ML032690655
| ML032690655 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/13/2003 |
| From: | Reid J Public Service Enterprise Group |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-272/03-301, 50-311/03-301 | |
| Download: ML032690655 (16) | |
Text
PSEG Nuclear LLC Nuclear Training Center 244 Chestnut Street, Salem, N.J.08079 fax: 856.339.3997 NTD-03-3003
@ PSEG Nuclear LLC January I O , 2003 Mr. Todd Fish U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415
Dear Mr. Fish,
Enclosed please find the following 2 documents:
- 1. Permanent WA suppression list for Salem Generating Station.
- 2. Salem Initial License Written Exam Outline for Jeffrey Scanish (SROU retake).
The WA suppression list will become permanent upon your review and approval. The suppression list was derived from guidance provided on the NRC web site titled WA Supression.
The outline for Jeff Scanishs SROU written exam retake was requested to be sent to you by Alan Blarney, during a post exam review conversation of the Salem GInitial License Operator NRC exam conducted November 4-15, 2002. This outline excludes those WAs noted on the Permanent Suppression List included in this package.
Mr. Scanishs docket # is 55-61969.
I will be the point of contact for this exam. I can be reached at 856-339-1554. Please contact me with any questions or concerns.
Sincerely, Gerald S. Gauding W GG:blm Attachments C NBS Records (N64)
ES-401 PWR SRO Examination Outline Printed: 01/09/2003 Facility: Salem Form ES-40 1-3 Exam Date: 05/21/2003 Exam Level: SRO WA Category Points 2 2 1 2 2 2 1 2 19 1 2 2 1 2 1 2 2 17 0 1 0 0 I 0 0 1 4 3 5 3 3 5 3 3 5 40 Note: 1 . Ensure that at least two topics from every WA category are sampled within each teir (i.e., the "Tier Totals" in each K/A category shall not be less than two).
- 2. Actual point totals must match those specified in the table.
- 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 RO license level, and the point totals for each system and category. K/As below 2.5 should bejustified on the basis of plant-specific priorites. Enter the tier totals for each category in the table above.
1
PWR SRO Examination Outline Printed: 0 I I0912003 Facility: Salem ES - 401 Emei Lency and Abnormal Plant Evolutions - Tier 1 / Groun 1 Form ES-401-3 E/APE ## E/APE Name I Safety Function KA Topic imp. Points 00 1 Continuous Rod Withdrawal I 1 AK3 .O 1 - Manually driving rods into position that 3.6 1 existed before start of casualty 005 Inoperable/Stuck Control Rod / 1 2.1.33 - Ability to recognize indications for system 4.0 1 operating parameters which are entry-level conditions for technical specifications.
01 1 Large Break LOCA 1 3 2.2.22 - Knowledge of limiting conditions for 4.1 1 operations and safety limits.
015 Reactor Coolant Pump (RCP) Malfunctions / 4 AK3.02 - CCW lineup and flow paths to RCP oil 3.1 1 coolers 017 Reactor Coolant Pump (RCP) Malfunctions (Loss of AK2.07 - RCP seals 2.9 1 RC Flow) / 4 024 Emergency Boration / 1 AA2.04 - Availability of BWST 4.2 1 026 Loss of Component Cooling Water (CCW) / 8 2.4.3 1 - Knowledge of annunciators alarms and 3.4 1 indications, and use of the response instructions.
029 040 Anticipated Transient Without Scram (ATWS) I 1 Steam Line Rupture / 4 ZlZ EA1.03 - Charging pump suction valves from VCT operating switch AK 1.05 - Reactivity effects of cooldown 3.2 4.4 1
1 1
PWR SRO Examination Outline Printed: 0 1 /09/2003 Facility: Salem ES - 401 Eme ind Abnormal Plant Evolutions - Tier 1 /Group 1 Form ES-401-3 1
E/APE #
057 E/APE Name / Safety Function Loss of Condenser Vacuum 1 4 Loss of Offsite and Onsite Power (Station Blackout) 6 Loss of Vital AC Electrical Instrument Bus / 6 K3 X
X KA Topic AK3 .O1 - Loss of steam dump capability upon loss of condenser vacuum EK3.02 - Actions contained in EOP for loss of offsite and onsite power 2.1.32 - Ability to explain and apply all system limits and precautions.
Imp.
3.1" 4.6 3.8
'oints 1
AK2.01 Radioactive-liquid monitors
- 2.8 1 059 Accidental Liquid Radwaste Release 1 9 062 Loss of Nuclear Service Water / 4 -
AA1.07 Flow rates to the components and systems 3.0 1 that are serviced by the SWS; interactions among the somponents 067 Plant Fire on Site I 9 AA2.09 - That a failed fire alarm detector exists - 2.7 1
- 1 068 Control Room Evacuation I 8 AA1.08 - Local boric acid flow 4.2*
Inadequate Core Cooling / 4 EK2.09 - Controllers and positioners 2.6*
- 1 074
- 1 076 High Reactor Coolant Activity / 9 AK1.06 - Chemical shock and crud burst 2.6 2
PWR SRO Examination Outline Printed: 01/09/2003 Facility: Salem ES - 401 Eme ind Abt rmal Plant Evolutions - Tier 1 /Group 1 Form ES-401-3 EIAPE # EIAPE Name I Safety Function <2 K3 KA Topic mP. 'oints E02 SI Termination / 3 EKl.2 - Normal, abnormal and emergency operating 3.9 1 procedures associated with SI Termination E04 LOCA Outside Containment / 3 EA2.1 - Facility conditions and selection of appropriate 4.3 1 procedures during abnormal and emergency operations E06 Degraded Core Cooling / 4 EA2.1 - Facility conditions and selection of appropriate 4.2 1 procedures during abnormal and emergency operations E07 Saturated Core Cooling / 4 EA1.3 - Desired operating results during abnormal and 3.9 1 emergency situations E09 Natural Circulation Operations / 4 X EK2.2 - Facility's heat removal systems, including 3.9 1 primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility E14 High Containment Pressure / 5 EK1.2 - Normal, abnormal and emergency operating 3.7 1 procedures associated with High Containment Pressure WA Category Totals: 4 4 4 4 4 Group Point Total: 24 3
PWR SRO Examination Outline Printed: 0 1/09/2003 Facility: Salem ES - 401 Emei ind Abnormal Plant Evolutions - Tier 1 / Grour, 2 - Form ES-401-3 EIAPE # E/APE Name / Safety Function K3 A1 KA Topic Imp. 'oints 008 Pressurizer (PZR) Vapor Space Accident (Relief AK2.02 - Sensors and detectors 2.7
- 1 Valve Stuck Open) / 3 009 Small Break LOCA / 3 EK2.03 - S/GS 3.3*
- 1 022 Loss of Reactor Coolant Makeup / 2 2.1.33 - Ability to recognize indications for system 4.0 operating parameters which are entry-level conditions for technical specifications.
025 Loss of Residual Heat Removal System (RHRS) / 4 AA2.04 - Location and isolability of leaks 3.6 037 Steam Generator (SIG) Tube Leak 1 3 2.1.32 - Ability to explain and apply all system limits 3.8 and precautions.
037 Steam Generator (S/G) Tube Leak / 3 X AK3.10 - Automatic actions associated with high 3.7*
radioactivity in S/G sample lines 038 Steam Generator Tube Rupture (SGTR) / 3 X EK3.01 - Equalizing pressure on primary and secondary 4.3 sides of ruptured SIG 054 Loss of Main Feedwater (MFW) 1 4 X AK3.03 - Manual control of AFW flow control valves 4.1 058 Loss of DC Power I 6 AA2.03 - DC loads lost; impact on to operate and
- 3.9 monitor plant systems 1
PWR SRO Examination Outline Printed: 0 1/09/2003 Facility: Salem ES 401 Emergencv and Abnormal Plant Evolutions - Tier 1 / G r o w 2 Form ES-401-3 I
1 Q KA Topic 'oints AK1.02 - Biological effects on humans of the various 1 types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels AK1 .O1 - Detector limitations 2.9?
AA 1.02 - Components served by instrument air to 2.8 minimize drain on system EA 1.3 - Desired operating results during abnormal and 4.1 emergency situations EA 1.1 - Components, and functions of control and 4.0 safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK2.1 - Components, and functions of control and 3.9 safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK1.2 - Normal, abnormal and emergency operating 3.2
- procedures associated with High Containment Radiation WA Category Totals: 3 3 3 3 2 2 Group Point Total: 16 2
PWR SRO Examination Outline Printed: 01/09/2003 Facility: Salem ES - 401 Emereencv and Abnormal Plant Evolutions - Tier 1 / Group 3
- u Form ES-401-3 E/APE # E/APE Name / Safety Function K1 K2 KA Topic Points 028 Pressurizer (PZR) Level Control Malfunction / 2 X AKl.01 - PZR reference leak abnormalities 3.1" 036 Fuel Handling Incidents / 8 AA2.03 - Magnitude of potential radioactive release 4.2*
056 Loss of Offsite Power I 6 2.4.6 - Knowledge symptom based EOP mitigation 4.0 strategies.
~~ ~
WA Category Totals: 1 0 1 1 Group Point Total:
1
PWR SRO Examination Outline Printed: 0 1/09/2003 Facility: Salem ES - 401 ant Syst h e r 2 I ;roup 1 Form 5-401-3 Sys/Ev # K3 K4 41 A2 KA Topic Imp. Points 00 1 K2.05 - M/G sets 3.5 1 003 A3.01 - Seal injection flow 3.2 1 (RCPS) / 4 004 Chemical and Volume Control System A3.10 - PZR level and pressure 3.9 1 (CVCS) / 1 004 Chemical and Volume Control System A4.15 - Boron concentration 3.7 1 (CVCS) / 1 013 Engineered Safety Features Actuation X A 1.08 - Containment sump level 3.8 1 System (ESFAS) / 2 I
0I4 Rod Position Indication System K5.02 - RF'IS independent of demand position 3.3 (RP1S)l 1 015 Nuclear Instrumentation System / 7 2.4.6 - Knowledge symptom based EOP
- 4.0 mitigation strategies.
015 Nuclear Instrumentation System I 7 K6.04 - Bistables and logic circuits 3.2 026 056 I
Containment Spray System (CSS) I 5 Condensate System / 4 I
X X
K3.01 - CCS A2.04 - Loss of condensate pumps 4.1 2.8*
1 1
1
PWR SRO Examination Outline Printed: 0 1 /10/2003 Facility: Salem CS - 401 IS - Tier 2 / #roup 1
~
,s-401-3 System / Evolution Name L3 A4 G KA Topic [mp. Points iys/Ev ## -
059 Main Feedwater (MFW) System / 4 X 2.4.4 - Ability to recognize abnormal 4.3 1 indications for system operating parameters which are entry-level conditions for emergency md abnormal operating procedures.
06 1 Auxiliary I Emergency Feedwater K2.02 - AFW electric driven pumps 3.7 (AFW) System / 4 06 1 Auxiliary / Emergency Feedwater K5.02 - Decay heat sources and magnitude 3.6 (AFW) System 1 4 063 D.C. Electrical Distribution System / 6 K4.0 1 - Manual/automatic transfers of control 3.0*
K1.07 - Sources of liquid wastes for LRS
- 2.9 068 Liquid Radwaste System (LRS) / 9 A2.02 - Lack of tank recirculation prior to
-2.8*
068 Liquid Radwaste System (LRS) / 9 release 07 1 Waste Gas Disposal System (WGDS) K4.05 - Point of release 3 .O
/9 A 1.06 - Ventilation system
- 2.8 071 Waste Gas Disposal System (WGDS)
/9
- 3.5 1 072 Area Radiation Monitoring (ARM) K3.02 - Fuel handling operations Svstem 17 WA Category Totals: 2 2 2 1 2 Group Point Total: 19 2
PWR SRO Examination Outline Printed: 0 1/09/2003 Facility: Salem 3s - 401 ant ?stems - Tie ! I Group 2 Form 5-401-3 Sys/Ev # System / Evolution Name Kl 41 A2 93 A4 KA Topic mP. Points 002 Reactor Coolant System (RCS) / 2 K3.03 - Containment 4.6 1 002 Reactor Coolant System (RCS) / 2 K5.13 - Causes of circulation
-3.9
- 1 K5.02 - Relationship between accumulator
-2.9 1 006 Emergency Core Cooling System (ECCS) 1 2 volume and pressure 010 2.2.25 - Knowledge of bases in technical 3.7 (PZR PCS) 1 3 specifications for limiting conditions for operations and safety limits.
01 1 Pressurizer Level Control System K6.03 - Relationship between PZR level and
- 3.3 (PZR LCS) / 2 PZR heater control circuit A2.08 Loss of level compensation
- 2.8 011 Pressurizer Level Control System X (PZR LCS) / 2 K2.01 - RPS channels, components, and
- 3.7 1 0 12 Reactor Protection System 1 7 interconnections K1.07 - ECCS
-3.7* 1 016 Non-Nuclear Instrumentation System X
("IS) /7 02 8 Hydrogen Recombiner and Purge X A4.03 - Location and operation of hydrogen
- 3.3
- 1 Control System (HRPS) / 5 sampling and analysis of containment atmosphere, including alarms and indications
- 3.6 1 029 Containment Purge System (CPS) / 8 X A4.04 - Containment evacuation signal 1
PWR SRO Examination Outline Printed: 01/09/2003 Facility: Salem ES - 401 ystems .
SysrEv # System / Evolution Name K1 K2 42 A3 KA Topic Imp. Points 033 Spent Fuel Pool Cooling System A1.01 - Spent fuel pool water level 3.3 1 (SFPCS) / 8 034 Fuel Handling Equipment System X (FHES) / 8 035 Steam Generator System (S/GS) / 4 K3.02 - ECCS 4.3 1 064 Emergency Diesel Generator (ED/G) 2.2.22 - Knowledge of limiting conditions for 4.1 1 System / 6 operations and safety limits.
064 Emergency Diesel Generator (ED/G) X A3.04 - Number of starts available with an air 3.5 1 System I 6 compressor 086 Fire Protection System (FPS) / 8 K6.04 - Fire, smoke, and heat detectors 2.9 1 103 Containment System / 5 K4.04 - Personnel access hatch and emergency 3.2 1 WA Category Totals: 2 1 2 2 Group Point Total: 17 2
PWR SRO Examination Outline Printed: 01/09/2003 Form 3-401-3 s ~ ~ #/ E ~ / Evolution Name System K 1 K2 K4 K5 K6 A1 A2 A3 Imp. Points 005 Residual Heat Removal System K3.06 - CSS 3.2*
(RHRS) 1 4 008 Component Cooling Water System 4.1 I (ccws)18 operations and safety limits.
Steam Dump System (SDS) and Turbine Bypass Control 1 4 I Svstem I 4 X
X 3 K5.07 - Reactivity feedback effects A2.17 - Malfunction of electrohydraulic contro 3.6 2.9*
1 I
WA Category Totals: 0 0 0 1 1 Group Point Total: 4 1
Generic Knowledge and Abilities Outline (Tier 3)
Printed: 0 1/09/2003 PWR SRO Examination Outline Form ES-401-5 Facility: Salem Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.10 Knowledge of conditions and limitations in the facility license.
2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports.
2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status.
2.1.20 Ability to execute procedure steps.
I Category Total: 4 Equipment Control 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
2.2.6 Knowledge of the process for making changes in procedures as described in the safety analysis report.
2.2.21 Knowledge of pre- and post-maintenance operability requirements.
2.2.25 Knowledge of bases in technical specificationsfor limiting conditions for operations and 3.7 safety limits.
Category Total: 4 Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.
2.3.2 Knowledge of facility ALARA program.
2.3.3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control room (e.g., waste disposal and handling systems).
2.3.8 Knowledge of the process for performing a planned gaseous radioactive release. 3.2 Category Total: 4 1
Generic Knowledge and Abilities Outline (Tier 3)
Printed: 0 1 /09/2003 PWR SRO Examination Outline Form ES-401-5 Facility: Salem Generic Category KA KA Topic Imp. Points 3 .I
- 1 Emergency Procedures/Plan 2.4.8 Knowledge of how the event-based emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs.
2.4.12 Knowledge of general operating crew responsibilities during emergency operations. 3.9 1 2.4.25 Knowledge of fire protection procedures. 3.4 1 2.4.21 Knowledge of fire in the plant procedure. 3.5 1 2.4.28 Knowledge of procedures relating to emergency response to sabotage. 3.3 1 Category Total: 5 Generic Total: ' 17 2
ES-401 Record of Rejected K/As Form ES-401-10
~ TieTGroup Randomly Selected KIA Reason for Rejection 1/ I 003 AK 1.20 Several KIAs related to control rods and rod control. Increase breadth of examination coverage by manually selecting 040 AK 1.Ob (unselected topic, same KIA category).
I/ I 015 G2.4 .49 Several KIAs related to RCPs and Loss of KC t-Iow. Also, no immediate actions for this topic Increase breadth of examination coverage by manually selecting 026 G 2.4.31 (unselected topic, same KIA category).
II1 01 / AK 1.04 Several KIAs related to KCPs and Loss of KC: FIow. Increase breadth of examination coverage by manually selecting 0 / 6 AK 1.06 (unselected topic, same KIA category).
1/1 024 AK 3.01 Several KIAs related to Emergency Boration. Also this KIA relates to cortrol rods and rod control.
Increase breadth of examination coverage by manually selecting 026 G 2 .4.31 (unselected topic, same KIA category).
112 008 AA 1.01 Several KIAs related to PLK vapor space accident. Increase breadth of examination coverage by manually selecting t o 3 t A 1.3 (unselected topic, same KIA category).
112 038 t A 1.33 Several KIAs related to SG I K and I ube leak. Also this KIA relates to Natrral Circulation.
~ ____
~
Increase breadth of examination coverage by manually selecting t o 5 t A 1.I(unselected topic,
~~
same KIA category).
113 056 AKI .04 Several KIAs related to Loss of Offsite Power. Increase breadth of examination coverage by manually selecting 028 AK 1.01 (unselected topic, same KIA category).
211 001 K 3.02 Several KIA s related to control rods and rod control. Increase breadth of examination coverage by manually selecting 0/2 K 3.02 (unselected topic, same K/A category).
211 014 K 3.02 Several KIA s related to KPlS. Increase breadth of examination coverage by manually selecting 026 K 3.01 (unselected topic, same KIA category).
211 059 G 2 .4 .30 KIA selected has no relevance to system. Manually selected G 2 .4.4 (same KIA category for system) 213 005 K 5.03 Several KIA s related to KHK. Increase breadth of examination coverage by manually selecting 041 K 5.0/ (unselected topic, same KIA category).
NUREG 1021, Revision 8. Supplement 1