ML112430546

Wat 2011-08 Retake Draft Outlines

ML112430546
Person / Time
Site:	Waterford
Issue date:	08/08/2011
From:	Kelly Clayton Operations Branch IV
To:	Entergy Operations
References
50-382/11-302, ES-301-1
Download: ML112430546 (3)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: WATERFORD 3 Date of Examination: August 12, 2011 Examination Level: RO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

2.1.19, Ability to use plant computers to evaluate A1 S, M system or component status.

Conduct of Operations Perform a Containment pressure calculation in accordance with OP-903-001, Technical Specification Surveillance Logs, Attachment 11.15.

K/A Importance:

3.9 A2 R, M 2.1.25, Ability to interpret reference materials, such as Conduct of Operations graphs, curves, tables, etc.

Determine the minimum time allowed to place K/A Importance: Shutdown Cooling in service in accordance with OP-3.9 902-009, Standard Appendices.

A3 S, N 2.2.12, Knowledge of surveillance procedures Equipment Control Complete assessment of heated and Unheated thermocouple in accordance with OP-903-013, K/A Importance: Monthly Channel Checks, Attachment 10.3.

3.7 A4 R, N 2.3.11, Ability to control radiation releases.

Radiation Control Complete release permit for a Waste Condensate Tank release.

K/A Importance:

3.8 Emergency Plan Not selected 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.

• 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)

Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: WATERFORD 3 Date of Examination: August 12, 2011 Exam Level Reactor Operator Operating Test No.: NRC Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Type Safety System / JPM Title Code* Function S1 004 Chemical and Volume Control System, Perform OP-903-096, Boron D, L, S 1 Flow Rate Verification.

A4.07 Boration/Dilution RO - 3.9 S2 006 Emergency Core Cooling System, Evaluate the need and establish D, L, P, S 2 simultaneous hot and cold leg injection in accordance with OP-902-002, Loss of Coolant Accident Recovery.

A4.07, ECCS pumps and valves RO - 4.4 S3 009 Small Break LOCA, Test RC-1014, 1015, and RC-1017 in D, L, S 3 accordance with OP-903-098, RCS Vent System Functional Check and Valve Lineup Verification.

EA1.17 Pressurizer Relief Tank RO - 3.4 S4 059 Main Feedwater System; Secure Main Feedwater Pump B at power A, M, S 4-S in accordance with OP-003-033, Main Feedwater.

Fault: Main Feedwater Pump B will develop high vibration during shutdown sequence; manual action will be required to secure Main Feedwater Pump B.

A2.07 Tripping of MFW pump turbine RO - 3.0 S5 003 Reactor Coolant Pump System, Start Reactor Coolant Pump 1A in A, D, L, S 4-P accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: RCP 1A will develop a seal leak and high vibration, requiring action to secure pump.

A4.06 RCP parameters RO - 2.9 S6 064 Emergency Diesel Generator (ED/G) System; Parallel Emergency D, L, S 6 Diesel Generator A across Bus Tie breaker 3A -2A with a SIAS signal actuated in accordance with OP-902-009, Standard Appendices.

A4.07 Transfer ED/G (with load) to grid RO - 3.4 S7. 060 Accidental Gaseous Waste Release; Restore Control Room D, S 8 ventilation following a Control Room Isolation Signal in accordance with OP-003-014, Control Room Heating and Ventilation.

AA1.02 Ventilation system RO - 2.9 S8. 068 Liquid Radwaste System; Discharge WCT A to the Circulating Water A, D, P, S 9 System in accordance with OP-007-004, Liquid Waste Management System Fault: Upon initiation of flow, controller fails in raise, exceeding maximum flow allowed, requiring the operator to manually close the isolation valves.

A4.03 Stoppage of release if limits exceeded RO - 3.9 1 NRC 2011 Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P1 005 Shutdown Cooling System A, L, M, R 4-P Secure Shutdown Cooling Purification in accordance with OP-009-005, Shutdown Cooling.

Fault: During the manipulations, a reach rod valve will fail, requiring corrective actions.

A2.04 RHR valve malfunction RO - 2.9 P2 062 A.C. Electrical Distribution A, D, P 6 Transfer SUPS 014AB from Alternate to Normal AC Power in accordance with OP-006-005, Inverters and Distribution.

Fault: After alignment, voltage will not be indicated on SUPS 014 AB inverter.

A3.04 Operation of inverter RO - 2.7, SRO - 2.9 P3 061 Emergency Feedwater System; Complete OP-903-001, Technical E, N, R 4-S Specification Surveillance Logs, Attachment 11.12, Emergency Feedwater Steam Binding Corrective Actions.

A2.06 Back leakage of MFW RO - 2.7

@ 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 4-6 / 4-6 / 2-3 5 (C)ontrol room 0 (D)irect from bank 9/8/4 8 (E)mergency or abnormal in-plant 1/1/1 1 (EN)gineered safety feature - / - / 1 (control room system) -

(L)ow-Power / Shutdown 1/1/1 6 (N)ew or (M)odified from bank including 1(A) 2/2/1 3 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 3 (R)CA 1/1/1 2 (S)imulator 8 2 NRC 2011 Revision 0