ML120470482

2012-01-Draft Outlines

ML120470482
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: ML120470482 (6)

Text

DRAFT 4 for NRC 1 of 2 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 Authorization Exposure (EPF 06-013-02) for correctness and approval.

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 In the simulator setting, perform an Emergency Plan classification, completing an Emergency Notification form (EPF 06-007-01) within fifteen minutes.

Time Critical 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.

DRAFT 4 for NRC 2 of 2

• 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)

DRAFT 4 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 JPM's are Bolded. System / JPM Title Type Code*

Safety Function S1 004 CVCS: Perform manual makeup to the Volume Control Tank 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 010 Pressurizer Pressure Control System (PZR PCS): Depressurize the RCS to 1920 psig 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 041 Steam Dump System and Turbine Bypass Control (SDS): move steam load from Turbine to steam dumps 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 DRAFT 4 for NRC 2 of 4 S4 003 Reactor Coolant Pumps (RCP): RCP seal injection high: seal injection too high when at 100%, must trip reactor (first) and then trip RCP and close valve etc. 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 103 Containment System: Phase A not completed - must "make it so" 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 062 A.C. Electrical Distribution: align alternate power to bus 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 DRAFT 4 for NRC 3 of 4 S7 015 Nuclear Instrumentation System (NIS): IR under compensation, correct energize SR NI's 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 001 Control Rod Drive System (CRDM): Start a rod drive motor generator set 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 061 Auxiliary Feedwater System (AFW): align AFW alternate suction from fire protection standpipe 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 DRAFT 4 for NRC 4 of 4 P3 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