ML033280749
| ML033280749 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/08/2003 |
| From: | Cooper P Nuclear Management Co |
| To: | NRC/RGN-III |
| References | |
| 50-282/03-301, 50-306/03-301 | |
| Download: ML033280749 (41) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021, Draft Revision 9 Page 22 of 34 Facility: Prairie Island Date of Examination: 09/08/2003 Examination Level (circle one): RO / SRO Operating Test Number: ______
Administrative Topic Describe activity to be preformed:
Conduct of Operations NEW, Review Daily Control Room Log for Discrepancies (Classroom)
Conduct of Operations NEW, Prepare Reactivity Plan For A Power Increase from 50% to 100% (Classroom)
Key Elements:
Power defect
Rod Worth
Boron worth
Boron quantity Equipment Control BANK, Remove An Annunciator Alarm From Service ADMIN-11, (Simulator)
Radiation Control BANK, Prepare to Conduct an Emergency Radiation Survey (Classroom)
Emergency Plan N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
Facility: Prairie Island Date of Examination: 09/08/2003 Examination Level (circle one): RO / SRO Operating Test Number: ______
Administrative Topic Describe activity to be preformed:
Conduct of Operations NEW, Review A Temporary Procedure Change 5AWI 1.5.10 Step 6.4.2 (Classroom)
Conduct of Operations BANK, (Repeat 2002), Determine Maximum RCS Venting Time ADMIN-10, F5 Appendix B, Attachment M - (Classroom)
Equipment Control NEW, Review a Surveillance Test for Acceptance Criteria (Classroom)
Radiation Control NEW, Authorize a Waste Gas Release (Classroom)
Emergency Plan BANK, Prepare a Protective Action Recommendation (Classroom)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021, Draft Revision 9 Page 22 of 34 Facility: Prairie Island Date of Examination: 09/08/2003 Exam Level (circle one): RO / SRO(I) / SRO(U)
Operating Test No.:___________
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function a) VC-12S A, Emergency Boration MSA 1
b) SI-11S, Transfer to Recirculation MSL 2
c) Respond to stuck open pressurizer spray valve NSAL 3
d) EO-21SF-1, RCS Bleed And Feed During Response To Loss Of Secondary Heat Sink With A PORV Failing To Open DSAL 4a e) Place standby air ejector in service (loss of condenser vac)
(ROs-Only)
NS 4b f) Response to Containment Isolation Failure to actuate NSAL 5
g) Respond To A Pressurizer Level Channel Failing HIGH NS 7
h) RC-15S, High RCS Activity DS 9
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i) F5-9, F5-10, F5-7 or F5-8, Immediate actions (by position) for control room evacuation.
D 8
j) Local start of DG (ECA-0.0 Step 18)
NA 6
k) MS-4, Locally Open 12 S/G PORV DR 4b Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021, Draft Revision 9 Page 22 of 34 Facility: Prairie Island Date of Examination: 09/08/2003 Exam Level (circle one): RO / SRO(I) / SRO(U)
Operating Test No.:___________
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function a) VC-12S, Emergency Boration MSA 1
b) SI-11S, Transfer to Recirculation MSL 2
c) Respond to stuck open pressurizer spray valve NSAL 3
d) EO-21SF-1, RCS Bleed And Feed During Response To Loss Of Secondary Heat Sink With A PORV Failing To Open DSL 4a e) Not administered to SRO Instant f) Response to Containment Isolation Failure to actuate NSAL 5
g) Respond To A Pressurizer Level Channel Failing HIGH NS 7
h) RC-15S, High RCS Activity DS 9
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i) F5-9, F5-10, F5-7 or F5-8, Immediate actions (by position) for control room evacuation.
D 8
j) Local start of DG (ECA-0.0 Step 18)
NA 6
k) MS-4, Locally Open 12 S/G PORV DR 4b Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021, Draft Revision 9 Page 22 of 34 Facility: Prairie Island Date of Examination: 09/08/2003 Exam Level (circle one): RO / SRO(I) / SRO(U)
Operating Test No.:___________
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function a) VC-12S, Emergency Boration MSA 1
b) Not administered to the SRO-U candidates.
c) New, Respond to Stuck Open Pressurizer Spray Valve NSAL 3
d) Not administered to the SRO-U candidates.
e) Not administered to the SRO-U candidates.
f) New, Response to Containment Isolation Failure to Actuate NSAL 5
g) Not administered to the SRO-U candidates.
h) Not administered to the SRO-U candidates.
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i) F5-9, F5-10, F5-7 or F5-8, Immediate actions (by position) for control room evacuation.
D 8
j) Not administered to the SRO-U candidates.
k) MS-4, Locally Open 12 S/G PORV DR 4b Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021, Draft Revision 9 Page 22 of 34 RO K/A Category Points SRO-Only Points TIER GROUP K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
TOTAL K
A A
2 G
TOTAL 1.
3 3
3 3
3 3
18 1
0 4
2 7
2.
1 2
1 1
2 2
9 1
0 2
2 5
1.
Emergency Abnormal Plant Evolutions Tier Totals 4
5 4
4 5
5 27 2
0 6
4 12 1.
3 2
3 2
3 2
3 3
2 3
2 28 2
0 0
2 4
2.
1 1
1 1
1 0
1 1
1 1
1 10 0
0 0
2 2
2.
Plant Systems Tier Totals 4
3 4
3 4
2 4
4 3
4 3
38 2
0 0
4 6
1 2
3 4
1 2
3 4
- 3. Generic Knowledge and Abilities Categories 3
2 3
2 10 2
2 2
1 7
Notes:
- 1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the Tier Totals in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling.
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution 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 (G) K/As in Tiers 1 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.
- 8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
- 9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
Page 23 of 34 NUREG-1021, Draft Revision 9 ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 000007 Reactor Trip - Stabilization - Recovery
/ 1 S
EA2.04: Ability to determine and interpret the following as they apply to a reactor trip: If reactor should have tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP 4.4 0/1 000008 Pressurizer Vapor Space Accident / 3 R
AA2.20: Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:
The effect of an open PORV on code safety, based on observation of plant parameters 3.4 1/0 000009 Small Break LOCA / 3 R
EA2.14: Ability to determine and interpret the following as they apply to a small break LOCA: Actions to be taken if PTS limits are violated 3.8 1/0 000011 Large Break LOCA / 3 R
S EK3.15: Knowledge of the reasons for the following responses as they apply to the Large Break LOCA: Criteria for shifting to recirculation mode (SRO) EA2.02: Ability to determine and interpret the following as they apply to a Large Break LOCA:
Consequences to RHR of not resetting safety injection 4.3 3.7 1/1 000015/17 RCP Malfunctions / 4 R
AK2.08: Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions and the following: CCWS 2.6 1/0 000022 Loss of Rx Coolant Makeup / 2 R
AK1.04: Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Pump Makeup: Relationship of charging flow to pressure differential between charging and RCS 2.7 1/0 000025 Loss of RHR System / 4 R
AK1.01: Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of operation 3.9 1/0 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction / 3 R
S AK3.03: Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction (SRO) 2.4.30: Emergency Procedures/Plan: Knowledge of which events related to system operations/status should be reported to outside agencies. (Pressurizer Pressure Control Malfunction) 3.7 3.6 1/1
Page 23 of 34 NUREG-1021, Draft Revision 9 ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 000029 ATWS / 1 R
EK2.06: Knowledge of the interrelations between the ATWS and the following: Breakers, relays, and disconnects 2.9 1/0 000038 Steam Gen. Tube Rupture / 3 R
EA1.27: Ability to operate and/or monitor the following as they apply to a SGTR: Steam dump valve status lights and indicators 3.9 1/0 000040 and W/E12 Steam Line Rupture -
Excessive Heat Transfer / 4 R
2.4.31: Emergency Procedures/Plan:
Knowledge of annunciators alarms and indications, and use of the response instructions. (Steam Line Rupture) 3.3 1/0 000054 Loss of Main Feedwater / 4 R
S AK3.01: Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW):
Reactor and/or turbine trip, manual and automatic (SRO) AA2.01: Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Occurrence of reactor and/or turbine trip 4.1 4.4 1/1 000055 Station Blackout / 6 S R 2.2.25: Equipment Control:
Knowledge of bases in technical specification for limiting conditions for operation and safety limits. (Station Blackout)
(SRO) EA2.02: Ability to determine and interpret the following as they apply to a Station Blackout: RCS core cooling through natural circulation cooling to S/G cooling 2.5 4.6 1/1 000056 Loss of Off-site Power / 6 R
AA1.37 :Ability to operate and/or monitor the following as they apply to the Loss of Offsite Power: Instrument air 3.4 1/0 000057 Loss of Vital AC Inst. Bus / 6 R S AA2.12: Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:
PZR level controller, instrumentation, and heater indications (SRO) 2.2.25: Equipment Control:
Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. (Loss of Vital AC Instrument Bus) 3.5 3.7 1/1 000058 Loss of DC Power / 6 R
2.1.32: Conduct of Operations: Ability to explain and apply all system limits and precautions. (Loss of DC Power) 3.4 1/0 000062 Loss of Nuclear Svc Water / 4
Page 23 of 34 NUREG-1021, Draft Revision 9 ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 000065 Loss of Instrument Air / 8 R
AA1.05: Ability to operate and/or monitor the following as they apply to the Loss of Instrument Air: RPS 3.3 1/0 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 S R EK2.2: Knowledge of the interrelations between the Loss of Emergency Coolant Recirculation and the following: Facilitys 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 (SRO) EA2.1: Ability to determine and interpret the following as they apply to Loss of Emergency Coolant Recirculation: Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
3.9 4.2 1/1 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 R
EK1.3: Knowledge of the operational implications of the following concepts as they apply to the Loss of Secondary Heat Sink: Annunciators and conditions indicating signals, and remedial actions associated with the Loss of Secondary Heat Sink 3.9 1/0 RO 3
3 3
3 3
3 K/A Category Totals SRO 1
-- -- -- 4 2
Group Point Total 18/7
NUREG-1021, Draft Revision 9 Page 24 of 34 ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 000001 Continuous Rod Withdrawal / 1 R
AA2.02: Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal:
Position of emergency boration valve 4.2 1/0 000003 Dropped Control Rod / 1 S
AA2.03: Ability to determine and interpret the following as they apply to the Dropped Control Rod: Dropped rod using in-core/ex-core instrumentation, in-core or loop temperature measurements 3.8 0/1 000005 Inoperable Stuck Control Rod / 1 000024 Emergency Boration / 1 S
AA2.01: Ability to determine and interpret the following as they apply to the Emergency Boration: Whether boron flow and/or MOVs are malfunctioning, from plant conditions 4.1 0/1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 R
AK1.01: Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation:
Effects of voltage changes on performance 2.7 1/0 000036 Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. /9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 Control Room Evac. / 8 R
AA2.05: Ability to determine and interpret the following as they apply to the Control Room Evacuation:
Availability of heat sink 4.2 1/0 000069 and W/E14 Loss of CTMT Integrity / 5 R
EK2.1: Knowledge of the interrelations between the High Containment Pressure and the following:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.4 1/0
NUREG-1021, Draft Revision 9 Page 24 of 34 ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 000074 (W/E06 & 07) Inad. Core Cooling / 4 R
S EK2.1: Knowledge of the interrelations between the Saturated Core Cooling and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features (SRO) 2.2.25: Equipment Control:
Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
(Inadequate Core Cooling) 3.2 3.7 1/1 000076 High Reactor Coolant Activity / 9 R
AK3.06: Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity:
Actions contained in EOP for high reactor coolant activity 3.2 1/0 W/E01 and W/E02 Rediagnosis & SI Termination / 3 R
EA1.2: Ability to operate and/or monitor the following as they apply to the SI Termination: Operating behavior characteristics of the facility 3.6 1/0 W/E13 Steam Generator Over-pressure / 4 S R 2.1.23: Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation. (Steam Generator Overpressure)
(SRO) EA2.2: Ability to determine and interpret the following as they apply to the Steam Generator Overpressure:
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.9 3.4 1/1 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 W/E03 LOCA Cooldown - Depress. / 4 W/E09 and W/E10 Natural Circ. / 4 S
EA2.2: Ability to determine and interpret the following as they apply to the Natural Circulation with Steam Void in Vessel with/without RVLIS:
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.9 1/0 W/E08 RCS Overcooling - PTS / 4 R
2.1.23: Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation. (Pressurized Thermal Shock) 3.9 1/0 RO 1
2 1
1 2
2 K/A Category Totals SRO 1
-- -- -- 2 2
Group Point Total 9/5
Page 25 of 34 NUREG-1021, Draft Revision 9 ES-401 PWR Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 003 Reactor Coolant Pump R
K2.01: Knowledge of bus power supplies to the following: RCPS 3.1 1/0 004 Chemical and Volume Control R
K5.17: Knowledge of the operational implications of the following concepts as they apply to the CVCS: Types and effects of radiation, dosimetry, and shielding-time-distance 2.6 1/0 005 Residual Heat Removal R
K6.03: Knowledge of the effect of a loss or malfunction of the following will have on the RHRS: RHR heat exchanger 2.5 1/0 006 Emergency Core Cooling R
K5.06: Knowledge of the operational implications of the following concepts as they apply to the ECCS:
Relationship between ECCS flow and RCS pressure 3.5 1/0 007 Pressurizer Relief/Quench Tank R
A3.01: Ability to monitor automatic operation of the PRTS, including:
Components which discharge to the PRT 2.7 1/0 008 Component Cooling Water R
A1.04: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including: Surge tank level 3.1 1/0 010 Pressurizer Pressure Control R
R K1.06: Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems: CVCS A1.01: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: PZR and RCS boron concentrations 2.9 2.8 2/0 012 Reactor Protection S
R K5.01: Knowledge of the operational implications of the following concepts as they apply to the RPS: DNB (SRO) 2.2.25: Equipment Control:
Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. (RPS) 3.3 3.7 1/1 013 Engineered Safety Features Actuation R
S K6.01: Knowledge of the effect of a loss or malfunction of the following will have on the ESFAS: Sensors and detectors (SRO) 2.2.25: Equipment Control:
Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. (ESFAS) 2.7 3.7 1/1
Page 25 of 34 NUREG-1021, Draft Revision 9 ES-401 PWR Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 022 Containment Cooling R
A1.04: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Cooling water flow 3.2 1/0 026 Containment Spray R
R K3.01: Knowledge of the effect that a loss or malfunction of the CSS will have on the following: CCS A2.03: Ability to (a) predict the impacts of the following malfunctions or operations on the CSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of ESF 3.9 4.1 2/0 039 Main and Reheat Steam R
R 2.4.49: Emergency Procedures/Plan:
Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. (Main and Reheat Steam)
K1.06: Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: Condenser steam dump 4.0 3.1 2/0 056 Condensate R
A2.04: Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps 2.6 1/0 059 Main Feedwater R
R K3.04: Knowledge of the effect that a loss or malfunction of the MFW System will have on the following:
RCS A4.12: Ability to manually operate and/or monitor in the control room:
Initiation of automatic feedwater isolation 3.6 3.4 2/0
Page 25 of 34 NUREG-1021, Draft Revision 9 ES-401 PWR Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 061 Auxiliary/Emergency Feedwater R
R K2.02: Knowledge of bus power supplies to the following: AFW electric driven pumps K4.02: Knowledge of AFW System design feature(s) and/or interlock(s) which provide for the following: AFW automatic start upon loss of MFW pump, S/G level, blackout, or safety injection 3.7 4.5 2/0 062 AC Electrical Distribution R
S K3.02: Knowledge of the effect that a loss or malfunction of the A.C.
Distribution System will have on the following: ED/G (SRO) 2.4.6: Emergency Procedures/Plan: Knowledge symptom based EOP mitigation strategies. (AC Electrical Distribution) 4.1 4.0 1/1 063 DC Electrical Distribution R
A2.01: Ability to (a) predict the impacts of the following malfunctions or operations on the D.C. Electrical System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Grounds 2.5 1/0 064 Emergency Diesel Generator S
R A3.03: Ability to monitor automatic operation of the ED/G System, including: Indicating lights, meters, and recorders (SRO) 2.2.22: Knowledge of limiting conditions for operations and safety limits.
3.4 2.9 1/1 073 Process Radiation Monitoring R
A4.03: Ability to manually operate and/or monitor in the control room:
Check source for operability demonstration 3.1 1/0 076 Service Water R R 2.1.14: Conduct of Operations:
Knowledge of system status criteria which require the notification of plant personnel. (Service Water System)
A4.04: Ability to manually operate and/or monitor in the control room:
Emergency heat loads 2.5 3.5 2/0 078 Instrument Air R
K1.02: Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Service air 2.7 1/0
Page 25 of 34 NUREG-1021, Draft Revision 9 ES-401 PWR Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 103 Containment R
K4.04: Knowledge of Containment System design feature(s) and/or interlock(s) which provide for the following: Personnel access hatch and emergency access hatch 2.5 1/0 RO 3
2 3
2 3
2 3
3 2
3 2
K/A Category Totals:
-- -- 1
-- -- 1
-- -- -- -- 2 Group Point Total:
28/4
2003 ILT Exam K/A Suppression Report Page 26 of 40 ES-401 PWR Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 Group 2 (RO / SRO)
K 1
K 2
K 3
K 4
K 5
K 6
A 1
A 2
A 3
A 4
G K/A Topic(s)
IR 001 Control Rod Drive 002 Reactor Coolant R
A3.03: Ability to monitor automatic operation of the RCS, including:
Pressure, temperatures, and flows 4.4 1/0 011 Pressurizer Level Control R
S K2.01: Knowledge of bus power supplies to the following: Charging pumps (SRO) 2.4.4: Emergency Procedures/Plan: Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures..
(Pressurizer Level Control System) 3.1 4.3 1/1 014 Rod Position Indication R
K3.02: Knowledge of the effect that a loss or malfunction of the RPIS will have on the following: Plant computer 2.5 1/0 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor R
A1.01: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ITM System controls including: Core exit temperature 3.7 1/0 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control R S A4.02: Ability to manually operate and/or monitor in the control room:
Location and interpretation of containment pressure indications (SRO) 2.2.25: Equipment Control:
Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
(Hydrogen Recombiner and Purge Control System) 3.7 3.7 1/1 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator
2003 ILT Exam K/A Suppression Report Page 27 of 40 ES-401 PWR Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 Group 2 (RO / SRO)
K 1
K 2
K 3
K 4
K 5
K 6
A 1
A 2
A 3
A 4
G K/A Topic(s)
IR 041 Steam Dump/Turbine Bypass Control R
K5.07: Knowledge of the operational implications of the following concepts as they apply to the SDS: Reactivity feedback effects 3.1 1/0 045 Main Turbine Generator 055 Condenser Air Removal R
2.1.32: Conduct of Operations: Ability to explain and apply all system limits and precautions. (Condenser Air Removal System) 3.4 1/0 068 Liquid Radwaste R
A2.04: Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Failure of automatic isolation 3.3 1/0 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air R
K4.01: Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with IAS 2.9 1/0 086 Fire Protection R
K1.01: Knowledge of the physical connections and/or cause-effect relationships between the Fire Protection System and the following systems: High-pressure service water 3.0 1/0 RO 1
1 1
1 1
0 1
1 1
1 1
K/A Category Totals:
-- -- -- -- -- -- -- -- -- -- 2 Group Point Total:
10/2
2003 ILT Exam K/A Suppression Report Page 28 of 40 ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Prairie Island Date of Exam: 09/11/2003 RO SRO Category K/A #
Topic IR IR 2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports.
2.9 1
2.1.29 Knowledge of how to conduct and verify valve lineups.
3.4 1
2.1.31 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
4.2 1
2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.
2.9 1
2.1.6 Conduct of Operations: Ability to supervise and assume a management role during plant transients and upset conditions.
4.3 1
1.
Conduct of Operations Subtotal 3
2 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
3.7 1
2.2.4 Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility. (multi-unit) 2.8 1
2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
3.7 1
2.2.32 Knowledge of the effects of alterations on core configuration.
3.3 1
2.
Equipment Control Subtotal 2
2 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.
2.6 1
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
2.9 1
2.3.9 Knowledge of the process for performing a containment purge.
2.5 1
2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
3.1 1
2.3.3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control room (e.g., waste disposal and handling systems).
2.9 1
3.
Radiation Control Subtotal 3
2 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures.
3.0 1
2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.0 1
2.4.27 Knowledge of fire in the plant procedure.
3.5 1
4.
Emergency Procedures /
Plan Subtotal 2
1 Tier 3 Point Total 10 7
2003 ILT Exam K/A Suppression Report Page 29 of 40 Facility: Prairie Island Scenario No.: 2003NRC-A Op-Test No.:
Examiners:
Operators:
RO:
Lead:
SS:
Initial Conditions: (IC-40)
100% power EOC
Turbine impulse pressure failed with S/D abnormal per C51 Turnover:
Event No.
Malf.
No.
Event Type*
Event Description 1
VC01A C
Loss of charging pump (RO) 2 RC21A C
Reactor vessel flange O-ring leak (RO) 3 Various Overrides I
Rad monitor (R-11 &12) low flow (LEAD) {T.S}
4 MS01B M
Steam line rupture inside containment [Ramp 35% over 5 minutes]
5 FW34A/B C
AFW pumps fail to start (RO) 5 FW32 C
Trip of MDAFW pump on manual start 6
RP06 C
MSIVs fail to auto close 6
DI-46158C DI-46159C C
MSIVs fail to close in manual (ECA-2.1) (LEAD has CT actions) 7 CS03A/B C
CS pumps fail to start (LEAD) 8 CS02A/B C
Caustic addition valves fail to open (LEAD)
Critical Tasks:
E-0 (E) Minimum containment cooling equipment
E-0 (F) Minimum AFW flow
ECA-2.1 (A) Reduce AFW flow
2003 ILT Exam K/A Suppression Report Page 30 of 40 Facility: Prairie Island Scenario No.: 2003NRC-B Op-Test No.:
Examiners:
Operators:
RO:
Lead:
SS:
Initial Conditions: (IC-6)
6% power
Turnover:
Event No.
Malf.
No.
Event Type*
Event Description 1
RX216 I
SG pressure fails (HIGH) {T.S.} (LEAD) 2 SI07A C
SI accumulator check valve leakage (LEAD) 3 FW13A C
Main feedwater pump trips (RO - power reduction) 4 ED18, ED19, DG07A/B M
Loss of all AC power (ECA-0.0) with restoration from DG within 5 minutes 5
SG02A M
SG tube rupture [10%]
6 DI-46158C C
Associated MSIV wont close in manual 7
RC22A or B C
Pressurizer PORV leaks after RCS depressurization (RO)
Critical Tasks:
E-0 (A) Restore heat sink -OR-Manual reactor trip
E-0 (C) Restore electrical power
E-3 (A) Isolate ruptured SG
E-3 (C) Depressurize RCS
E-3 (D) Terminate SI
2003 ILT Exam K/A Suppression Report Page 31 of 40 Facility: Prairie Island Scenario No.: 2003NRC-C Op-Test No.:
Examiners:
Operators:
RO:
Lead:
SS:
Initial Conditions: (IC-
79% power
Maximize pressurizer bypass spray flow
Ensure pressurizer heaters are in AUTO Turnover:
Event No.
Malf.
No.
Event Type*
Event Description 1
EG200 I
Generator gas temperature controller failure (LEAD) 2 RX014 I
Pressurizer low level bistable failure (No heaters) (RO) 3 CC01B C
Running CC pump trips 3
CC02A C
Standby CC pump fails to auto-start {T.S. 3.0.3} (LEAD) 4 MS02B M
Main steam rupture outside containment before MSIV 5
various C
ATWS (setup using computer assisted exercise) 6 TC01A C
Turbine stop valve sticks open (LEAD) 7 NI04A I
IR compensation causes P-6 failure (SR does not energize) (RO)
Critical Tasks:
E-0 (A) Manual reactor trip
E-0 (K) Minimum CCW pumps
FR-S.1 (C) Negative reactivity insertion
FR-S.1 (A) Isolate Main Turbine
2003 ILT Exam K/A Suppression Report Page 32 of 40 Facility: Prairie Island Scenario No.: 2003NRC-D Op-Test No.:
Examiners:
Operators:
RO:
Lead:
SS:
Initial Conditions: (IC-15)
Mode 4
RCS temperature 320F - 340F
RCS pressure <400 psig Turnover:
Ready to place RHR in service
RCP 11 is operating
RCP 12 needs to be placed in service and RCP 11 stopped.
Event No.
Malf.
No.
Event Type*
Event Description 0
RX09A I
Loop pressure instrument fails HIGH 1
NA N
Switch operating RCPs. (RO) 2 ED09A C
Loss of 4160v Bus #11 {T.S.}
3 CC09 C
Seal water heat exchanger tube rupture [70%] (LEAD) 4 RC05B C
Bearing failure on only running RCP {T.S.} (RO) 5 RC08A M
LOCA - RCS cold leg (will result in PTS -> FR-P.1) [Ramp 2%-6%]
6 SI05A/B C
SI pumps fail to start on SI (LEAD) 7 DI-46026 C
Loss of CCW flow to RCP thermal barriers (LEAD)
Critical Tasks:
E-0 (I) Minimum SI pumps
FR-P.1 (A) Terminate SI
2003 ILT Exam K/A Suppression Report Page 33 of 40 KA suppression was performed in accordance with ES-401 Attachment 2 K/A Elimination Guidance from NUREG-1021 Draft Revision 9.
The attached tables do not include K/As suppressed for the following reasons:
All K/As associated with System 025 Ice Condenser System were suppressed because this form of containment is not installed at Prairie Island.
All generic K/As were suppressed for RO and SRO exam outline preparation at Tier 1 and Tier 2 except for K/As 2.1.2, 2.1.14, 2.1.23, 2.1.27, 2.1.28, 2.1.30, 2.1.32, 2.1.33, 2.2.22, 2.2.25, 2.4.4, 2.4.6, 2.4.30, 2.4.31, 2.4.49 and 2.4.50. No K/As were suppressed for outline preparation at Tier 3.
All K/As with RO importance ratings less than 2.5 were suppressed for the RO exam outline preparation.
All K/As with SRO importance ratings less than 2.5 were suppressed for the SRO exam outline preparation.
The attached tables for Tier 1 and Tier 2 identify, with the four bulleted exceptions noted above, those K/A statements which were suppressed prior to random generation of the written exam outlines for the 2003 Prairie Island RO and SRO exams.
2003 ILT Exam K/A Suppression Report Page 34 of 40 Tier 1 - Events Event Information K/A #
K/A Statement Basis for suppression 001 Continuous Rod Withdrawal AK1.14 Knowledge of the operational implications of the following concepts as they apply to Continuous Rod Withdrawal:Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS Equipment not installed.
003 Dropped Control Rod AA1.04 Ability to operate and/or monitor the following as they apply to the Dropped Control Rod: Control rod drive safety rod out limit bypass switch or key Equipment not installed.
003 Dropped Control Rod AK1.13 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS Equipment not installed.
003 Dropped Control Rod AK2.03 Knowledge of the interrelations between the Dropped Control Rod and the following:
Metroscope Equipment not installed.
003 Dropped Control Rod AK3.01 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: When ICS logic has failed on a dropped rod, the load must be reduced until flux is within specified target bank Equipment not installed.
003 Dropped Control Rod AK3.02 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Reactor runback with a dropped control rod Equipment not installed.
003 Dropped Control Rod AK3.03 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Turbine automatic runback with reactor in order to balance power outpu Equipment not installed.
003 Dropped Control Rod AK3.05 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Tech-Spec limits for reduction of load to 50%
power if flux cannot be brought back within specified target band Action not applicable.
(Reactor must be tripped.)
003 Dropped Control Rod AK3.06 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Reset of demand position counter to zero Action not applicable.
(Reactor must be tripped.)
003 Dropped Control Rod AK3.09 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Recording of group bank position for dropped rod (reference point used to withdraw dropped rod to equal height with other rods in the bank)
Action not applicable.
(Reactor must be tripped.)
005 Inoperable/Stuck Control Rod AA1.03 Ability to operate and/or monitor the following as they apply to the Inoperable/Stuck Control Rod:
Metroscope Equipment not installed.
005 Inoperable/Stuck Control Rod AA2.02 Ability to determine and interpret the following as they apply to the Inoperable/Stuck Control Rod:
Difference between jog and run rod speeds, effect on CRDM of stuck rod Equipment not installed.
005 Inoperable/Stuck Control Rod AK1.04 Knowledge of the operational implications of the following concepts as they apply to Inoperable/Stuck Control Rod: Definitions of axial imbalance, neutron error, power demand, actual power tracking mode, ICS tracking Equipment not installed.
2003 ILT Exam K/A Suppression Report Page 35 of 40 Tier 1 - Events Event Information K/A #
K/A Statement Basis for suppression 005 Inoperable/Stuck Control Rod AK2.03 Knowledge of the interrelations between the Inoperable/Stuck Control Rod and the following:
Metroscope Equipment not installed.
008 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck AA2.23 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: Criteria for throttling high-pressure injection after a small LOCA SI Throttling not allowed for.
009 Small Break LOCA EA1.18 Ability to operate and/or monitor the following as they apply to a small break LOCA: Balancing of HPI loop flows Equipment not installed or capability does not exist.
009 Small Break LOCA EA2.26 Ability to determine and interpret the following as they apply to a small break LOCA: Activity waste tank level gauges Equipment not in CR & action not required.
009 Small Break LOCA EA2.30 Ability to determine and interpret the following as they apply to a small break LOCA: Tech-Spec limits for plant operation with less than four loops 2 loop does not allow for idle loop operation.
009 Small Break LOCA EA2.31 Ability to determine and interpret the following as they apply to a small break LOCA: Tech-Spec limits for plant operation with an idle loop 2 loop does not allow for idle loop operation.
009 Small Break LOCA EA2.35 Ability to determine and interpret the following as they apply to a small break LOCA: Conditions for throttling or stopping reflux boiling spray Equipment not installed or capability does not exist.
011 Large Break LOCA EA1.02 Ability to operate and/or monitor the following as they apply to a Large Break LOCA: Reflux boiling sump level indicators Equipment not installed or action does not occur.
011 Large Break LOCA EA1.16 Ability to operate and/or monitor the following as they apply to a Large Break LOCA: Balancing of HPI loop flows Equipment not installed or action does not occur.
011 Large Break LOCA EA2.12 Ability to determine and interpret the following as they apply to a Large Break LOCA: Conditions for throttling or stopping reflux boiling spray Equipment not installed or action does not occur.
011 Large Break LOCA EK3.07 Knowledge of the reasons for the following responses as they apply to the Large Break LOCA:
Stopping charging pump bypass flow Equipment not installed or action does not occur.
011 Large Break LOCA EK3.13 Knowledge of the reasons for the following responses as they apply to the Large Break LOCA:
Hot-leg injection/recirculation Equipment not installed or action does not occur.
015 Reactor Coolant Pump (RCP)
Malfunctions AA1.19 Ability to operate and/or monitor the following as they apply to the Reactor Coolant Pump Malfunctions: Power transfer confirm lamp Equipment not installed.
015 Reactor Coolant Pump (RCP)
Malfunctions AK1.03 Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions: The basis for operating at a reduced power level when one RCP is out of service 2 loop, Single loop operation not allowed.
015 Reactor Coolant Pump (RCP)
Malfunctions AK3.04 Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions: Reduction of power to below the steady state power-to-flow limit Power to flow limit does not exist 024 Emergency Boration AA1.01 Ability to operate and/or monitor the following as they apply to the Emergency Boration: Use of spent fuel pool as backup to BWST Flowpaths not available/used for emergency boration
2003 ILT Exam K/A Suppression Report Page 36 of 40 Tier 1 - Events Event Information K/A #
K/A Statement Basis for suppression 024 Emergency Boration AA1.04 Ability to operate and/or monitor the following as they apply to the Emergency Boration: Manual boration valve Flowpath not directed for use 024 Emergency Boration AA1.10 Ability to operate and/or monitor the following as they apply to the Emergency Boration: CVCS centrifugal charging pumps Equipment not installed.
024 Emergency Boration AA1.11 Ability to operate and/or monitor the following as they apply to the Emergency Boration: BIT suction and recirculation valves Equipment not installed.
024 Emergency Boration AA1.20 Ability to operate and/or monitor the following as they apply to the Emergency Boration: Manual boration valve and indicators Flowpath not directed for use 024 Emergency Boration AA1.21 Ability to operate and/or monitor the following as they apply to the Emergency Boration: CVCS charging pump miniflow isolation valves and indicators Equipment not installed.
024 Emergency Boration AA1.22 Ability to operate and/or monitor the following as they apply to the Emergency Boration: Safety injection valves, switches, flow meters, and indicators Flowpaths not available/used for emergency boration 024 Emergency Boration AA1.23 Ability to operate and/or monitor the following as they apply to the Emergency Boration: CVCS centrifugal charging pump switches and indicators Equipment not installed.
024 Emergency Boration AA1.24 Ability to operate and/or monitor the following as they apply to the Emergency Boration: BIT inlet and outlet valve switches and indicators Equipment not installed.
024 Emergency Boration AA2.02 Ability to determine and interpret the following as they apply to the Emergency Boration: When use of manual boration valve is needed Flowpath not directed for use 025 Loss of Residual Heat Removal System (RHRS)
AA1.05 Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: Raw water or sea water pumps Equipment not installed.
025 Loss of Residual Heat Removal System (RHRS)
AA1.13 Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: SWS radiation monitors Flowpath not directly affected 025 Loss of Residual Heat Removal System (RHRS)
AA1.19 Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: Block orifice bypass valve controller and indicators Equipment not installed.
028 Loss of Component Cooling Water (CCW)
AA1.03 Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water: SWS as a backup to the CCWS Systems not related in this manner.
028 Loss of Component Cooling Water (CCW)
AA1.04 Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water: CRDM high-temperature alarm system Systems not related in this manner.
027 Pressurizer Pressure Control (PZR PCS)
Malfunction AA1.02 Ability to operate and/or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: SCR-controlled heaters in manual mode Manual mode operation not performed any differently than that covered by KA:
AA1.01.
028 Pressurizer (PZR) Level Control Malfunction AK3.04 Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions: Change in PZR level with power change, even though RCS T-ave. constant, due to loop size difference Plant does not react in this manner
2003 ILT Exam K/A Suppression Report Page 37 of 40 Tier 1 - Events Event Information K/A #
K/A Statement Basis for suppression 029 Anticipated Transient Without Scram (ATWS)
EA1.04 Ability to operate and/or monitor the following as they apply to a ATWS: BIT inlet valve switches Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EA1.05 Ability to operate and/or monitor the following as they apply to a ATWS: BIT outlet valve switches Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EA1.06 Ability to operate and/or monitor the following as they apply to a ATWS:Operating switches for normal charging header isolation valves Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EA1.07 Ability to operate and/or monitor the following as they apply to a ATWS: Operating switch for charging pump recirculation valve Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EA2.03 Ability to determine and interpret the following as they apply to a ATWS: Centrifugal charging pump ammeter Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EA2.04 Ability to determine and interpret the following as they apply to a ATWS: CVCS centrifugal charging pump operating indication Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EK3.03 Knowledge of the reasons for the following responses as they apply to the ATWS: Opening BIT inlet and outlet valves Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EK3.04 Knowledge of the reasons for the following responses as they apply to the ATWS: Closing the normal charging header isolation valves Action not performed for Evolution 029 Anticipated Transient Without Scram (ATWS)
EK3.05 Knowledge of the reasons for the following responses as they apply to the ATWS: Closing the centrifugal charging pump recirculation valve Equipment not installed or not used in Evolution.
029 Anticipated Transient Without Scram (ATWS)
EK3.09 Knowledge of the reasons for the following responses as they apply to the ATWS: Opening centrifugal charging pump suction valves from RWST Equipment not installed or not used in Evolution.
037 Steam Generator (S/G) Tube Leak AA1.03 Ability to operate and/or monitor the following as they apply to the Steam Generator Tube Leak:
Loop isolation valves Equipment not installed.
037 Steam Generator (S/G) Tube Leak AK3.08 Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: Criteria for securing RCP Does not apply to this Evolution.
038 Steam Generator Tube Rupture (SGTR)
EA1.28 Ability to operate and/or monitor the following as they apply to a SGTR: Interlock between MSIV and bypass valve Equipment not installed.
038 Steam Generator Tube Rupture (SGTR)
EK1.04 Knowledge of the operational implications of the following concepts as they apply to the SGTR:
Reflux boiling Condition not expected for Evolution.
038 Steam Generator Tube Rupture (SGTR)
EK3.07 Knowledge of the reasons for the following responses as they apply to the SGTR: RCS loop isolation values Equipment not installed.
040 Steam Line Rupture AA1.21 Ability to operate and/or monitor the following as they apply to the Steam Line Rupture: Vibration alarm Not applicable to this evolution.
056 Loss of Offsite Power AA1.15 Ability to operate and/or monitor the following as they apply to the Loss of Offsite: Service water booster pump Equipment not installed.
2003 ILT Exam K/A Suppression Report Page 38 of 40 Tier 1 - Events Event Information K/A #
K/A Statement Basis for suppression 056 Loss of Offsite Power AA2.11 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:
Operational status of service water booster pump Equipment not installed.
056 Loss of Offsite Power AA2.29 Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Service water booster pump ammeter and flowmeter Equipment not installed.
057 Loss of Vital AC Electrical Instrument Bus AA1.03 Ability to operate and/or monitor the following as they apply to the Loss of Vital AC Instrument Bus:
Feedwater pump speed to control pressure and level in S/G Constant speed motor-driven feed pumps w/o controllers.
057 Loss of Vital AC Electrical Instrument Bus AA2.02 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:
Core flood tank pressure and level indicators Redundant (different eqpt name) to AA2.01.
057 Loss of Vital AC Electrical Instrument Bus AA2.11 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:
Main feed pump running indicator and controller Constant speed motor-driven feed pumps w/o controllers.
062 Loss of Nuclear Service Water AA1.03 Ability to operate and/or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): SWS as a backup to the CCWS System does not provide this function.
062 Loss of Nuclear Service Water AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers Equipment not installed, Lake provides cooling 065 Loss of Instrument Air AA2.07 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Whether backup nitrogen supply is controlling valve position Equipment not installed.
065 Loss of Instrument Air AK3.05 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Checking electric loads on a running compressor Equipment not installed.
068 Control Room Evacuation AK3.04 Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation: Filling the feedwater system and closing the AFW pump discharge valve Action not performed.
074 Inadequate Core Cooling EA1.03 Ability to operate and/or monitor the following as they apply to an Inadequate Core Cooling: The alternate control station for turbine bypass valve operation Equipment not installed.
076 High Reactor Coolant Activity AA1.04 Ability to operate and/or monitor the following as they apply to the High Reactor Coolant Activity:
Failed fuel-monitoring equipment Equipment not installed
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 001 Control Rod Drive System A1.08 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CRDS controls including: Verification that CRDS temperatures are within limits before starting Actions not performed.
001 Control Rod Drive System A1.10 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CRDS controls including: Location and operation of controls and indications for CRDS component cooling water Equipment not installed or not aligned in this manner.
001 Control Rod Drive System A1.13 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CRDS controls including: "Prepower dependent insertion limit" and power dependent insertion limit, determined with metroscope Equipment not installed or not aligned in this manner.
001 Control Rod Drive System A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Positioning of axial shaping rods and their effect on SDM Equipment not installed or not aligned in this manner.
001 Control Rod Drive System A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCW to CRDS Equipment not installed or not aligned in this manner.
001 Control Rod Drive System A2.20 Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Isolation of lift coil on affected rod to prevent coil burnout Action not performed 001 Control Rod Drive System A4.09 Ability to manually operate and/or monitor in the control room: CCWS Equipment not installed or not aligned in this manner.
001 Control Rod Drive System K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the following systems: CCW Equipment not installed or not aligned in this manner.
001 Control Rod Drive System K1.09 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the following systems: CCWS must be cut in before energizing CRDS Equipment not installed or not aligned in this manner.
001 Control Rod Drive System K5.11 Knowledge of the operational implications of the following concepts as they apply to the CRDS:
Relationship between reactivity worth of power-shaping control rod group and other control rod groups (power-shaping, or part-length, rods have much less reactivity than full-length control rods)
Equipment not installed or not aligned in this manner.
001 Control Rod Drive System K5.12 Knowledge of the operational implications of the following concepts as they apply to the CRDS:
Effects on power of inserting axial shaping rods Equipment not installed or not aligned in this manner.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 001 Control Rod Drive System K5.16 Knowledge of the operational implications of the following concepts as they apply to the CRDS:
Relationship between RCS temperature and NDT of vessel Heatup & cooldown at temperatures of concern not associated with CRDS 001 Control Rod Drive System K5.68 Knowledge of the operational implications of the following concepts as they apply to the CRDS:
Understanding of "cold-water" (startup) accidents "Cold" startups not allowed 001 Control Rod Drive System K5.76 Knowledge of the operational implications of the following concepts as they apply to the CRDS:
Effects on power of inserting axial shaping rods Equipment not installed or not aligned in this manner.
001 Control Rod Drive System K5.79 Knowledge of the operational implications of the following concepts as they apply to the CRDS:
Effects of positioning of axial shape rods on SDM Equipment not installed or not aligned in this manner.
002 Reactor Coolant System (RCS)
A4.05 Ability to manually operate and/or monitor in the control room: The HPI system when it is used to refill the refueling cavity System is not used in this manner.
002 Reactor Coolant System (RCS)
K4.09 Knowledge of RCS design feature(s) and/or interlock(s) which provide for the following:
Operation of loop isolation valves Equipment not installed.
002 Reactor Coolant System (RCS)
K5.16 Knowledge of the operational implications of the following concepts as they apply to the RCS:
Reason for automatic features of the Feedwater control system during total loss of reactor coolant flow Equipment not installed.
002 Reactor Coolant System (RCS)
K6.15 Knowledge of the effect of a loss or malfunction on the following RCS components: Post-accident sampling Value not determined yet for both RO & SRO importance..
003 Reactor Coolant Pump System (RCPS)
K1.11 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems: Sound monitoring Equipment not installed.
003 Reactor Coolant Pump System (RCPS)
K3.05 Knowledge of the effect that a loss or malfunction of the RCPS will have on the following: ICS Equipment not installed.
004 Chemical and Volume Control System (CVCS)
A4.22 Ability to manually operate and/or monitor in the control room: Boronometer chart recorder Equipment not installed.
004 Chemical and Volume Control System (CVCS)
K1.22 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: BWST Covered by KA K1.23 004 Chemical and Volume Control System (CVCS)
K1.25 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: Interface between HPI flow path and excess letdown flow path Interface does not exist.
004 Chemical and Volume Control System (CVCS)
K1.33 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: Interface between clean waste receiver tank and seal injection filters Interface does not exist 004 Chemical and Volume Control System (CVCS)
K5.31 Knowledge of the operational implications of the following concepts as they apply to the CVCS:
Purpose of flow path around boric acid storage tank Equipment not installed.
004 Chemical and Volume Control System (CVCS)
K6.12 Knowledge of the effect of a loss or malfunction on the following CVCS components: Principle of recirculation valve: (permit emergency flow even if valve is blocked by crystallized boric acid)
Equipment not provided for this reason.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 004 Chemical and Volume Control System (CVCS)
K6.19 Knowledge of the effect of a loss or malfunction on the following CVCS components: Purpose of centrifugal pump miniflows (recirculation)
Equipment not installed.
005 Residual Heat Removal System (RHRS)
K1.08 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the following systems: SWS System are not used in this manner.
005 Residual Heat Removal System (RHRS)
K1.10 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the following systems: CSS System are not used in this manner. (interface not used) 005 Residual Heat Removal System (RHRS)
K3.06 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: CSS System are not used in this manner. (interface not used) 006 Emergency Core Cooling System (ECCS)
A4.03 Ability to manually operate and/or monitor in the control room: Transfer from boron storage tank to boron injection tank Equipment not installed.
006 Emergency Core Cooling System (ECCS)
K1.04 Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems: Auxiliary spray system Equipment not related to ECCS.
006 Emergency Core Cooling System (ECCS)
K1.05 Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems: RCP seal injection and return Equipment not related to ECCS.
006 Emergency Core Cooling System (ECCS)
K1.10 Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems: Safety injection tank heating system Equipment not installed.
006 Emergency Core Cooling System (ECCS)
K4.12 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: HPI flow throttling Action not performed.
006 Emergency Core Cooling System (ECCS)
K4.19 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following:
Interlocks to storage tank makeup valve Equipment not installed.
006 Emergency Core Cooling System (ECCS)
K4.20 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following:
Automatic closure of common drain line and fill valves to accumulator Equipment not installed.
006 Emergency Core Cooling System (ECCS)
K4.22 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following:
Interlocks between RCP seal flow rate and standby HPI pump Equipment not related to ECCS.
006 Emergency Core Cooling System (ECCS)
K4.29 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: BIT recirculation Equipment not installed.
007 Pressurizer Relief Tank/Quench Tank System (PRTS)
A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Recirculating quench tank Equipment not installed.
008 Component Cooling Water System (CCWS)
A4.11 Ability to manually operate and/or monitor in the control room: CCW pump recirculation valve and its three-way control switch Equipment not installed 008 Component Cooling Water System (CCWS)
K3.02 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: CRDS Equipment does not function in this manner.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 008 Component Cooling Water System (CCWS)
K4.04 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: Weir design aspect of the surge tank Equipment not installed.
008 Component Cooling Water System (CCWS)
K4.06 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:
Auxiliary building CCWS isolation Equipment not installed 008 Component Cooling Water System (CCWS)
K4.07 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:
Operation of the CCW swing-bus power supply and its associated breakers and controls Equipment not installed 011 Pressurizer Level Control System (PZR LCS)
A2.09 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High ambient reflux boiling temperature effect or indicated PZR level Process not addressed.
011 Pressurizer Level Control System (PZR LCS)
A4.05 Ability to manually operate and/or monitor in the control room: Letdown flow controller Equipment not installed.
011 Pressurizer Level Control System (PZR LCS)
K1.05 Knowledge of the physical connections and/or cause-effect relationships between the PZR LCS and the following systems: Reactor regulating system Equipment not installed.
011 Pressurizer Level Control System (PZR LCS)
K5.06 Knowledge of the operational implications of the following concepts as they apply to the PZR LCS:
Indicated charging flow: seal flow plus actual charging flow Equipment not installed.
012 Reactor Protection System K6.07 Knowledge of the effect of a loss or malfunction of the following will have on the following: Core protection calculator Equipment not installed.
012 Reactor Protection System K6.08 Knowledge of the effect of a loss or malfunction of the following will have on the following: COLSS Equipment not installed.
012 Reactor Protection System K6.09 Knowledge of the effect of a loss or malfunction of the following will have on the following: CEAC Equipment not installed.
013 Engineered Safety Features Actuation System (ESFAS)
A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including: Feedwater header differential Equipment not installed.
013 Engineered Safety Features Actuation System (ESFAS)
K4.06 Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following:
Recirculation actuation system reset Equipment not installed.
013 Engineered Safety Features Actuation System (ESFAS)
K4.14 Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following: Upper head injection accumulator isolation Equipment not installed.
013 Engineered Safety Features Actuation System (ESFAS)
K4.17 Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following: Reason for stopping air coolers on train being tested Action not performed.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 013 Engineered Safety Features Actuation System (ESFAS)
K4.21 Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following: Reason for starting an additional service water booster pump for train not being tested and stopping the pump on train under test Equipment not installed.
013 Engineered Safety Features Actuation System (ESFAS)
K4.24 Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following: Reason for disabling of BIT so it will not function during ESF sequencer test Equipment not installed.
014 Rod Position Indication System (RPIS)
A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls including: Metroscope reed switch display Equipment not installed.
014 Rod Position Indication System (RPIS)
A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of reed switch Equipment not installed.
014 Rod Position Indication System (RPIS)
K4.01 Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Upper electrical limit Equipment not installed.
014 Rod Position Indication System (RPIS)
K4.02 Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Lower electrical limit Equipment not installed.
014 Rod Position Indication System (RPIS)
K4.04 Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Zone reference lights Equipment not installed.
014 Rod Position Indication System (RPIS)
K6.03 Knowledge of the effect of a loss or malfunction of the following will have on the following:
Metroscope Equipment not installed.
015 Nuclear Instrumentation System K1.05 Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems: ICS Equipment not installed.
015 Nuclear Instrumentation System K1.06 Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems: Reactor regulating system Equipment not installed.
015 Nuclear Instrumentation System K3.04 Knowledge of the effect that a loss or malfunction of the NIS will have on the following: ICS Equipment not installed.
015 Nuclear Instrumentation System K3.06 Knowledge of the effect that a loss or malfunction of the NIS will have on the following: Reactor regulating system Equipment not installed.
015 Nuclear Instrumentation System K4.04 Knowledge of NIS design feature(s) and/or interlock(s) which provide for the following: Slow response time of SPNDs Equipment not installed.
022 Containment Cooling System (CCS)
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the CCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor vibration Equipment not installed.
022 Containment Cooling System (CCS)
K4.01 Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following: Cooling of containment penetrations Equipment not installed.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 026 Containment Spray System (CSS)
A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level Operation during SI recirc not addressed.
026 Containment Spray System (CSS)
A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Reflux boiling pressure spike when first going on recirculation Operation during SI recirc not addressed.
026 Containment Spray System (CSS)
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic recirculation transfer Equipment not installed.
026 Containment Spray System (CSS)
A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Increase in spray flow following swapover, because of higher pump suction pressure Operation during SI recirc not addressed.
026 Containment Spray System (CSS)
A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding), or sump level below cutoff (interlock) limit Containment spray is not used when ECCS is aligned for recirculation.
026 Containment Spray System (CSS)
A4.02 Ability to manually operate and/or monitor in the control room: The remote location and use of spool pieces and other equipment to set up portable recirculation pump for additive tank, including power supply Action not required.
026 Containment Spray System (CSS)
K3.02 Knowledge of the effect that a loss or malfunction of the CSS will have on the following: Recirculation spray system Equipment not installed.
026 Containment Spray System (CSS)
K4.05 Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
Prevention of material from clogging nozzles during recirculation Containment spray is not used when ECCS is aligned for recirculation.
026 Containment Spray System (CSS)
K4.07 Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
Adequate level in containment sump for suction (interlock)
Containment spray is not used when ECCS is aligned for recirculation.
026 Containment Spray System (CSS)
K4.08 Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm)
Containment spray is not used when ECCS is aligned for recirculation.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 026 Containment Spray System (CSS)
K4.09 Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover)
Containment spray is not used when ECCS is aligned for recirculation.
027 Containment Iodine Removal System (CIRS)
K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CIRS and the following systems: CSS System not related for operation.
029 Containment Purge System (CPS)
K1.05 Knowledge of the physical connections and/or cause-effect relationships between the Containment Purge System and the following systems: Containment air cleanup and recirculation system Equipment not installed.
033 Spent Fuel Pool Cooling System (SFPCS)
A3.01 Ability to monitor automatic operation of the Spent Fuel Pool Cooling System, including: Temperature control valves Equipment not installed.
033 Spent Fuel Pool Cooling System (SFPCS)
K1.02 Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems:
RHRS Equipment not related in this manner.
033 Spent Fuel Pool Cooling System (SFPCS)
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems:
SIS Equipment not related in this manner.
034 Fuel Handling Equipment System (FHES)
K1.05 Knowledge of the physical connections and/or cause-effect relationships between the Fuel Handling System and the following systems:
Shutdown monitor Equipment not installed.
035 Steam Generator System (S/GS)
A3.02 Ability to monitor automatic operation of the S/G, including: MAD valves Equipment not installed.
039 Main and Reheat Steam System (MRSS)
A4.03 Ability to manually operate and/or monitor in the control room: MFW pump turbines Equipment not installed.
(motor driven MFW pumps) 039 Main and Reheat Steam System (MRSS)
K3.04 Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: MFW pumps Equipment is not related to MRSS. (motor driven MFW pumps) 041 Steam Dump System (SDS) and Turbine Bypass Control A4.01 Ability to manually operate and/or monitor in the control room: ICS voltage inverter Equipment not installed.
041 Steam Dump System (SDS) and Turbine Bypass Control A4.07 Ability to manually operate and/or monitor in the control room: Remote gagging of stuck open-relief valves Actions not provided for.
041 Steam Dump System (SDS) and Turbine Bypass Control K2.01 Knowledge of bus power supplies to the following:
ICS, normal and alternate power supply Equipment not installed.
041 Steam Dump System (SDS) and Turbine Bypass Control K2.02 Knowledge of bus power supplies to the following:
ICS inverter breakers Equipment not installed.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 041 Steam Dump System (SDS) and Turbine Bypass Control K4.01 Knowledge of SDS design feature(s) and/or interlock(s) which provide for the following:
RRG/ICS system Equipment not installed.
041 Steam Dump System (SDS) and Turbine Bypass Control K4.08 Knowledge of SDS design feature(s) and/or interlock(s) which provide for the following: Control rod index Equipment not installed.
041 Steam Dump System (SDS) and Turbine Bypass Control K4.15 Knowledge of SDS design feature(s) and/or interlock(s) which provide for the following:
"Measured variable" readings on ICS hand-automatic stations and required action if reading is out of the acceptable band Equipment not installed.
045 Main Turbine Generator (MT/G)
System A2.13 Ability to (a) predict the impacts of the following malfunctions or operations on the MT/G System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Opening of the steam dumps at low pressure Action not provided for.
045 Main Turbine Generator (MT/G)
System K4.08 Knowledge of MT/G System design feature(s) and/or interlock(s) which provide for the following:
The reactor bailey station and reactor diamond station in integrated control circuitry Equipment not installed.
045 Main Turbine Generator (MT/G)
System K4.44 Knowledge of MT/G System design feature(s) and/or interlock(s) which provide for the following:Impulse pressure mode control of steam dumps Not directly controlled covered by previous KA 045 Main Turbine Generator (MT/G)
System K4.45 Knowledge of MT/G System design feature(s) and/or interlock(s) which provide for the following:
Operation of low-pressure steam dump to prevent T/G overspeed Equipment not installed.
059 Main Feedwater (MFW) System A1.07 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW System controls including: Feed Pump speed, including normal control speed for ICS Variable speed MFW pumps not installed.
059 Main Feedwater (MFW) System A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the MFW System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Tripping of MFW pump turbine Turbine-driven MFW pumps not installed.
059 Main Feedwater (MFW) System A3.04 Ability to monitor automatic operation of the MFW System, including: Turbine driven feed pump Turbine-driven MFW pumps not installed.
059 Main Feedwater (MFW) System A3.07 Ability to monitor automatic operation of the MFW System, including: ICS Equipment not installed.
059 Main Feedwater (MFW) System A4.01 Ability to manually operate and/or monitor in the control room: MFW turbine trip indication Turbine-driven MFW pumps not installed.
059 Main Feedwater (MFW) System A4.10 Ability to manually operate and/or monitor in the control room: ICS Equipment not installed.
059 Main Feedwater (MFW) System K1.07 Knowledge of the physical connections and/or cause-effect relationships between the MFW System and the following systems: ICS Equipment not installed.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 059 Main Feedwater (MFW) System K4.05 Knowledge of MFW System design feature(s) and/or interlock(s) which provide for the following:
Control of speed of MFW pump turbine Turbine-driven MFW pumps not installed.
059 Main Feedwater (MFW) System K4.13 Knowledge of MFW System design feature(s) and/or interlock(s) which provide for the following:
Feedwater fill for S/G upon loss of RCPs Equipment does not function in this manner.
059 Main Feedwater (MFW) System K4.17 Knowledge of MFW System design feature(s) and/or interlock(s) which provide for the following:
Increased feedwater flow following a reactor trip Equipment does not function in this manner.
059 Main Feedwater (MFW) System K4.18 Knowledge of MFW System design feature(s) and/or interlock(s) which provide for the following:
Automatic feedwater reduction on plant trip Equipment does not function in this manner.
059 Main Feedwater (MFW) System K5.12 Knowledge of the operational implications of the following concepts as they apply to the MFW System: Increased MFW pump discharge with increased turbine speed Turbine-driven MFW pumps not installed.
059 Main Feedwater (MFW) System K6.09 Knowledge of the effect of a loss or malfunction of the following will have on the MFW System components: MFW pump speed and flow regulating valves (reason for adjusting position of both)
Variable speed MFW pumps not installed.
061 Auxiliary /
System A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Automatic control malfunction Equipment not installed.
061 Auxiliary /
System A2.09 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Total loss of feedwater RO & SRO KA values yet to be determined.
061 Auxiliary /
System A3.03 Ability to monitor automatic operation of the AFW System, including: AFW S/G level control on automatic start Equipment not installed.
061 Auxiliary /
System A3.04 Ability to monitor automatic operation of the AFW System, including: Automatic AFW isolation Equipment not installed.
061 Auxiliary /
System K1.10 Knowledge of the physical connections and/or cause-effect relationships between the AFW System and the following systems: Diesel fuel oil Equipment not installed.
061 Auxiliary /
System K2.03 Knowledge of bus power supplies to the following:
AFW diesel driven pump Equipment not installed.
061 Auxiliary /
System K4.05 Knowledge of AFW System design feature(s) and/or interlock(s) which provide for the following:
Prevention of MFW swapover to AFW suction pressure is low Equipment does not function in this manner.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 061 Auxiliary /
System K4.11 Knowledge of AFW System design feature(s) and/or interlock(s) which provide for the following:
Automatic level control Equipment not installed.
061 Auxiliary /
System K4.14 Knowledge of AFW System design feature(s) and/or interlock(s) which provide for the following:
AFW automatic isolation Equipment not installed.
062 A.C. Electrical Distribution System A4.02 Ability to manually operate and/or monitor in the control room: Remote racking in and out of breakers Equipment not installed.
062 A.C. Electrical Distribution System K4.06 Knowledge of A.C. Distribution System design feature(s) and/or interlock(s) which provide for the following: One-line diagram of 6.9kV distribution, including sources of normal and alternative Equipment not installed.
064 Emergency Diesel Generator (ED/G) System A2.13 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Consequences of opening auxiliary feeder bus (ED/G sub supply)
Equipment not installed.
064 Emergency Diesel Generator (ED/G) System A2.17 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Consequences of not shedding loads during nonoperability test Equipment not installed.
064 Emergency Diesel Generator (ED/G) System A2.21 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Significance and interpretation of opening of ring bus during test Equipment not installed.
064 Emergency Diesel Generator (ED/G) System A3.08 Ability to monitor automatic operation of the ED/G System, including: Consequences of automatic transfer to automatic position after the ED/G is stopped Equipment not installed.
064 Emergency Diesel Generator (ED/G) System A3.09 Ability to monitor automatic operation of the ED/G System, including: Functions (modes) of automatic transfer switch (to a startup bank)
Equipment not installed.
064 Emergency Diesel Generator (ED/G) System A4.04 Ability to manually operate and/or monitor in the control room: Remote operation of the air compressor switch (different modes)
Equipment not installed.
064 Emergency Diesel Generator (ED/G) System A4.08 Ability to manually operate and/or monitor in the control room: Opening of the ring bus Equipment not installed.
071 Waste Gas Disposal System (WGDS)
A3.01 Ability to monitor automatic operation of the Waste Gas Disposal System, including: HRPS Equipment is not related in this manner.
072 Area Radiation Monitoring (ARM)
System A3.01 Ability to monitor automatic operation of the ARM system, including: Changes in ventilation alignment Equipment does not function in this manner.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 072 Area Radiation Monitoring (ARM)
System K1.01 Knowledge of the physical connections and/or cause-effect relationships between the ARM system and the following systems: Plant ventilation systems Equipment does not function in this manner.
072 Area Radiation Monitoring (ARM)
System K1.02 Knowledge of the physical connections and/or cause-effect relationships between the ARM system and the following systems: Containment isolation Equipment does not function in this manner.
072 Area Radiation Monitoring (ARM)
System K1.03 Knowledge of the physical connections and/or cause-effect relationships between the ARM system and the following systems: Fuel building isolation Equipment does not function in this manner.
072 Area Radiation Monitoring (ARM)
System K1.04 Knowledge of the physical connections and/or cause-effect relationships between the ARM system and the following systems: Control room ventilation Equipment does not function in this manner.
072 Area Radiation Monitoring (ARM)
System K1.05 Knowledge of the physical connections and/or cause-effect relationships between the ARM system and the following systems: MRSS Equipment does not function in this manner.
072 Area Radiation Monitoring (ARM)
System K3.01 Knowledge of the effect that a loss or malfunction of the ARM system will have on the following:
Containment ventilation isolation Equipment does not function in this manner.
072 Area Radiation Monitoring (ARM)
System K4.01 Knowledge of ARM system design feature(s) and/or interlock(s) which provide for the following:
Containment ventilation isolation Equipment does not function in this manner.
072 Area Radiation Monitoring (ARM)
System K4.02 Knowledge of ARM system design feature(s) and/or interlock(s) which provide for the following:
Fuel building isolation Equipment does not function in this manner.
073 Process Radiation Monitoring (PRM) System A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Calibration drift Not addressed by Operations.
073 Process Radiation Monitoring (PRM) System K4.02 Knowledge of PRM System design feature(s) and/or interlock(s) which provide for the following:
Letdown isolation on high-RCS activity Equipment does not function in this manner.
075 Circulating Water System K3.07 Knowledge of the effect that a loss or malfunction of the Circulating Water System will have on the following: ESFAS Equipment not related in this manner.
076 Service Water System (SWS)
A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures Equipment not installed.
076 Service Water System (SWS)
K1.07 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: Secondary closed cooling water Equipment not installed.
076 Service Water System (SWS)
K1.08 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: RHR system Equipment is not related in this manner.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 076 Service Water System (SWS)
K1.09 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: Reactor building closed cooling water Equipment not installed.
076 Service Water System (SWS)
K1.21 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: Auxiliary backup SWS Equipment not installed.
076 Service Water System (SWS)
K2.04 Knowledge of bus power supplies to the following:
Reactor building closed cooling water Equipment not installed.
076 Service Water System (SWS)
K3.02 Knowledge of the effect that a loss or malfunction of the SWS will have on the following: Secondary closed cooling water Equipment not installed.
076 Service Water System (SWS)
K3.03 Knowledge of the effect that a loss or malfunction of the SWS will have on the following: Reactor building closed cooling water Equipment not installed.
076 Service Water System (SWS)
K3.08 Knowledge of the effect that a loss or malfunction of the SWS will have on the following: Radioactive liquid waste discharges System does not function in this manner.
076 Service Water System (SWS)
K4.01 Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following:
Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return valves Equipment not installed.
078 Instrument Air System (IAS)
K1.01 Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Sensor air Equipment not installed. (IA is sensor air) 078 Instrument Air System (IAS)
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Containment air Equipment not installed.
078 Instrument Air System (IAS)
K2.02 Knowledge of bus power supplies to the following:
Emergency air compressor Equipment not installed.
078 Instrument Air System (IAS)
K3.01 Knowledge of the effect that a loss or malfunction of the IAS will have on the following: Containment air system Equipment not installed.
086 Fire Protection System (FPS)
A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fire Protection System controls including: Fire water storage tank level Equipment not installed.
(River is water source) 086 Fire Protection System (FPS)
A4.04 Ability to manually operate and/or monitor in the control room: Fire water storage tank makeup pumps Equipment not installed.
(River is water source) 086 Fire Protection System (FPS)
K1.02 Knowledge of the physical connections and/or cause-effect relationships between the Fire Protection System and the following systems: Raw service water Equipment not related in this manner. (Lake is water source) 086 Fire Protection System (FPS)
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the Fire Protection System and the following systems:
AFW System Equipment not related in this manner.
103 Containment System A4.07 Ability to manually operate and/or monitor in the control room: Use of the air lock rate test panel Action not performed by Operators.
103 Containment System A4.09 Ability to manually operate and/or monitor in the control room: Containment vacuum system Equipment not installed.
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Draft Revision 9 22 of 27 Tier 2 - Systems System Information K/A #
K/A Statement Basis for suppression 103 Containment System K1.06 Knowledge of the physical connections and/or cause-effect relationships between the Containment System and the following systems:
Subsurface drain system Equipment not installed.
103 Containment System K1.07 Knowledge of the physical connections and/or cause-effect relationships between the Containment System and the following systems:
Containment vacuum system Equipment not installed.
103 Containment System K4.02 Knowledge of Containment System design feature(s) and/or interlock(s) which provide for the following: Containment penetration cooling Equipment not installed.
103 Containment System K4.03 Knowledge of Containment System design feature(s) and/or interlock(s) which provide for the following: Prevention of radiation streaming Design characteristic not controlled by operator.