ML112430546
| 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 Revision 0 Facility:
WATERFORD 3 Date of Examination:
August 12, 2011 Examination Level:
RO Operating Test Number:
1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed A1 Conduct of Operations K/A Importance:
3.9 S, M 2.1.19, Ability to use plant computers to evaluate system or component status.
Perform a Containment pressure calculation in accordance with OP-903-001, Technical Specification Surveillance Logs, Attachment 11.15.
A2 Conduct of Operations K/A Importance:
3.9 R, M 2.1.25, Ability to interpret reference materials, such as graphs, curves, tables, etc.
Determine the minimum time allowed to place Shutdown Cooling in service in accordance with OP-902-009, Standard Appendices.
A3 Equipment Control K/A Importance:
3.7 S, N 2.2.12, Knowledge of surveillance procedures Complete assessment of heated and Unheated thermocouple in accordance with OP-903-013, Monthly Channel Checks, Attachment 10.3.
A4 Radiation Control K/A Importance:
3.8 R, N 2.3.11, Ability to control radiation releases.
Complete release permit for a Waste Condensate Tank release.
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)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 1
NRC 2011 Revision 0 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)
System / JPM Title Type Code*
Safety Function S1 004 Chemical and Volume Control System, Perform OP-903-096, Boron Flow Rate Verification.
A4.07 Boration/Dilution RO - 3.9 D, L, S 1
S2 006 Emergency Core Cooling System, Evaluate the need and establish 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 D, L, P, S 2
S3 009 Small Break LOCA, Test RC-1014, 1015, and RC-1017 in accordance with OP-903-098, RCS Vent System Functional Check and Valve Lineup Verification.
EA1.17 Pressurizer Relief Tank RO - 3.4 D, L, S 3
S4 059 Main Feedwater System; Secure Main Feedwater Pump B at power 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 A, M, S 4 - S S5 003 Reactor Coolant Pump System, Start Reactor Coolant Pump 1A in 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 A, D, L, S 4 - P S6 064 Emergency Diesel Generator (ED/G) System; Parallel Emergency 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 D, L, S 6
S7.
060 Accidental Gaseous Waste Release; Restore Control Room 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 D, S 8
S8.
068 Liquid Radwaste System; Discharge WCT A to the Circulating Water 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 A, D, P, S 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 2
NRC 2011 Revision 0 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
P1 005 Shutdown Cooling System 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 A, L, M, R 4 - P P2 062 A.C. Electrical Distribution 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 A, D, P 6
P3 061 Emergency Feedwater System; Complete OP-903-001, Technical Specification Surveillance Logs, Attachment 11.12, Emergency Feedwater Steam Binding Corrective Actions.
A2.06 Back leakage of MFW RO - 2.7 E, N, R 4 - S 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