ML031840188
| ML031840188 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/05/2003 |
| From: | Roy D Florida Power & Light Energy Seabrook |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-443/03-301 50-443/03-301 | |
| Download: ML031840188 (28) | |
Text
The point total for each group and tier in the proposed outline must match tha specified in the table. The final point total for each group and tier may deviate by from that specified in the table based on NRC revisions. The final exam must total from a given system unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated. outline.
The shaded areas are not applicable to the categoryAier.
The generic WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
- 6.
33 of 46 NUREG-1021, Revision 8, Supplement 1
WAPE # I Name I Safety Function K l X
000005 Inoperable/Stuck Control Rod / 1 000015/17 RCP Malfunctions I 4 BWEOS; CWAl3; W/EOS&ElO Natural Circ. / 4 000024 Emergency Boration I 1 000026 Loss of Component Cooling Water I 8 WA Topic(s)
Imp Points K2 K3 A I A2 G
AKI.05 Calculation of minimum shutdown margin 3 3 1
X 2 1 7 Ability to evaluate plant performance and make operational 3 7 1
lud ments based on operating characteristics, reactor behavior, and insPrument interpretation abnormal and emergency operations X
EA2.1 Facility conditions and selection of appropriate procedures during 3 1 1
X AA1 17 Emergency borate control valve and indicators 3 9 1
X AK3 01 The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers 3 2 1
000027 Pressurizer Pressure Control System Malfunction I3 X
AK2.03 Controllers and positioners 2 6 1
000040 (BWIEOS. CE/E05* W/E12) Steam Line CWAl 1; WIE08 RCS Overcooling - PTS I 4 Rupture - Excessive Heat fransfer I 4 000051 Loss of Condenser Vacuum I 4 000055 Station, Blackout I 6 000057 Loss of Vital AC Elec. Inst. Bus / 6 000062 Loss of Nuclear Service Water I 4 000067 Plant Fire On-site I 9..
000069 (WIE14) Loss.of CTMT Integrity 1 5.,.
~
000074 (W/E06&E07) Inad. Core Cooling I 4 NUREG-1021, Revision 8, Supplement 1 34 of 46 X
EK1.2 Normal, abnormal and emergency o erating rocedures 3.5 1
X EK2.1 Components, and functions of control and safety systems, 3.4 1
associated with (Uncontrolled Depressurira&on of alfSteam Generators).
includin instrumentation signals, interlocks, failure modes, and automa& and manual features.
X AK3.01 Loss of steam dump capability upon loss of condenser vacuum 2.8 1
X EA1.07 Restoration of power from offsite 4.3 1
x AA2.20 Interlocks in effect on loss of ac vital electrical instrument bus 3 6 1
that must be bypassed to restore normal equipment operation emergency operations.
x 2.4.12 Knowledge,of general operating crew responsibilities during 3.4 1
X AKl.01 Fire classifications, by type 2.9 1
. ~,
!X EK2.2 Facilitys heat removal s stems, including primary coolant, 3.4 1
emergenc coolant, the decay ieat removal systems, and relations between d e proper operation of these systems to the operation of the facility.
results during abnormal, and emergency situations.
X EK3.3 Manipulation of controls required to obtain desired operating 4.0 1
000076 High Reactor Coolant Activity I 9 I
I I
I x I I AA1 04 Failed fuel-monitoring equipment 3 2 1
WA Category Totals:
I 3 I 3 I 3 I 3 I 2 1 2 I Group Point Total 16
WAPE # I Name I Safety Function K1 K2 K3 A I A2 G
K/A Topic(s)
)OW03 Dropped Control Rod I 1
X AA1.01 Demand position counter and pulselanalog converter 100008 Pressurizer Vapor Space Accident I 3
X AK3.03 Actions contained in EOP for PZR vapor space accident/ LOCA Imp Points 2 9 1
4 1 1
)00009 Small Break LOCA I 3
30001 I Large Break LOCA I 3 X
EK2 Knowled e of the interrelations between the small break LOCA and 3.0 X
EKI.01 Natural circulation and cooling, including reflux boiling.
4.1 the following: gK2.03 SlGs 1
1 NE04 LOCA Outside Containment I 3
1 X
EK2.1 Corn onents and functions of control and safety systems, 3 5 includin inskumentation, signals, interlocks, failure modes, and automa& and manual features.
1 WE1 1 Loss of Emergency Coolant Recirc. I 4 X
EK3.3 Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
1 3.8 1
W E 0 1 & E02 Rediagnosis & SI Termination I3 P
oooO59 Accidental Liquid RadWaste Rel. I 9
000060 Accidental Gaseous Radwaste Rel. I 9 X
EA1.l Com onents and functions of control and safety systems, 3 7 includin inskumenthtion, signals, interlocks, failure modes, and automa& and manual features.
000038 Steam Generator Tube Rupture I 3 B W E W WE05 lnade uate Heat Transfer - Loss of Secoddary Heat Sin! I 4 4 0 1
X EK3.05 Normal operating precautions to preclude or minimize SGTR X
EA1.2 Operating behavior characteristics of the facility 3 7 1
X AA2.05 The occurrence of automatic safety actions as a result of a high PRM system signal X
3.6 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.
3.3 2.5 3.0 000061 ARM System Alarms I 7 WE16 High Containment Radiation I 9 1
X X
17 2
35 of 46 NUREG-1021, Revision 8, Supplement 1 AKI.01 Detector limitations EK2.1 Com onents and functions of control and safety systems, includin inskumentation, signals, interlocks, failure modes, and automa& and manual features.
2 Group Point Total:
WA Category Point Totals:
3 4
3 3
J ElAPE # I Name I Safety Function Kl Y
\\
K2 K3 A1 A2 G
K/A Topic(s)
Imp Points oooO28 Pressurizer Level Malfunction I 2 X
AK2.02 Sensors and detectors 2 6 1
WE13 Steam Generator Over-pressure I4 WE15 Containment Flooding I5 X
EA1.1 Components, and functions of control and safety systems, 3.1 1
includin instrumentation. signals, interlocks, failure modes, and automa& and manual features.
X EKI.I Components, capacity, and function of emergency systems 2 0 1
NUREG-1021, Revision 8, Supplement 1 36 of 46 WA Category Point Totals:
1 1
1 Group Point Total:
3 33-401 K3 X
X P
PI K4 K5 X
X
\\
K2 Knowledge of bus power supplies to the following: K2.05 MOVs A2.27 Improper RWST boron concentration X
A4.02 Tern erature values used to determine 8CSlRCP operation during inadequate core cooling (Le.. if applicable.
avera e of five highest values) 2.1.2f!Knowledge of the purpose and function of major system components and controls.
K2.01 Containment cooling fans K4.02 Correlation of fan s eed and flowpath changes with containmenPpressure Form ES-401-4 3 RC q X
Imp.
2.8 2.9 -
2.9 2.8 -
2.7 3.5 3 7 3 8 3 8 3.2 -
3 0 3.1 G I KIA Topic@)
I Points 2
2 2
System # I Name DO1 Control Rod Drive 003 Reactor Coolant Pump A I.02 RCP pump and motor bearing tern eratures function.
2.1.87 Knowledge of system purpose and or 004 Chemical and Volume Control I A3.01 Input channels and logic I
013 Engineered Safety Features Actuation 015 Nuclear Instrumentation 017 Incore Temperature Monitor I A4.03 Trio bvoasses X
022 Containment Cooling 056 Condensate I K1 Knowledse of the Dhvsical connections 2 6 2 6 2
andlor cause-effect reiatronships between the Condensate s stem and the following I svstems: K1.03 &W 059 Main Feedwater 3.6 2.5 -
2.6 4.2 x
W K6 Knowledge of the effect bf a loss or malfunction of the followin will have on the AFW components:K6.02 fgumps K3 Knowledge of the effect that a loss or malfunction of the AFW will have on the following: K3.02 SIG 061 Auxiliary/Ernergency Feedwater
ES-401 PWR RO Examination Outline Plant Systems - Tier 2lGroup System #I Name K l K2 K3 K4 K5 K6 A I A2 A3 002 Reactor Coolant X
006 Emergency Core Cooling X
010 Pressurizer Pressure Control X
01 1 Pressurizer Level Control X
01 2 Reactor Protection X
014 Rod Position Indication X
016 Non-nuclear instrumentation X
026 Containment Spray 029 Containment Purge 033 Spent Fuel Pool Cooling 035 Steam Generator 039 Main and Reheat Steam 055 Condenser Air Removal X
062 AC Electrical Distribution X
X X
063 DC Electrical Distribution X
064 Emergency Diesel Generator X
073 Process Radiation Monitoring X
075 Circulating Water X
079 Station Air X
086 Fire Protection X
WA Category Point Totals:
2 1
2 2
1 2
2 3
2 NUREG-1021, Revision 8, Supplement 1 38 of 46 Form ES-401-4 2
A4 G
Imp Points t
A203 Lossof 4 1 1
e A I 14 Reactor vessel Idel 3 5 1
I 7 K602 PZR I I/
3.2 1
2 7 1
program -
K4 07 First-out indication 3 0 1
2 5 1
K3 02 Plant computer 3 6 1
K1 06 AFW system X
A4 01 CSS controls 4 5 1
X 2.4.31 Knowledge of annunciators alarms 3 3 1
and indications, and use of the response instructions.
A3 02 Spent fuel leak or rupture 2 9 1
X A4 06 SlG isolation on steam leak or tube 4 5 1
rupturelleak A2 04 Malfunctioning steam dump 3 4 1
2 5 1
K3 01 Main condenser K4 07 One-line diagram of 4kV to 480V 2 7 1
distribution including sources of normal and alternative power K1 02 AC electrical system 2 7 1
K6 07 Air receivers
_ _ 2 7 1
3 2 1
A1 01 Radiation levels K2 03 Emergencylessential SWS pumps 2 6 1
A2 01 Cross-connection with IAS 2 9 1
A3 02 Actuation of the FPS 2 9 1
2 1
Group Point Total 20
078 Instrument Air WA Categoty Point Totals:
Plant-Specific Priority Total: (limit 10)
A3 01 Air pressure 3 1 1
X 1
1 1
1 1
1 1
1 Group Point Total 8
39 of 46 System I Topic NUREG-1021, Revision 8. Supplement 1 Recommended Replacement for Reason Points
Topic ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5 Imp Points
!a broo k KIA #
Ability to obtain and verify controlled procedure copy.
Ability to obtain and interpret station electrical and mechanical drawinas.
2.1.2 3 1 1
2 8 1
2.1.21 2.1.24 2.2. 12 I Knowledge of surveillance procedures.
I 3.0 1
Knowledge of operator responsibilities during all modes of plant operation.
~
~
2.3.2 Knowledge of facility ALARA program.
2 5 1
Total 1 3 I
I I
2.3.10 Ability to perform procedures to reduce excessive levels 2.9 1
of radiation and guard against personnel exposure.
2.2. 25 Total 2.4.1 Knowledge of EOP entry conditions and immediate action 4.3 Knowledge of bases in technical specifications for limiting 1 2.5 conditions for oDerations and safetv limits.
I 1 3
1 2.2.1 1 I Knowledge of shift turnover practices.
I 2.5 I 1 2.4.10 I
Total 3
steps.
Knowledge of annunciator response procedures.
3.0 1
Facility:
Category
/
Conductof,
Operations I
/
/
Equipment Control r
Radiation Control
~
/
Emergency J Procedures/
Plan J
f'
... Q NUREG-1021, Revision 8, Supplement 1 40 of 46 2.4.15 Knowledge of communications procedures associated 3.0 1
with EOP implementation.
2.3.4 2.4.2 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Knowledge of system set points, interlocks and automatic 3.9 1
actions associated with EOP entry conditions.
Total 4
Abnormal Plant Totals
- 3. Generic Knowledge and Abilities Cat 1 Cat2 Cat3 Cat4 4
4 4
5 17 NUREG-1021, Revision 8, Supplement 1 26 of 46
Emergency and Abnormal Plant Evolutions -Tier l/Group 1 Imp.
EIAPE # I Name I Safety Function K1 K2 K3 AI A2 G
KIA Topic(s)
// -. 1 000001 Continuous Rod Withdrawal I f *** 1 X
AK2.08 Individual rod display lights adsications 3.0 000003 Dropped Control Rod I 1 X
AA1.01 Demand position counter and pulse/analog converter 2.9 I
000005 InoperableIStuck Control Rod I 1
/ x AK1.05 Calculation of minimum shutdown margin 4.1 00001 1 Large Break LOCA I 3 X
EKI.01 Natural circulation and cooling, including reflux boiling.
4.4 WE04 LOCA Outside Containment I 3 X
EK2.1 Components, and functions of control and safety systems.
3.9 includin instrumentation, signals, interlocks, failure modes, and automa& and manual features.
includin instrumentation, signals, interlocks, failure modes, and automa& and manual features.
natural circulation enhancement EA2.1 Facility conditions and selection of ap&opriate procedures during abnormal and emergency operations.
W E 0 1 & E02 Rediagnosis &
X EA1.l Components, and functions of control and safety systems, 3.7 000015/17 RCP Malfunctions X
AK3.07 Ensuring that S/G levels are 4.2 BWE09; CUA13; WE09&E10 Natural Circ. / 4 X
3.8 000024 Emergency Boration I 1 X
AA1.I7 Emergency borate control valve and indicators 3.9 000026 Loss of Component Cooling Water I8 X
AK3.01 The.condjtions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers 3.5 000029 Anticipated Transient wlo Scram I 1 X
EA2.01 Reactor nuclear instrumentation 4.7 000040 (BWEOS CEIEOB WIE12) Steam Line EK1.2 Normal, abnormal and emergency o erating rocedures CWAl I; WIE08 RCS Overcooling - PTS I 4 Points 1
1 1
1 1
1 1
1 1
1 1
c r":
cu
000037 Steam Generator Tube Leak I W/E1Gi&iZ&ainment
,/
RG~~~Gv 9
NUREG-1021, Revision 8, Supplement 1
PWR SRO Examination Outline Form Emergency and Abnormal Plant Evolutions - Tier l/Group 3 ES-401 UAPE # I Name I Safety Function K1 K2 K3 A1 A2 G
WA Topic(s)
Imp 000028 Pressurizer Level Malfunction I 2 X
AK2 02 Sensors and detectors 2 7 WE13 Steam Generator Over-pressure I 4 ***
WIE15 Containment Flooding I 5 X
X EA1 1 Components, and functions of control and safety systems 3 3 includin instrumentation, ignals, interlocks failure modes and automaac and manual fea4res EKI 1 Components, capa y, and function of emergency systenp I\\.
I L,
Mg :\\6" /
\\" /
KIA Category Point Totals:
1 1
1 Group Point Total 29 of 46 NUREG-1021, Revision 8, Supplement 1 ES-401-3 Points 1
1 1
3
Form ES-401-3 qG-3.1 I 1 017 In-core Temperature Monitor 2 9 2
2 9 3.3 I 3.4 I 1 4.3 1 1
- /
- 4.4 I
1 3.6 I 1
-I P NUREG-1021, Revision 8, Supplement I 30 of 46
ES-401 WA Topic(s)
A2.03 Loss of forced circulation AI 14 Reactor vessel level K602 PZR PWR SRO Examination Outline Plant Systems - Tier 2IGroup 2 Imp Points 4 3 1
3 9 1
3 5 1
I I
I I
K1.06 AFW system K5.01 Purpose of charcoal filters 033 Spent Fuel Pool X
034 Fuel Handling E X
3.5 1
3.4 1
035 Steam Generator X
039 Main and Reheat Steam 055 Condenser Air Removal X
062 AC Electrical Distribution X
X 086 Fire P r o t e r n X
X W
WA Category Point Totals:
1 1
1 1
1 2
2 3
2 2
1 A4.06 S/G isolation on steam leak or tube rupturelleak A2.04 Malfunctioning steam dump K3.01 Main condenser K4.07 One-line diagram of 4kV to 480V distribution, including sources of normal and alternative power K2.03 Ernergency/essentiai SWS pumps A2.01 Cross-connection with IAS 4 6 1
3.7 1
2.7 1
3.1 1'
3.5 1
2.7 1
3 2 /?l n
r I 3.4 hl 2 2.4.31 Knowledge of annunciators alarms and indications. and use of the resoonse i
n s
t r
u A3.02 S ent fuel leak or rupture K6 0 adiation monitoring system
-L 4
, A3.02 Actuation of the FPS I
1 A4 04 Phase A and phase 6 resets Group Point Total:
I 17 NUREG-1021, Revision 8, Supplement 1 3
Plant Systems - Tier 2IGroup 3 Imp System # I Name K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G
KIA Topic(si 005 Residual Heat Removal X
A4 02 Heat exchanger b y
w flow control 3 1 007 Pressurizer Relief/Quench Ta
[
x K1 03RCS %&
3 2 008 Component Cooling Water ff X
K2 02 CCW pump including emergency 3 2 backup 041 Steam Dumpfiurbine Bypass Control 045 Main Turbine Generator 076 Service Water I
078 Instrument Air X
A3 01 Air pressure 3 2 T
KIA Category Point Totals:
1 1
1 1
Group Point Total Points 1
1 1
1 4
~~~~
~ ~ _ _ _ _ _ _ _
System / Topic Recommended Replacement for...
Reason Points
Plant-Specific Priority Total: (limit 10)
NUREG-I 021, Revision 8, Supplement I 32 of 46
Facilitv:
Seabrook Date of Exam:
05130103 xam Level: SRC I
/
1 1
I 2.2. 12 2.2. 25 2.2.1 1 2.2.1 3 Category Knowledge of surveillance procedures.
3.4 1
Knowledge of bases in technical specifications for limiti 1
conditions for operations and safety limits. **
($0 4.
Knowledge of shift turnover practices.
/'3.4 1
Knowledae of taaaina and clearance orocedures. ***
3.8 I
Conduct of Operations Total 2.3.2 Knowledge of facility ALARA program. ***
3.0 2.3.4 Knowledge of radiation exposure limits and contamination 2.9 control, including permissible levels in excess of those authorized. ***
of radiation and guard against personnel exposure.
control reauirements.
2.3.10 Ability to perform procedures to reduce excessive levels 3.1 Knowledge of 10 CFR: 20 and related facility radiation 2.3.1 3.0 Equipment Control 4
I 1
1 1
Radiation Control Total 2.4.1 e of EOP entry conditions and immediate action 4.6 2.4.1 0 Knowledge of annunciator response procedures.
3.1 Emergency Procedures1 Plan 4
1 1
Knowledge of communications procedures associated Knowledge of system set points, interlocks and automatic Knowledge of abnormal condition procedures.
with EOP implementation.
actions associated with EOP entry conditions. -
2.4.1 1 3.5 1
4.1 I
3.6 1
Knowledge of communications procedures associated Knowledge of system set points, interlocks and automatic Knowledge of abnormal condition procedures.
with EOP implementation.
actions associated with EOP entry conditions. -
2.4.1 1 3.5 1
4.1 I
3.6 1
Tier 3 Point Total I
I 17
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5 I Facility:
Category F Knowledge of conduct of operations reauirements.
3.7 2.4.10 Knowledge of annunciator response procedures.
2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
I Date of Exam:
05/30/03 Exam Level: RC I
Seabrc KIA #
2.1.2 Points 1
1 Conduct of Operations Equipment Control Radiation Control Emergency Procedures/
Pian Tier 3 Point Total 2.1.1 2.1.11 Knowledge of less than one-hour technical I 3.0 1
specification action statement for systems.
I 3
1 Total 2.2.12 Knowledge of surveillance procedures.
3.0 2.2. 25 Knowledge of bases in technical specifications 2.5 for limiting conditions for operations and safety limits.
1 2.2.1 1 I Knowledge of shift turnover practices.
I 2.5 1
Total 3
2.3.2 I Knowledge of facility ALARA program.
I 2.5 1
2.5 1
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Knowledge of 1 OCFR20 and related facility radiation control reauirements.
2.3.1 2.6 1
Total 3
2.4.1 I Knowledge of EOP entry conditions and 4.3 1
I immediate action steps.
I 3.0 1
3.7 1
2.4.21 I Knowledge of the parameters and logic used to I assess the status of safety functions.
3.9 1
4 13 NUREG-I021, Revision 8, Supplement I 40 of 46
ES-401 Generic Knowledge and Abilities Outline-(Tier 3)
Form ES-401-5 I
I Facility:
Seabrook Date of Exam:
05/30/03 Exam Level: SRO I
I I
I Category WA #
Topic Imp.
Points 2.1.2 Knowledge of operator responsibilities during all modes of 4.0 I
plant operation.
I Conduct of Operations Equipment Control Radiation Control 2.1.I 0 3.9 2.1. I I Knowledge of less-than-1-hour technical specification 3.8 Knowledge of conditions and limitations in the facility license.
statements for systems 2.1.4 Knowledge of shift staffing requirements.
3.4 2.2.12 Knowledge of surveillance procedures.
3.4 Total 2.2.25 Knowledge of bases in technical specifications for limiting 3.7 conditions for operations and safety limits.
changes.
2.2.1 1 Knowledge of the process for controlling temporary 3.4 2.2.13 Knowledge of tagging and clearance procedures.
3.8 1
1 I 1 1 2.3.2 2.3.4 4
I Knowledge of facility ALARA program.
Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
2.9 3.1 1
2.3.10 2.3.1 1
Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
Knowledge of 10 CFR: 20 and related facility radiation control requirements.
3.3 3.0 1
2.4.1 Knowledge of EOP entry conditions and immediate action 4
I 4.6 1
Emergency Procedures/
Plan steps.
2.4.1 0 Knowledge of annunciator response procedures.
3.1 1
2.4.1 5 Knowledge of communications procedures associated 3.5 I
2.4.2 Knowledge of system set points, interlocks and automatic 4.1 1
2.4.1 1 Knowledge of abnormal condition procedures.
3.6 1
with EOP implementation.
actions associated with EOP entry conditions.
I I
4 1
I Tier 3 Point Total I
17 NUREG-1021, Revision 8, Supplement 1 40 Of 46
ES-301 Administrative Topics Outline Form ES-301-1 Administrative Topic/Su bject Description A. 1 QPTR Calculation J PM Facility: Seabrook Station Date of Examination: 6/02/03-6/05/03 Examination Level (circle one): RO Operating Test Number:
1 Describe method of evaluation:
- 2. TWO Administrative Questions 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. RO: 3.9.
JPM: Perform required QPTR due to PRNI failure.
SDM Calculation JPM A.2 A.3 A.4 2.1 2 5 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data. RO:
2.8.
JPM: Perform a SDM calculation for Natural Circulation Cooldown.
High Radiation Area Question Contamination Control Question R O s Responsibilities During Emergency Plan Implementation Tagout JPM 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. RO: 2.5.
Question: Given the plant is in a Site Area Emergency, what is the highest dose a worker is allowed to receive in a non-emergency operation.
2.3.1 Knowledge of 10CFR20 and related facility radiation control requirements. RO: 2.6.
Question: Requirements for a Locked High Rad Area.
2.4.39 Knowledge of the ROs responsibilities in emergency plan implementation. RO: 3.3.
Question: E Plan reporting requirements during training (off watch).
2.4.39 Knowledge of the ROs responsibilities in emergency plan implementation. RO: 3.3.
Question: Operator responsibilities during SGTR event.
2.2.1 3 Knowledge of tagging and clearance procedures. RO: 3.6.
JPM: Generate a danger tagout.
I
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Seabrook Station Examination Level: SRO Date of Exam in at ion: 6/02/03-6/05/03 Operating Test Number:
1 Administrative Topidsubject Description A. I A.2 A.3 A.4 Loss of RHR Cooling SDM Calculation Review Tagouts
~
Radiation control Emergency Classification, Notifications, and PAR.
JPM Describe method of evaluation:
- 2. TWO Administrative Questions 2.1.25 Ability to obtain and interpret station reference materials such as as graphs, monographs, and tables which contain performance data. SRO: 3.1.
JPM: Evaluate loss of cooling conditions and determine time to boilina from chart.
~~
~
2.1.25 Ability to obtain and interpret station reference materials such as as graphs, monographs, and tables which contain performance data. SRO: 3.1.
JPM: Review a SDM calculation for Natural Circulation Cooldown.
2.2.1 3 Knowledge of tagging and clearance procedures. SRO:
3.8.
JPM: Review a tagout request.
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. SRO: 3.1 JPM: Contaminated iniured man actions.
~~
2.4.38 Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator. SRO: 4.0 JPM: Given a set of conditions, the applicant will make an EAL determination, PAR, and make required notifications.
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Seabrook Station Exam Level (circle one): RO / SRO(I) / SRO(U)
Date of Examination: 6/02/03-6/06/03 Operating Test No.:
D'S I
B.l Control Room Systems System I JPM Title
~~~
Type Code*
Safety Function 1
- a. 001 Control Rod Drive / Power Increase to Criticality. Identify that the reactor goes critical below -500 pcm value.
~~
(SRO-U)
- c. 010 Primary Pressure Control System / Depressurize the RCS during a natural circulation cooldown with letdown unavailable IAW ES-0.2.
(SRO-U) 2 3
~
~~
~
~
- d. 062 AC Electrical distribution / Loss of All AC Power; failure of EPS on shutting EDG output breaker.
6
~
~
~
(SRO-U)
- f. 012 RPS Power Range NI Failure 5
5 D, S 7
7
- g. 004 Blended Makeup Calculation and Performance 2
B.2 Facility Walk-Through I
(SRO-U)
D 6
- c. 061 ERN / Reset the T D E W pump turbine trip throttle valve.
D 4(sec)
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, Edimulator. (Llow-Power. (RXA
Appendix D Scenario Outline Form ES-D-I h
Facility:
Seabrook Station Scenario No.:
I Op-Test No.:
1 Examiners:
Operators:
Malf. No.
Initial Conditions:
75% Dower ll Event Event Type*
Description I
Turnover:
reduce Dower to 50% in an exoeditious manner.
The reactor is at 75%. The dispatcher has reauested that Seabrook Station R(USJW N(BoP)
Event No.
Crew continues downpower in accordance with OS1 000.06, "Power Decrease".
1 ptFWPT505 2
!(ALL)
PT-505 fails low; control rods automatically insert.
3 LTRCLT459 4
WJS)
Controlling PZR level channel, LT-459, fails low.
Charging increases and letdown isolates.
5 MFED037 8
W L L )
Main generator breaker trips open (faulty 86 relay) causing a loss of load turbine trip/reactor trip.
I I
wRCPCV456A MFRPSO19 MS-V6 MS-VI MFRPSOSO C(USIB*P) c(usaRo) fait open.
WJSIBOP)
One PZR PORV and two S/G safety valves open and MSlVs are failed open and will not close automatically.
I N ( W 1 Restore letdown to service.
I' I
I I
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
DDendix D Scenario Outline Form ES-D.
Facility:
Seabrook Station Scenario No.:
2 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions:
Reactor is at IOa amm. CCP 'B is taqaed out for maintenance.
Turnover:
power increase to raise reactor Dower to minimum loading.
Power increase is in progress. Current mwer level is loa amps. Continue Event No.
Malf. No.
Event Type*
Event Description I
Normal power increase to minimum loading in accordance with OS1000.02, "Plant Startup from Hot Standby to Minimum Load" and OS1000.07, "Approach to Criticalitv".
2 LTMllT539 I(US,BOP)
S/G 'C' level transmitter, LT-539, fails high. 'C' S/G FRV bvDass valve closes.
3 MFSG002 C(US,BoP) 30 GPD primary to secondary tube leak on S/G 'A'.
S/G 'A' ASDV fails OPEN.
4 ptMSPK3001 C(US,BOP) 5 ptRCPT455 I(US,RO)
PZR pressure instrument, PT-455 fails high. PZR spray initiates.
6 MFSGOOZ M(ALL)
~
~~~
S/G 'A' 500 m m tube rwture.
7 C(ALL)
Control rods fail to insert automatically and manually (ATWS).
MFCP005 AUTORODS MANUALRODS FRPS001 FRPSOO2 bkCPRTA bkCPRTB override Rx Trip SW MFCCO16 8
C(US,RO)
CCP 'A' trips. Crew must start positive displacement DumD to comdete emeraencv boration.
(I)nstrument, (C)omponent, (M)ajor (N)ormi (R)eactivi
Amendix D Scenario Outline Form ES-D-1 Event Type*
11 Facility:
Seabrook Station Scenario No.:
3 Op-Test No.:
1 Event Description Examiners:
Operators:
Initial Conditions:
Reactor is at 75%
N&JS*RO)
R(BoP)
Turnover:
SGFP from service. SW PumD 41 C is taaaed out for maintenance.
Reactor Dower is at 75%. Crew must continue Dower decrease to remove 'A Normal power reduction in accordance with OSlOOO.06, "Power Decrease" 11 E;rt I Malf. No.
I(USIBOP)
C(USIRO)
WALL)
MFRHOOS MFRHOOG 6
MFRPSO13 MFRPSOl4 MFRH003 CCBSV14 7
8 rods insert automatically.
SGFP master speed controller fails (pumps slow down).
PCCW leak to supply of 'Cy RCP oil cooler. US will direct reactor trip on high RCP vibrations.
Large Break LOCA.
I'
- (N)ormal, (R)eactivi I
7 C(US,RO)
(USRO)
~ _ _ _ _ _
~ _ _ _ _
~
Containment isolation phase-B failed to auto initiate, Loss of ECCS Recirculation
, manual action is required.
W S I W I Loop 1 Tc fails high resulting in high Tave for loopl; C(USJJOP) Both RHR and SI pumps fail to start automatically; 1 manual start is reauired.
Scenario Outline Form ES-D-Facility:
Seabrook Station Scenario No.:
4 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions:
Reactor is at 75%. EDG 'By is faulted such that it will NOT start.
Turnover:
Reactor mwer is at 75%. Crew must continue oower increase to 100%. The
'B SW DumD is taaned out for maintenance.
Event No.
1 2
3 4
5 6
7 8
(N)orm Malf. No.
ptMSPTsO9 Override RC-PK-455A MFCSO17 MFEDO19 MFEW036 MFED038 MFRCOIG
, (R)eact Event I(US,BOP)
I(US,RO)
C(US,RO)
M(ALL)
C(US,RO)
Event Description Normal Power increase in accordance with OS1000.05, "Power Increase" Main steam header pressure instrument, PT-507, fails high resulting in an increase of SGFP speed which raises flow/pressure in the main feed lines to all generators.
~
~
Master pressure controller, PK-455A, setpoint fails high resulting in PZR pressure control system sensing low PZR pressure. All PZR heaters energize.
Centrifugal charging pump CS-P-2B trips on overcurrent.
Loss of DC bus 1 1A.
Failure of main generator output breaker to open.
Loss of all AC power from loss of offsite power and failure of both EDGs to start.
Small break LOCA (RCP seal failure). 90gpm leak results from failure of RCP seals during the loss of all AC power.
ty, (I)nstrument, (C)omponent, (M)ajor