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 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 S u pression.
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 G Initial License Operator NRC exam conducted November 4-1 5, 2002. This outline excludes those WAs noted on the Permanent Suppression List included in this package.
Mr. Scanishs docket # is 55-61 969.
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, W
Gerald S. Gauding GG:blm Attachments C
NBS Records (N64)
ES-401 PWR SRO Examination Outline Printed: 01/09/2003 Form ES-40 1-3 Facility:
Salem 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
- 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.
they relate to plant-specific priorities.
1
PWR SRO Examination Outline imp.
3.6 4.0 4.1 3.1 2.9 4.2 3.4 3.2
4.4 Facility
Salem Points 1
1 1
1 1
1 1
1 1
ES - 401 E/APE ##
00 1 005 01 1 015 017 024 026 029 040 Emei E/APE Name I Safety Function Continuous Rod Withdrawal I 1 Inoperable/Stuck Control Rod / 1 Large Break LOCA 1 3 Reactor Coolant Pump (RCP) Malfunctions / 4 Reactor Coolant Pump (RCP) Malfunctions (Loss of RC Flow) / 4 Emergency Boration / 1 Loss of Component Cooling Water (CCW) / 8 Anticipated Transient Without Scram (ATWS) I 1 Steam Line Rupture / 4 Lency and Abnormal ZlZ Plant Evolutions - Tier 1 / Groun 1 Printed:
0 I I0912003 Form ES-401-3 KA Topic AK3.O 1 - Manually driving rods into position that existed before start of casualty 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
2.2.22 - Knowledge of limiting conditions for operations and safety limits.
AK3.02 - CCW lineup and flow paths to RCP oil coolers AK2.07 - RCP seals AA2.04 - Availability of BWST 2.4.3 1 - Knowledge of annunciators alarms and indications, and use of the response instructions.
EA1.03 - Charging pump suction valves from VCT operating switch AK 1.05 - Reactivity effects of cooldown 1
Facility:
Salem Imp.
3.1" -
4.6 3.8 2.8 3.0 2.7 4.2*
2.6*
2.6 ES - 401 E/APE # 1 057 059 062 067 068 074 076 Eme E/APE Name / Safety Function Loss of Condenser Vacuum 14 Loss of Offsite and Onsite Power (Station Blackout) 6 Loss of Vital AC Electrical Instrument Bus / 6 Accidental Liquid Radwaste Release 1 9 Loss of Nuclear Service Water / 4 Plant Fire on Site I 9 Control Room Evacuation I 8 Inadequate Core Cooling / 4 High Reactor Coolant Activity / 9 PWR SRO Examination Outline ind Abnormal Plant Evolutions - Tier 1 /Group 1 Printed:
0 1 /09/2003 Form ES-401-3 K3 X -
X KA Topic AK3.O 1 - 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.
AK2.01 - Radioactive-liquid monitors AA1.07 - Flow rates to the components and systems that are serviced by the SWS; interactions among the somponents AA2.09 - That a failed fire alarm detector exists -
AA1.08 - Local boric acid flow EK2.09 - Controllers and positioners AK1.06 - Chemical shock and crud burst
'oints 1
1 1
1 1
1 1
2
PWR SRO Examination Outline ind
<2 X
Printed:
01/09/2003 Abt K3 Facility:
Salem ES - 401 EIAPE #
E02 E04 E06 E07 E09 E14 Eme EIAPE Name I Safety Function SI Termination / 3 LOCA Outside Containment / 3 Degraded Core Cooling / 4 Saturated Core Cooling / 4 Natural Circulation Operations / 4 High Containment Pressure / 5 WA Category Totals:
4 rmal Plant Evolutions - Tier 1 /Group 1 Form ES-401-3 4
4 4
KA Topic EKl.2 - Normal, abnormal and emergency operating procedures associated with SI Termination EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations EA1.3 - Desired operating results during abnormal and emergency situations EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility EK1.2 - Normal, abnormal and emergency operating procedures associated with High Containment Pressure mP.
3.9 4.3 4.2 3.9 3.9 3.7 -
4 Group Point Total:
'oints 1
1 1
1 1
1 -
24 3
Facility:
Salem K3 X
X X
ES - 401 A1 EIAPE #
008 009 022 025 037 037 038 054 058 Emei E/APE Name / Safety Function Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open) / 3 Small Break LOCA / 3 Loss of Reactor Coolant Makeup / 2 Loss of Residual Heat Removal System (RHRS) / 4 Steam Generator (SIG) Tube Leak 13 Steam Generator (S/G) Tube Leak / 3 Steam Generator Tube Rupture (SGTR) / 3 Loss of Main Feedwater (MFW) 14 Loss of DC Power I 6 PWR SRO Examination Outline ind Abnormal Plant Evolutions - Tier 1 / Grour, 2 Printed:
0 1 /09/2003 Form ES-401-3 KA Topic AK2.02 - Sensors and detectors EK2.03 - S/GS 2.1.33 - Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
AA2.04 - Location and isolability of leaks 2.1.32 - Ability to explain and apply all system limits and precautions.
AK3.10 - Automatic actions associated with high radioactivity in S/G sample lines EK3.01 - Equalizing pressure on primary and secondary sides of ruptured SIG AK3.03 - Manual control of AFW flow control valves AA2.03 - DC loads lost; impact on to operate and monitor plant systems Imp.
2.7 3.3*
4.0 3.6 3.8 3.7*
4.3 4.1 -
3.9
'oints 1 -
1 1
Facility:
Salem ES - 401 AK1.O 1 - Detector limitations PWR SRO Examination Outline Emergencv and Abnormal Plant Evolutions - Tier 1 / G r o w 2 2.9?
Printed:
0 1/09/2003 Form ES-401-3 AA 1.02 - Components served by instrument air to minimize drain on system EA 1.3 - Desired operating results during abnormal and emergency situations EA 1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK1.2 - Normal, abnormal and emergency operating procedures associated with High Containment Radiation WA Category Totals:
3 3
3 3
2.8 4.1 4.0 3.9 3.2 2
I 1
KA Topic AK1.02 - Biological effects on humans of the various 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 Q
2 Group Point Total:
'oints 1
16 2
Facility:
Salem ES - 401 E/APE #
E/APE Name / Safety Function 028 Pressurizer (PZR) Level Control Malfunction / 2 036 Fuel Handling Incidents / 8 056 Loss of Offsite Power I 6 PWR SRO Examination Outline Emereencv and Abnormal Plant Evolutions - Tier 1 / Group 3 u
K1 K2 X
AKl.01 - PZR reference leak abnormalities
~~
~
WA Category Totals:
1 0
3.1" 1
AA2.03 - Magnitude of potential radioactive release Printed:
01/09/2003 Form ES-401-3 4.2*
KA Topic 2.4.6 - Knowledge symptom based EOP mitigation strategies.
4.0 1
Group Point Total:
Points 1
PWR SRO Examination Outline Printed:
0 1 /09/2003 ant 41 X
Facility:
ES - 401 Syst A2 X
Salem K3 X
Sys/Ev #
00 1 K4 003 004 004 013 0 I4 015 015 026 056 (RCPS) / 4 Chemical and Volume Control System (CVCS) / 1 (CVCS) / 1 Chemical and Volume Control System Engineered Safety Features Actuation System (ESFAS) / 2 I
Rod Position Indication System (RP1S)l 1 Nuclear Instrumentation System / 7 Nuclear Instrumentation System I 7 Containment Spray System (CSS) I 5 I
I Condensate System / 4 her 2 I ;roup 1 KA Topic K2.05 - M/G sets A3.01 - Seal injection flow A3.10 - PZR level and pressure A4.15 - Boron concentration A 1.08 - Containment sump level K5.02 - RF'IS independent of demand position 2.4.6 - Knowledge symptom based EOP mitigation strategies.
K6.04 - Bistables and logic circuits K3.01 - CCS A2.04 - Loss of condensate pumps Form Imp.
3.5 3.2 3.9 3.7 3.8 3.3 -
4.0 3.2 4.1 2.8*
5-401-3 Points 1
1 1
1 1
1 1 -
1
PWR SRO Examination Outline IS -
L3 Printed:
0 1 /10/2003 Tier 2 /
A4 G X
Facility:
1 CS - 401 iys/Ev ##
059 06 1 06 1 063 068 068 07 1 07 1 072 Salem System / Evolution Name Main Feedwater (MFW) System / 4 Auxiliary I Emergency Feedwater (AFW) System / 4 Auxiliary / Emergency Feedwater (AFW) System 14 D.C. Electrical Distribution System / 6 Liquid Radwaste System (LRS) / 9 Liquid Radwaste System (LRS) / 9 Waste Gas Disposal System (WGDS)
/ 9 Waste Gas Disposal System (WGDS)
/ 9 Area Radiation Monitoring (ARM)
Svstem 17 WA Category Totals:
2 2
- roup 1
~
KA Topic 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency md abnormal operating procedures.
K2.02 - AFW electric driven pumps K5.02 - Decay heat sources and magnitude K4.0 1 - Manual/automatic transfers of control K1.07 - Sources of liquid wastes for LRS A2.02 - Lack of tank recirculation prior to release K4.05 - Point of release A 1.06 - Ventilation system K3.02 - Fuel handling operations
[mp.
4.3 -
3.7 -
3.6 3.0*
2.9 -
2.8*
3.O -
2.8 3.5
,s-401-3 Points 1
2 1
2 Group Point Total: 19 2
PWR SRO Examination Outline ant ?stems Printed:
0 1/09/2003
- Tie Facility:
93 3s - 401 Sys/Ev #
002 002 A4 X
X 006 System / Evolution Name Reactor Coolant System (RCS) / 2 Reactor Coolant System (RCS) / 2 Emergency Core Cooling System (ECCS) 12 010 K l 01 1 01 1 41 0 12 A2 X
016 Non-Nuclear Instrumentation System
("IS)
/ 7 02 8 X
029 Salem (PZR PCS) 13 Pressurizer Level Control System (PZR LCS) / 2 Pressurizer Level Control System (PZR LCS) / 2 Reactor Protection System 17 Hydrogen Recombiner and Purge Control System (HRPS) / 5 Containment Purge System (CPS) / 8
! I Group 2 KA Topic K3.03 - Containment K5.13 - Causes of circulation K5.02 - Relationship between accumulator volume and pressure 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
K6.03 - Relationship between PZR level and PZR heater control circuit A2.08 - Loss of level compensation K2.01 - RPS channels, components, and interconnections K1.07 - ECCS A4.03 - Location and operation of hydrogen sampling and analysis of containment atmosphere, including alarms and indications A4.04 - Containment evacuation signal Form mP.
4.6 -
3.9 2.9 3.7 3.3 -
2.8 3.7 3.7*
3.3 3.6 5-401-3 Points 1 -
1 1
1 1 -
1 1
1
PWR SRO Examination Outline KA Topic A1.01 - Spent fuel pool water level Printed: 01/09/2003 Imp.
Points 3.3 1
Facility:
K1 ES - 401 SysrEv #
033 034 035 064 064 086 103 K2 Salem ystems 42 X
System / Evolution Name Spent Fuel Pool Cooling System (SFPCS) / 8 A3 X
Fuel Handling Equipment System (FHES) / 8 K3.02 - ECCS 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
A3.04 - Number of starts available with an air compressor Steam Generator System (S/GS) / 4 4.3 1
4.1 1
3.5 1
Emergency Diesel Generator (ED/G)
System / 6 Emergency Diesel Generator (ED/G)
System I 6 K6.04 - Fire, smoke, and heat detectors Fire Protection System (FPS) / 8 2.9 1
Containment System / 5 K4.04 - Personnel access hatch and emergency WA Category Totals:
3.2 1
2 1
2 2
Group Point Total:
17 2
PWR SRO Examination Outline K6 A1 Printed: 01/09/2003 A2 A3 X
K1 I (ccws)18 K2 Steam Dump System (SDS) and Turbine Bypass Control 14 K4 I Svstem I 4 K5 X
WA Category Totals:
s ~ ~ / E ~
005 008 System / Evolution Name Residual Heat Removal System (RHRS) 14 Component Cooling Water System 0
0 0
1 K3.06 - CSS operations and safety limits.
K5.07 - Reactivity feedback effects 3
A2.17 - Malfunction of electrohydraulic contro Form Imp.
3.2*
4.1 3.6 2.9*
3-401-3 Points 1
I 1
Group Point Total:
4 1
Facility:
Salem Generic Category Conduct of Operations I
Equipment Control Radiation Control KA 2.1.10 2.1.18 2.1.19 2.1.20 2.2.1 2.2.6 2.2.21 2.2.25 2.3.1 2.3.2 2.3.3 2.3.8 Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline Printed: 0 1/09/2003 Form ES-401-5 KA Topic Knowledge of conditions and limitations in the facility license.
Ability to make accurate, clear and concise logs, records, status boards, and reports.
Ability to use plant computer to obtain and evaluate parametric information on system or component status.
Ability to execute procedure steps.
Imp.
Points Category Total:
4 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
Knowledge of the process for making changes in procedures as described in the safety analysis report.
Knowledge of pre-and post-maintenance operability requirements.
Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
3.7 Category Total:
4 Knowledge of 10 CFR: 20 and related facility radiation control requirements.
Knowledge of facility ALARA program.
Knowledge of SRO responsibilities for auxiliary systems that are outside the control room (e.g., waste disposal and handling systems).
Knowledge of the process for performing a planned gaseous radioactive release.
3.2 Category Total:
4 1
Facility:
Salem Generic Category Emergency Procedures/Plan Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline KA KA Topic 2.4.8 2.4.12 2.4.25 2.4.21 2.4.28 Printed: 0 1 /09/2003 Form ES-401-5 Knowledge of how the event-based emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs.
Knowledge of general operating crew responsibilities during emergency operations.
Knowledge of fire protection procedures.
Knowledge of fire in the plant procedure.
Knowledge of procedures relating to emergency response to sabotage.
Imp.
Points 3.I 3.9 3.4 3.5 3.3 1
1 1
1 1 -
Category Total:
5 Generic Total:
' 17 2
Record of Rejected K/As Form ES-401-10 ES-401
~ TieTGroup Randomly Selected KIA Reason for Rejection 1 / I 003 AK 1.20 Several KIA s 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 KIA s related to RCP s and Loss of KC t-I ow. 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).
I I1 1/1 112 112
~
01 / AK 1.04 Several KIA s related to KCP s and Loss of KC: FI ow. Increase breadth of examination coverage by manually selecting 0/6 AK 1.06 (unselected topic, same KIA category).
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).
Several KIA s related to PLK vapor space accident. Increase breadth of examination coverage by manually selecting to3 t A 1.3 (unselected topic, same KIA category).
Several KIA s 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).
024 AK 3.01 008 AA 1.01 038 t A 1.33
~
~~
113 056 AKI.04 Several KIA s related to Loss of Offsite Power. Increase breadth of examination coverage by manually selecting 028 AK 1.01 (unselected topic, same KIA category).
211 NUREG 1021, Revision 8. Supplement 1 001 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).
211 213 059 G 2..
4 30 005 K 5.03 KIA selected has no relevance to system. Manually selected G 2.4.4 (same KIA category for system)
Several KIA s related to KHK. Increase breadth of examination coverage by manually selecting 041 K 5.0/ (unselected topic, same KIA category).