 AK2.11 MSIV leakage control: Plant-Specific AA1.08 MSIV leakage control: Plant-Specific 295019 AK2.13 Isolation condenser: Plant-Specific 295020 AK2.05 Isolation condenser: Plant-Specific 295023 AK2.06 Containment ventilation: Mark Im AK3.05 Initiation of SLC/shutdown cooling: Plant-Specific AA1.08 Containment building ventilation: Mark 1I 600000 AA2.01 Gas treatment system
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