ML20149F262
| ML20149F262 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/05/1997 |
| From: | Slade R NIAGARA MOHAWK POWER CORP. |
| To: | Florek D, Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20149F155 | List: |
| References | |
| NMP-91941, NUDOCS 9707220116 | |
| Download: ML20149F262 (14) | |
Text
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N aElt bl o, N#6E hmLE POINT NUCLEAR TRANNNG CENTER / RD f t. 8oX 148 / 05WEGO. NEW YORK 1 February 5,1997 i
Mr. Hubert Miller Regional Administrator United States Nuclear Regulatory Commission Region I C/5 Allendale Road King of Prussia, PA 19406 ATTENTION: Mr. Don Florek, Senior Operations Engineer
Dear Mr. Miller:
Per your request in the January 22,1997 exam letter to Nine Mile Point Unit #2, please find one (1) copy for your review, of the proposed exam outline for Mr.
Michael Smith's re-examination.
Please contact Mr. Bruce Hennigan at (315) 349-1081 or myself at (315) 349-1300 for any questions or comments on this outline. Thank you.
Sincerely, a6 a
w Mr. Richard Slade General Supervisor Operations Training RKS/crr i
cc:
License Class File D. Wolniak (memo only) l License File (memo only)
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GENERIC KNOWLEDGES AND ABILITIES (13 Required) 4 K/A Reference Number K/A Topic Importance Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements.
3.7 (CFR 41.10,45.13) 2.1.11 Knowledge ofless than one hour technical 3.0 specification action statements for systems.
(CFR 43.2,45.13) 2.1.29 Knowledge of how to conduct and verify valve 3.4 lineups.
(CFR 41.10,45.1,45.12)
Equipment Control 2.2.13 Knowledge of tagging and clearance procedures. (CFR 3.6 41.10,45.13) 2.2.22 Knowledge oflimiting conditions for operations and 3.4 safety limits.
(CFR 43.2,45.2)
Radiation Control (0)
None selected, all K/A are < 3.0 l
Emergency Procedures /
Plan 2.4.1 Knowledge of EOP entry conditions and immediate 4.3 action steps. (CFR 41.10,43.5,45.13) 2.4.6 Knowledge symptom based EOP mitigation strategies.
3.1 (CFR 41.10,43.5,45.13) 2.4.14 Knowledge of general guidelines for EOP flowchart 3.3 use. (CFR 41.10,45.13 )
GENERIC KNOWLEDGES AND ABILITIES (13 Required)
J K/A Reference Number K/A Topic Importance Emergency Procedures /
Plan (Continued) 2.4.8 Knowledge of how the event-based emergency /
3.0 abnormal operating procedures are used in conjunction with the symptom-based EOPs.
(CFR 41.10,43.5,45.13) 2.4.17 Knowledge of EOP terms and definitions.
3.1 (CFR 41.10,45.13) 2.4.20 Knowledge of operational implications of EOP 3.3 warnings, cautions, and notes. (CFR 41.10,45.13) 2.4.27 Knowledge of fire in the plant procedure.
3.0 (CFR 41.10,43.5,45.13) 2.4.32 Knowledge of operator response to loss of all 3.3 annunciators. (CFR 41.10,43.5,45.13) l
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PLANT SYSTEMS GROUP I (28 Required)
System K/A K/A Topic Importance 201001 K4.06 Isolation of the SCRAM discharge volumes during 3.8 CRDH SCRAM conditions 201001 K4.04 Scramming control rods with inoperative SCRAM 3.6 CRDH solenoid valves (back-up SCRAM valves) 201001 K4.08 Controlling control rod drive header pressure 3.1 CRDH 201002 K! 03 Control rod block interlocks / power operation refueling 3.4 RMCS 201002 K4.05
" Notch override" rod withdrawal 3.3 RMCS
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202002 Kl.03 Reactor core flow 3.7 Recirc Flow Control 202002 K4.08 Automatic flow control valve positioning: BWR-5,6 3.3 Recire i
Flow Control 203000 K5.02 Core cooling methods 3.5 RHR/LPCI
- Injection Mode 209001 K4.08 Automatic system initiation 3.8 LPCS 209002 K4.02 Prevents over filling reactor vessel 3.4 HPCS 211000 K4.08 System initiation upon operation of SBLC control 4.2 SLC switch 212000 K3.07 Reactor power (thermal heat flux) 3.8 RPS 215003 K1.02 Reactor manual control 3.6 IRM
PLANT SYSTEMS GROUP I (28 Required)
System K/A K/A Topic Importance 215004 K1.01 Reactor protection system 3.6 SRM 215005 K1.04 LPRM channels 3.6 APRM 215005 K3.05 Reactor power indication 3.8 APRM i
216000 K5.01 Vessel level measurement 3.1 NBI 216000 K3.13 Feedwater system 3.4 NBI 217000 K4.02 Prevent over filling reactor vessel 3.3 RCIC 218000 KS.01 ADS logic operation 3.8 ADS 223001 K4.01 Allows for absorption of the energy released during a 3.7 Primary LOCA Containment 223002 Kl.08 Shutdown cooling system /RHR 3.4 PCIS/NSSSS 239002 K4.05 Allows for SRV operation from more than one 3.6 SRV location: Plant-Specific 241000 K3.06 Bypass valves 4.1 EHC 259001 Kl.16 Recirculation 3.1 Feedwater 259002 K6.05 Reactor water level input 3.5 RWLC 261000 Kl.01 Reactor building ventilation system 4.3 '
SBGT 264000 K4.02 Emergency generator trips (emergency /LOCA) 4.0 EDG
PLANT SYSTEMS GROUP II (19 Required)
System K/A K/A Topic Importance 201003 K4.04 The use of either accumulator or reactor water to 3.6 CRDM SCRAM the control rod 201003 K4.05 Rod position indication 3.2 CRDM 202001 K1.06 Jet pumps 3.6 Recirc 204000 K4.04 System isolation upon-receipt of isolation signals 3.0 RWCU 205000 K4.03 Low reactor water level:
3.8 SDC 215002 K1.02 LPRM: BWR-3,4,5 3.2 RBM 219000 K1.01 Suppression pool 3.6 SP Cooling 226001 Kl.12 Suppression pool (spray penetration): Plant-Specific 3.0 Containment Spray 290001 K1.01 Reactor building ventiiation: Plant-Specific 3.3 Secondary Containment 290003 K1.01 Radiation monitor 3.4 Control Room HVAC 230000 K6.03 Emergency generator 3.5 SP Spray 239001 K4.01 Automatic isolation of steam lines 3.8 Main Steam 256000 K4.01 Condensate and/or booster pump auto start Plant-3.4 Reactor Specific Condensate
PLANT SYSTEMS GROUP II (19 Required)
System K/A K/A Topic Importance 226001 K1.01 Emergency generators (diesel / jet) 3.8 A.C.
Electrical Distribution 262002 K4.01 Transfer from preferred power to alternate power 3.1 UPS supplies 263000 K2.01 Major D.C. loads 3.1 D.C.
271000 K3.01 Condenser vacuum 3.5 Offgas 272000 K4.03 Fail safe tripping of process radiation monitoring logic 3.6 Rad during conditions ofinstrument failure Monitor 286000 K4.02 Automatic system initiation 3.3 Fire Protection System
PLANT SYSTEMS GROUP III (4 Required)
System K/A K/A Topic Importance 268000 K5.02 Radiation hazards and ALARA concept 3.1 1
Radwaste 290002 K5.07 Safety limits 3.9 Reactor Vessel Internals 290002 K5.01 Thermal limits 3.5 Reactor Vessel Internals 234000 Kl.04 Reactor manual control system: Plant-Specific 3.3 Fuel Handling Equipment J
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A EMERGENCY AND ABNORMAL PLANT EVOLUTIONS I
l-GROUP I (13 Required)
System K/A K/A Topic Importance 1
295005 AK3.07 Bypass valve operation.
3.8 Main Turbine Generator Trip 295006 AK2.02 Reactor water level control system 3.8 SCRAM 295007 High AK2.01 Reactor / turbine pressure regulating system 3.5 Reactor Pressure 295009 Low AKl.05 Natural circulation 3.3 Reactor Water Level 295010 High AK1.01 Downcomer submergence: Mark-I&II 3.0 Drywell Pressure 295014 AKl.02 Reactivity anomaly 3.3 Inadvertent Reactivity Addition 295014 AK2.06 Moderator temperature 3.4 Inadvertent Reactivity Addition 295015 AK2.01 CRD hydraulics 3.8 Incomplete SCRAM 295024 High EKl.01 Drywellintegrity: Plant-Specific 4.1 Drywell Pressure 4
295024 High EA2.04 Suppression chamber pressure: Plant-Specific 3.9 Drywell Pressure
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS GROUP I (13 Required)
System K/A K/A Topic Importance l
295025 EK2.01 RPS 4.1 l
High Reactor l
Pressure 295031 Reactor EK3.05 Emergency depressurization 4.2 Low Water Level 295037 EK2.09 Reactor water level.
4.0 ATWAS 1
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5MERGENCY AND ABNORMAL PLANT EVOLUTIONS GROUP II (19 Required) j l
System K/A K/A Topic Importance 295001 AKl.02 Power / flow distribution 3.3 Partial or Comp!cte Loss of Forced i
Core Flow Circulation 295002 AK2.04 Reactor / turbine pressure regulating system 3.2 Loss of Main Condenser Vacuum 295003 AKl.06 Station blackout: Plant-Specific 3.8 Partial or Complete Loss of i
A.C. Power 295008 AK2.03 Reactor water level control 3.6 High Reactor Water Level 295012 AKl.01 Pressure / temperature relationship 3.3 High Drywell Temperature 295013 AK3.02 Limiting heat additions 3.6 High l
Suppression Pool Temperature 295016 AK2.01 Remote shutdown panel: Plant-Specific 4.4 Control Room Abandonme nt
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS GROUP II (19 Required)
System K/A K/A Topic Importance 295017 AK2.04 Plant ventilation systems 3.1 High Off-Site Release Rate 295018 AK2.01 System loads 3.3 Partial or Complete Loss of Component Cooling Water 295019 AK2.03 Reactor feedwater 3.2 1-artial or l
Complete Loss of Instrument Air 295019 AK2.14 Plant air systems 3.2 Partial or Complete Loss of Instrument Air 295022 AK2.07 Reactor pressure (SCRAM assist): Plant-Specific 3.4 Loss of CRD Pumps 295026 EK3.01 Emergency / normal depressurization 3.8 Suppression Pool High Water Temperature 295028 EK2.03 Reactor water levelindication 3.6 High Drywell Temperature
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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS GROUP II (19 Required)
System K/A K/A Topic Importance 295029 EK2.07 Drywell/contamment water level 3.1 l
High l
Suppression Pool Water Level 295030 EK2.08 SRV discharge submergence 3.5 low Suppression Pool Water Level 295033 EK2.04 Standby gas treatment system /FRVS 3.9 High Secondary Containmen t Area Radiation Levels 295034 EK2.01 Process radiation monitoring system 3.9 Secondary Containmen t Ventilation High Radiation 295038 EK2.04 Stack-gas monitoring system: Plant-Specific 3.9 High Off-Site Release Rate i
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BWR RO EMERGENCY AND ABNORMAL PLANT
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EVOLUTIONS GROUP III (4 Required)
System K/A K/A Topic Importance 295021 Loss AKl.02 Thermal stratification 3.3 of Shutdown Cooling l
295032 High EK3.01 Emergency /nonnal depressurization 3.5 Secondary j
Containment Area Temperature 295023 AKl.01 Radiation exposure hazards 3.6 Refueling Accidents 295021 Loss AK3.05 Establishing alternate heat removal flow paths 3.6 of Shutdown Cooling i
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