ML031560691
| ML031560691 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/15/2003 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-390/03-301 | |
| Download: ML031560691 (16) | |
See also: IR 05000390/2003301
Text
Final Submittal
(Blue Paper)
FINAL SAMPLE PLANS I OUTLINES
WATTS BAR EXAM 2003-301
50-390/2003-301
MAY 15, 2003
Printed: 03/25/2003
Facility:
Watts Bar Nuclear Plant
Form ES-401-3
Exam Date: 05/12/2003
Exam Level: SRO
K/A Category Points
Tier
Group
Point
KI
K2
K3
K4
K5
K6
Al
A2
A3
A4
G
Total
1
4
4
4
4
4
4
24
2
3
3
2
.
i:
2
3
3
16
Emergency-
&
3
0
1
0
0
1
1
3
Abnormal
Plant
Tier
Evolutions
Totals
7
8
6
6
8
8
43
1
2
2
2
3
1
1
2
2
1
1
2
19
2.
2
1
2
2
2
1
1
_
2
1
2
2
17
Plant
___
Systems
3
0
1
0
0
0
1
0
0
1
0
1
4
Tier
Totals
3
5
4
5
2
3
3
4
3
3
5
40
Cat I
Cat 2
Cat 3
Cat 4
3. Generic Knowledge And Abilities
4
4
4
5
17
Note: I . Ensure that at least two topics from every K/A category are sampled within each teir (i.e., the "Tier Totals" in each
K/A category shal I not be less than two).
2. Actual point totals must match those specified in the table.
3. Select top ics 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 I 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 RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the
basisof plant-specific priorites. Enterthetiertotals for each category in the tableabove.
l
Facility: (
Bar Nuclear Plant
PWR SiT
lamination Outline
Printed:
03/2(
ES - 401
Emergency and Abnormal Plant Evolutions - Tier I / Group I
Form ES-401-3
E/APE #
E/APE Name / Safety Function
KI K2 K3 Al
A2 G KA Topic
Imp.
Points
001
Continuous Rod Withdrawal / I
X
_
AA2.05 - Uncontrolled rod withdrawal, from available
4.6
indications
003
Dropped Control Rod / I
_
-
X
-
_
-
AK3.08 - Criteria for inoperable control rods
4.2
1
005
Inoperable/Stuck Control Rod / I
_
-
X
-
_
-
AK3.06 - Actions contained in EOP for
4.2
1
inoperable/stuck control rod
011
Large Break LOCA /3
X
EA1.03 - Securing of RCPs
4.0
1
015
Reactor Coolant Pump (RCP) Malfunctions /4
X
-
_ _ _
AKI 05 - Effects of unbalanced RCS flow on in-core
3.3
average temperature, core imbalance, and quadrant
power tilt
024
Emergency Boration / I
X
AA2.02 - When use of manual boration valve is needed
4.4
026
Loss of Component Cooling Water (CCW)/ 8
X 2.4.11 - Knowledge of abnormal condition procedures.
3.6
029
Anticipated Transient Without Scram (ATWS) / I
X
-
_ _ _
EK2.06 - Breakers, relays, and disconnects
3.*
I1
040
Steam Line Rupture /4
X
-
AA 1.24 - Main steam header pressure gauges
3.8
_
I
Facility:
(
Bar Nuclear Plant
1 amination Outline
Printed:
03/20
ES - 401
Emergency and Abnormal Plant Evolutions - Tier I / Group 1
Form ES-401-3
E/APE
- E/APE Name / Safety Function
Kl
K2 K3 Al A2
G KA Topic
Imp.
Points
051
X
AAI.04 - Rod position
2.5*
055
Loss of Offsite and Onsite Power (Station Blackout) /
X 2.2.30 - Knowledge of RO duties in the control room
3.3
6
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
operations, and supporting instrumentation.
057
Loss of Vital AC Electrical Instrument Bus /6
X
_ AA2.12 - PZR level controller, instrumentation, and
3.7
heater indications
059
Accidental Liquid Radwaste Release /9
X 2.4.8 - Knowledge of how the event-based
3.7
emergency/abnormal operating procedures are used in
conjunction with the symptom-based EOPs.
062
Loss of Nuclear Service Water / 4
X
_ AA2.03 - The valve lineups necessary to restart the
2.9
SWS while bypassing the portion of the system causing
the abnormal condition
067
Plant Fire on Site /9
X
-
AK3.02 - Steps called out in the site fire protection plan,
3.3
FPS manual, and fire zone manual
068
Control Room Evacuation / 8
X
AK2.03 - Controllers and positioners
3.1
069
Loss of Containment Integrity / 5
X
-
_
_
AKI .01 - Effect of pressure on leak rate
3.1
074
Inadequate Core Cooling /4
X
_
-
_
_ EKI.08 - Definition of subcooled liquid
3.1
2
Facility:
(
Bar Nuclear Plant
PWR SR(
amination Outline
Printed:
03/2(
ES - 401
Emergency and Abnormal Plant Evolutions - Tier 1 / Group I
Form ES-401-3
E/APE #
E/APE Name / Safety Function
KI K2 K3 Al A2
G KA Topic
Imp.
Points
076
High Reactor Coolant Activity / 9
X
AAI.04 - Failed fuel-monitoring equipment
3.4
I
E0 1
Rediagnosis /3
X
-
_
_
_ EK2.2 - Facility's heat removal systems, including
3.8
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
E04
LOCA Outside Containment /3
X
-
_
_ EK3.3 - Manipulation of controls required to obtain
3.8
1
desired operating results during abnormal, and
emergency situations
E06
Degraded Core Cooling /4
X
2.4.10 - Knowledge of annunciator response procedures.
3.1
1
E08
Pressurized Thermal Shock /4
X
-
_
_
_
_ EKI.3 - Annunciators and conditions indicating signals,
4.0
1
and remedial actions associated with the Pressurized
Thermal Shock
£10
Natural Circulation with Steam Void in Vessel
_
X
_
_
_
_ EK2.2 - Facility's heat removal systems, including
3.9
1
with/without RVLIS / 4
primary coolant, emergency coolant, the decay heat
removal systems, and relations between tne proper
operation of these systems to the operation of the facility
K/A Category Totals:
4
4
4
4
4
4
Group Point Total:
24
3
Facility: (
PWR ST<
Bar Nuclear Plant
-amination Outline
Printed:
03/2(
ES - 401
Emnergency and Abnormal Plant Evolutions - Tier 1/ Group 2
Form ES-401-3
E/APE #
E/APE Name / Safety Function
Kl lK2 K3 Al A2 G KA Topic
imp.
Points
008
Pressurizer (PZR) Vapor Space Accident (Relief
X
AK3.01 - Why PZR level may come back on scale if
4.4
Valve Stuck Open) /3
RCS is saturated
009
Small Break LOCA /3
-
X
-
_ _ _
EK2.03 - S/Gs
3.3* I
022
Loss of Reactor Coolant Makeup /2
_
_
X
AAI .08 - VCT level
3.3
025
Loss of Residual Heat Removal System (RHRS) / 4
X
AK2.01 - RHR heat exchangers
2.9
027
Pressurizer Pressure Control (PZR PCS) Malfunction
X
-
_
_
_
_ AKI .03 - Latent heat of vaporization/condensation
2.9
/3
032
Loss of Source Range Nuclear Instrumentation /7
X
AA2.09 - Effect of improper HV setting
2.9
1
037
Steam Generator (S/G) Tube Leak / 3
X 2.4.2 - Knowledge of system set points, interlocks and
4.1
automatic actions associated with EOP entry conditions.
Note: The issue of setpoints and automatic safety
features is not specifically covered in the systems
sections.
038
Steam Generator Tube Rupture (SGTR) /3
_
-
X
-
EAI.08 - Core cooling monitor
3.8*
1
054
Loss of Main Feedwater (MFW) /4
_
_
_
-
X
-
AA2.08 - Steam flow-feed trend recorder
33*
I
Facility:
W airs Bar Nuclear Plant
PWR Sly
gamination Outline
Printed:
03/2§'
ES - 401
Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2
Form ES-401-3
E/APE #
E/APE Name / Safety Function
KI K2 K3 Al A2 Gl KA Topic
Points
060
Accidental Gaseous Radwaste Release /9
X
AK 1.02 - Biological effects on humans of the various
3.1 j*
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
060
Accidental Gaseous Radwaste Release /9
X
_
AK3.02 - Isolation of the auxiliary building ventilation
3.5*
061
Area Radiation Monitoring (ARM) System Alarms / 7
X 2.3.8 - Knowledge of the process for performing a
3.2
_
1 1
planned gaseous radioactive release.
061
Area Radiation Monitoring (ARM) System Alarms / 7
X
AK2.01 - Detectors at each ARM system location
2.6*
1
E03
LOCA Cooldown and Depressurization / 4
X
_
_
_
_
_ EK I. I - Components, capacity, and function of
4.0
emergency systems
E05
Loss of Secondary Heat Sink /4
X 14.41 - Knowledge of the emergency action level
4.1
1
thresholds and classifications.
El
Loss of Emergency Coolant Recirculation / 4
X
_ EA2.2 - Adherence to appropriate procedures and
4.2
1
operation within the limitations in the facility's license
and amendments
K/A Category Totals:
3
3
2
2
3
3
Group Point Total:
16
Facility: (
ES - 401
Bar Nuclear Plant
PWR St
Lamination Outline
Printed:
03/2(
Emergency and Abnormal Plant Evolutions - Tier 1/ Group 3
Form ES-401-3
E/APE #
E/APE Name / Safety Function
Ki K2 K3 Al
A2 G KA Topic
Imp.
Points
028
Pressurizer (PZR) Level Control Malfunction / 2
_
_
_
-
X
_ AA2.l l -Leak in PZR
3.6
056
_X
2.4.21 - Knowledge of the parameters and logic used to
4.3
assess the status of safety functions including: 1.
Reactivity control; 2. Core cooling and heat removal;
3. Reactor coolant system integrity; 4. Containment
conditions; 5. Radioactivity release control.
E13
Steam Generator Overpressure /4
-
X
-
_
-
_
EK2.1 - Components, and functions of control and
3.1
l____
safety systems, including instrumentation, signals,
_Interlocs, taiture moues, and automatic and manual
features
K/A Category Totals:
0
1
0
0
1
1
Group Point Total:
3
1
Facility: (
Imination Outline
s Bar Nuclear Plant
Printed:
030
13
ES - 401
Plant Svstems - Tier 2/ Groun I
Form ESdfl-401-
Sys/Ev # System / Evolution Name
1K1 K2
1K3
1K4
KS K6 Al A2
A3 A4 G KA Topic
Imp.
Points
001
Control Rod Drive System / I
X
-
A2.16 - Possible causes of mismatched control
3.8
1
rods
003
Reactor Coolant Pump System
4
K6.02 - RCP seals and seal water supply
3.1
(RCPS) /4
004
Chemical and Volume Control System
X
K4.08 - Hydrogen control in RCS
3.2
1
(CVCS) / I
013
Engineered Safety Features Actuation
X
K2.01 - ESFAS/safeguards equipment control
3.8
1
System (ESFAS) / 2
014
Rod Position Indication System
X
K5.01 - Reasons for differences between RPIS
3.0
I
(RPIS) / I
and step counter
015
Nuclear Instrumentation System/ 7
_
A 1.04 - Quadrant power tilt ratio
3.7
1
017
In-Core Temperature Monitor (ITM)
X
K4.03 - Range of temperature indication
3.3
1
System / 7
022
Containment Cooling System (CCS) /
X
K4.05 - Containment cooling after LOCA
2.7
1
5
destroys ventilation ducts
025
Ice Condenser System / 5
X 2.1.14 - Knowledge of system status criteria
3.3
1
which require the notification of plant
personnel.
025
Ice Condenser System / 5
X
K3.01 - Containment
3.8*
1
I
Facility: (
.,Bar
Nuclear Plant
nination Outline
Printed:
03/(
73
ES - 401
Plant Systems - Tier 2 / Groun I
Fnrm S-401-3
Sys/Ev #
System / Evolution Name
Ki K2 K3 K4 K5 K6 Al A2 A3 A4
G KA Topic
Imp.
Points
026
Containment Spray System (CSS) /5
X 2.2.9 - Knowledge of the process for
3.3
determining if the proposed change, test or
experiment increases the probability of
occurrence or consequences of an accident
during the change, test or experiment.
056
Condensate System /4
X
A2.04 - Loss of condensate pumps
2.8*
1
059
Main Feedwater (MFW) Systeml4X
-
_ A3.04 - Turbine driven feed pump
2.6*
1
061
Auxiliary / Emergency Feedwater
X
3.3
1
(AFW) System / 4
063
D.C. Electrical Distribution System /6
X
A4.02 - Battery voltage indicator
2.9
1
068
Liquid Radwaste System (LRS) / 9
X
K1.07 - Sources of liquid wastes for LRS
2.9
1
071
Waste Gas Disposal System (WGDS)
X
K3.04 - Ventilation system
2.9
1
/ 9
072
Area Radiation Monitoring (ARM)
X
_
K1(.02 - Containment isolation
3.9
1
System / 7
072
Area Radiation Monitoring (ARM)
X
Al.0I - Radiation levels
3.6
__ _
_
_
System / 7
1
1I
K/A Category Totals:
2
2
2
3
1
1
2
2
1
1
2
Group Point Total:
19
2
Facility: (
s Bar Nuclear Plant
mination Outline
Printed:
03/(
qt3
ES - 401
Plant Systems - Tier 2 / Groun 2
Form. ESA-41-
Sys/Ev #
System / Evolution Name
Ki K2 K3 K4 K5 K6 Al A2 A3
A4 G KA Topic
Imp.
Points
002
Reactor Coolant System (RCS) / 2
X
A4.04 - The filling/draining of LPI pumps
2.6
1
during refueling
O11
Pressurizer Level Control System
X
K4.07 - Cold-calibrated channel
3.2
1
(PZR LCS) /2
012
X
_K4.05
- Spurious trip protection
2.9
1
016
Non-Nuclear Instrumentation System
X
_K5.01
- Separation of control and protection
2.8*
1
(NNIS) /7
circuits
028
Hydrogen Recombiner and Purge
X
K2.01 - Hydrogen recombiners
2.8*
1
Control System (HRPS) / 5
029
Containment Purge System (CPS) / 8
X
-
_ A3.01 - CPS isolation
4.0
1
034
Fuel Handling Equipment System
X 2.2.6 - Knowledge of the process for making
3.3
1
(FHES) /8
changes in procedures as described in the safety
analysis report.
035
Steam Generator System (S/GS) / 4
X 2.4.22 - Knowledge of the bases for prioritizing
4.0
1
safety functions during abnormal/emergency
operations.
039
Main and Reheat Steam System
X
A2.02 - Decrease in turbine load as it relates to
2.7
1
(MRSS) /4
steam escaping from relief valves
055
Condenser Air Removal System
X
K11.06 - PRM system
2.6
1
(CARS) /4
I
I
Facility: (
mination Outline
3 Bar Nuclear Plant
Printed:
03/(
')3
ES - 401
Plant Syvtems% - Tier 2 / Crrnin 2
Form. ES-1-3
Sys/Ev #
System / Evolution Name
K1 K2 K3 K4 K5 K6 Al A2 A3
A4 G KA Topic
Imp.
Points
062
A.C. Electrical Distribution System / 6
X
-
A2.07 - Consequences of opening a disconnect
3.4*
under load
064
Emergency Diesel Generator (ED/G)
X
K2.03 - Control power
3.6
1
System / 6
073
Process Radiation Monitoring (PRM)
X
A 1.0 1 - Radiation levels
3.5
1
System / 7
075
X
_K3.07
- ESFAS
3.5*
079
Station Air System (SAS) / 8
X
A4.01 - Cross-tie valves with IAS
2.7
1
086
Fire Protection System (FPS) / 8
X
K6.04 - Fire, smoke, and heat detectors
2.9
1
103
Containment System / 5
X
__3.03
- Loss of containment integrity under
4.1
1
_
_
_
_
_
_
_
_
_
_
_
_refueling
operations
K/A Category Totals:
1
2
2
2
1
1
1
2
1
2
2
Group Point Total:
17
2
Facility:(
ES - 401
s Bar Nuclear Plant
niination Outline
Plant Systems - Tier 2 / Groun 3
Printed:
03/0-
'03
Form. ES-40i1-3
Sys/Ev #
System / Evolution Name
Ki K2 K3 K4 K5 K6 Al A2 A3 A4
G KA Topic
imp.
Points
008
Component Cooling Water System
X 2.1.12 - Ability to apply technical specifications 4.0
(CCWS) / 8
for a system.
041
Steam Dump System (SDS) and
X
K6.03 - Controller and positioners, including
2.9
1
Turbine Bypass Control / 4
ICS, S/G, CRDS
076
Service Water System (SWS) /4
X
K2.04 - Reactor building closed cooling water
2.6*
1
078
Instrument Air System (IAS) /8
X
-
A3.01 -Air pressure
3.2
K/A Category Totals:
0
1
0
1
0
1
0
1
0
0
1
Group Point Total:
4
I
I
Generic Knowledge and Abilities Outline (Tier 3)
iation Outline
Printed: 03/25/200
Form ES-401-5
FacilitV:
Watts Bar Nuclear Plant
Generic Category
KA Topic
Imp.
Points
Conduct of Operations
2.1.3
Knowledge of shift turnover practices.
3.4
1
2.1.7
Ability to evaluate plant performance and make operational judgments based on operating
4.4
1
characteristics, reactor behavior, and instrument interpretation.
2.1.25
Ability to obtain and interpret station reference materials such as graphs, monographs, and
3.1
1
tables which contain performance data.
2.1.34
Ability to maintain primary and secondary plant chemistry within allowable limits.
2.9
1
Category Total:
4
Equipment Control
2.2.20
Knowledge of the process for managing troubleshooting activities.
3.3
1
2.2.28
Knowledge of new and spent fuel movement procedures.
3.5
I
2.2.31
Knowledge of procedures and limitations involved in initial core loading.
2.9*
1
2.2.33
Knowledge of control rod programming.
2.9
1
Category Total:
4
Radiation Control
2.3.2
Knowledge of facility ALARA program.
2.9
1
2.3.3
Knowledge of SRO responsibilities for auxiliary systems that are outside the control room
2.9
1
(e.g., waste disposal and handling systems).
2.3.9
Knowledge of the process for performing a containment purge.
3.4
1
2.3.10
Ability to perform procedures to reduce excessive levels of radiation and guard against
3.3
personnel exposure.
Category Total:
4
Generic Knowledge and Abilities Outline (Tier 3)
(I
iation Outline
Printed: 03/25/20<
Form ES-401-5
Facility:
Watts Bar Nuclear Plant
Generic Category
KA Topic
Imp.
Points
Emergency Procedures/Plan
2.4.20
Knowledge of operational implications of EOP warnings, cautions, and notes.
4.0
1
2.4.21
Knowledge of the parameters and logic used to assess the status of safety functions
4.3
I
including: I. Reactivity control; 2. Core cooling and heat removal; 3. Reactor coolant
system integrity; 4. Containment conditions; 5. Radioactivity release control.
2.4.27
Knowledge of fire in the plant procedure.
3.5
I
2.4.29
Knowledge of the emergency plan.
4.0
1
2.4.50
Ability to verify system alarm setpoints and operate controls identified in the alarm
3.3
I
response manual.
Category Total:
5
Generic Total:
17
Newman, Terry Lee
From:
Robert Monk [RLM2@nrc.gov]
nt:
Thursday, March 13, 2003 4:09 PM
tlnewman~tva.gov
a~bject:
Sample plan
I transferred it over to the standard form and some patterns came up that could be
problematic.
That is, too many questions for a given line item (topic area) on the form.
For example, there are 4 questions on RCP's. Topic area 15/17 is really one topic in the
K/A catalog.
Some other areas had multiple questions for a topic.
Here is a suggestion that will keep it random, provide a broader sample and not require
any adjustments to the cover sheet matrix.
First, manually transfer the items to the ES 401 form.
Using the WE01 and WE02 as an example:
Skip the first X in the K2 column, go to the second X in the K3 column. Move that X up to
the first empty topic area (row) which is WE04.
Go to the third X in column Al and move
it up to row 000011.
Continue the process, moving either up or down based on where you are on the page.
The result will be a broader test and you won't have to write multiple questions on ornery
topics like Accidental Gas release.
Attach this email to your sample plan to show the methodology of the modification.
bob
\\.
_?
1