ML120470445
| ML120470445 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/18/2012 |
| From: | Division of Reactor Safety IV |
| To: | Wolf Creek |
| References | |
| 50-482/12-301 | |
| Download: ML120470445 (5) | |
Text
FINAL 7 for NRC 1 of 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Wolf Creek Date of Examination: January 2012 Examination Level: RO SRO Operating Test Number:
Administrative Topic (see Note)
Type Code*
Describe activity to be performed A1 Conduct of Operations D, R Review completed boration requirement calculation for a downpower evolution.
2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management (CFR 41.1 / 43.6 /
45.6) (SRO: 4.6)
A2 Conduct of Operations D, R Using a supplied data (STS SF-002, Core Axial Flux Difference), complete and evaluate the acceptance criteria.
2.1.20 Ability to interpret and execute procedure step. (CFR 41.10 / 43.5 / 45.12) (SRO: 4.6) 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR 41.10
/ 43.6 / 45.6) (SRO: 4.3)
A3 Equipment Control N, R Evaluate plant conditions and determine if a mode change can occur.
2.2.35 Ability to determine Technical Specification Mode of Operation (CFR: 41.7 / 41.10 / 43.2 / 45.13) (SRO: 4.5) 2.2.40 Ability to apply Technical Specifications for a system.
(CFR: 41.10 / 43.2 / 43.5 / 45.3) (SRO: 4.7)
A4 Radiation Control N, R Evaluate an Emergency Exposure Authorization.
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR 41.12 / 43.4 / 45.10) (SRO: 3.7)
A5 Emergency Procedures/Plan N, S Complete an Emergency Notification.
2.4.41 Knowledge of the emergency action level thresholds and classification. (CFR 41.10 / 43.5 / 45.11) (SRO: 4.6)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
FINAL 6 for NRC 1 of 4 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Wolf Creek Date of Examination: January 2012 Examination Level: RO SRO Operating Test Number:
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Alternate Success Path JPMs are Bolded.
System / JPM Title Type Code*
Safety Function S1 Perform a manual makeup to the Volume Control Tank (VCT).
004 CVCS A4 Ability to manually operate and/or monitor in the Control Room: (CFR 41.7 / 45.5 to 45.8)
A4.12 Boration/Dilution batch control (SRO: 3.3)
A4.13 VCT level control and pressure control (SRO: 2.9)
A4.15 Boron concentration (SRO: 3.7)
D, S 2
S2 Depressurize the RCS during Natural Circulation conditions.
010 Pressurizer Pressure Control System (PZR PCS)
A1 Ability to predict and /or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: (CFR 41.5 / 45.5)
A1.07 RCS pressure (SRO: 3.7)
A4 Ability to manually operate and / or monitor in the Control Room: (CFR 41.7 / 45.5 to 45.8)
A4.01 PZR spray valve (SRO: 3.5)
PSA - Top Risk Significant System by PSA (BB - Reactor Coolant System)
N, S, L 3
S3 Transfer steam load from Turbine to the Steam Dumps.
041 Steam Dump System and Turbine Bypass Control (SDS)
A3 Ability to monitor automatic operation of the SDS, including: (CFR 41.7 / 45.5):
A3.02 RCS pressure, RCS temperature, and reactor power (SRO: 3.4)
A3.03 Steam flow (SRO: 2.8)
A4 Ability to manually operate and/ or monitor in the Control Room: (CFR 41.7 / 45.5 to 45.8)
A4.08 Steam dump valves (SRO: 3.1)
N, S 4S
FINAL 6 for NRC 2 of 4 S4 Respond to high RCP seal flow.
003 Reactor Coolant Pumps (RCP)
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPs; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR 41.5 / 43.5 / 45.3 / 45.13)
A2.01 Problems with RCP seals, especially rates of seal leak-off (SRO:
3.9)
A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP (SRO: 3.9)
PSA - Top Risk Significant System by PSA (BB - Reactor Coolant System)
N, A, S 4P S5 Perform EMG E-0, Attachment F Automatic Signal Verification.
103 Containment System A2 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR 41.5 / 43.5 /
45.3 / 45.13)
A2.03 Phase A and Phase B isolation (SRO: 3.8)
PSA - Top Risk Significant System by PSA (SA - Engineered Safeguards Features Actuation System)
M, A, S, L 5
S6 Align Safeguards Bus to Alternate Power Source.
062 A.C. Electrical Distribution A2 Ability to (a) predict the impacts of the following malfunctions or operations on the AC distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR 41.5 / 43.5 /
45.3 / 45.13)
A2.05 Methods for energizing a dead bus (SRO: 3.3) 055 Loss of Offsite and Onsite Power (Station Blackout)
EA2 Ability to determine or interpret the following as they apply to a Station Blackout (CFR 43.5 / 45.13)
EA2.03 Actions necessary to restore power (SRO: 4.7)
PSA - Station Blackout - Core Damage Frequency by Initiating Event
& Event tree M, A, S, L 6
FINAL 6 for NRC 3 of 4 S7 Determine IR Instrumentation Malfunction.
015 Nuclear Instrumentation System (NIS)
K6. Knowledge of the effect of a loss or malfunction on the following will have on the NIS: (CFR 41.7 / 45.7)
K6.02 Discriminator / compensation circuits (SRO: 2.9)
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR 41.5 / 43.5 / 45.3 / 45.13)
A2.02 Faulty or erratic operation of detectors or compensating components (SRO: 3.5)
LER 2009-011, Intermediate Range detector NI36 inoperable N, A, L, S 7
- h. NA In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1 Start a Rod Drive Motor Generator Set.
001 Control Rod Drive System (CRDM) 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. (CFR 41.5 / 41.10 / 43.5 / 45.1) (SRO: 4.4)
LER 2003-001, Manipulation of component outside of procedural guidance causes reactor trip D, R 1
P2 Align Auxiliary Feedwater alternate suction from Fire Protection Standpipe.
061 Auxiliary Feedwater System (AFW)
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR 41.5 / 43.5 / 45.3 / 45.13)
A2.04 Pump failure or improper operation (SRO: 3.8)
PSA - Top Risk Significant System by PSA (AL - Auxiliary Feedwater System)
D, L, E 4S
FINAL 6 for NRC 4 of 4 P3 Increasing Spent Fuel Pool level.
033 Spent Fuel Pool Cooling System (SFPCS)
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR 41.5 / 43.5 /
45.3 / 45.13)
A2.03 Abnormal spent fuel pool water level or loss of water level (SRO:
3.5 N, A, R 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1