ML14336A368

2014-11 Final Outlines

ML14336A368
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/21/2014
From:	Vincent Gaddy Operations Branch IV
To:	Entergy Operations
laura hurley
References
50-313/14-11, ES-401, ES-401-2 50-313/OL-14
Download: ML14336A368 (34)

Text

ES-301 Administrative Topics Outline Revision 0 Form ES-301-1 Facility: ANO-1 Date of Examination: 11-17-2014 Examination Level: RO SRO LI Operating Test Number: 2014-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Estimate SEP Time to Boil Al 2.1.25 NIR Ability to interpret reference materials, such as (Imp 3.9) graphs, curves, tables, etc.

Al JPM-RO-ADMIN-SFPTTB Conduct of Operations Operate the Plant Computer A2. 2.1.19 D/S Ability to use plant computers to evaluate system (Imp 3.9) or component status.

Al JPM-NRC-ADMIN-PMS3 Equipment Control Perform DG1 Operability Test complete A3. 2.2.12 N/R evaluation of pump based on surveillance results Knowledge of surveillance procedures (Imp 3.7)

Al JPM-RO-SURV3 Radiation Control Review RWP and Survey Map to calculate maximum stay time.

A4. 2.3.7 M/R Ability to comply with radiation work permit (Imp 3.5) requirements during normal or abnormal conditions A1JPM-RO-DOSE-SVY2O14 Emergency Procedures/Plan N/A N/A NCTE A: ;terrs 5 tota are ered for SOs RO appoants rere Oy 4 tems tey are retaRng o iy t a a3nn strative topi s wfler a 5 are equ ea Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 (1) for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1) (3)

(P)revious 2 exams ( 1; randomly selected) (0)

ES-301 Administrative Topics Outline Revision 0 Form ES-301-1 Facility: ANO-1 Date of Examination: 1 1-17-2014 Examination Level: RO SRO Operating Test Number: 2014-1 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations Door Breach requirements, determine need for a firewatch.

A5. 2.1.8 N/R Ability to coordinate personnel activities outside (Imp 4.1) the control room.

Al JPM-SRO-FIREWATCH Conduct of Operations Perform responsibilities & authorities of the SM as required, actions to take on OOS Chemistry Report A6. 2.1.34 DIR Knowledge of primary and secondary plant (Imp 35) chemistry limits Al JPM-SRO-CHEM 1 Equipment Control Utilize procedure deviation A7. 2.2.44 D/R A1JPM-SRO-PROC1 (Imp 4.4)

Radiation Control Potassium Iodine administration determination A8. 2.3 14 M/R Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or (Imp 3 8) emergency conditions or activities.

A1JPM-S RO-KJ Emergency Procedures/Plan Classify an Emergency Event Knowiedge of the emergency action level A9 2 441 N/S thresholds and classifications

( 4 A1JPMSRO EALI 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 (2) for SROs & RO retakes)

N)ew or (Modified from bank ( (3)

P) 2 e arns ra )m se te (0)

ES-301 Control Roomlin-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 1 Date of Examination: 11-17-2014 Exam Level: RO SRO-l SRO-U Operating Test No.: 2014-1 Control Room Systems© (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function a.

A1JPM-RO-A0P37 Respond to Continuous Rod 1 Withdrawal AID/LIP/S 001 AA1 .05 (RO 4.3/SRO 4.2) Reactivity Control RO/SRO-UISRO-l b.

A1JPM-RO-PZR01 Equalize Boron Concentrations between the RCS and the PZR A/D/S Reactor 010 A4.02 (RO 3.6/SRO 34) Pressure ROISRO-l Control C.

2 A1JPM-RO-EOP11 Perform Actions Required for an ESAS Actuation (Shift to RB Sump Suction) Reactor Coolant D/EN/L/S System 006 A4.02 (RO 4.0/SRO 3.8)

Inventory ROtS RO-l Control d.

A1JPM-RO-EOPO9 Energize Bus A2 from A4 in a Degraded Power Condition 6 A/D/E N/S 062 Al .01 (RO 34/SRO 3,8) Electrical ROISRO-l AIJPM-RO-A0F27 Respond to Inadvertent ESAS Actuation in A206 (RO 37/SRO 4.0) Contanment ROtS RO-UIS RO-l Integrity A1JPM-RO-E0P24 Reactor Tripped, check all NNI power available (Loss of NNI-X) 7 AID/S B&W APE A02 AAI .3 (RO 3,4/SRO 3.6) Instrumentation RO!SRO-l

g.

A1JPM-RO-A0P28 Respond to Simultaneous Loss of 4 Seal Injection and Seal Cooling N/S Heat Removal 003 A4.08 (RO 3.2ISRO 2.9) From Reactor RO Core (Primary) h.

A1JPM-RO-A0P29 Respond to Loss of Lake 8 Dardanelle Reservoir N/S Plant Service 075 A2.02 (RO 2.5/SRO 2.7)

Systems ROISRO-I In-Plant Systems@ (3 for RO) (3 for SRO-l) (3 or 2 for SRO-U) 4 A1JPM-RO-EFW1O Actions for swapping suction from L41B to T41 Heat Removal A/D/L!E/P/R From Reactor 061 Al .04 (RO 3.9/SRO 3.9)

Core ROISRO-UISRO-I (Secondary)

A1JPM-RO-EDO2O Place Battery Charger D-04A in service 6 D

058 AA1.03 (RO 3.l/SRO 3.3) Electrical ROIS RO-U!S RO-I k.

A1JPM-RO-LRWO2 Commence ThVMT T-16A Release 9 068 A302(RO 3.6/SRO 36) A/N/R Reactivity RO/SRO-U /SRO-I Release All RO and SRO-i control room (and n-plant systems must be different and serve different safety

!unctiins at f SRCJ. SvSte9s i.s seie nf-fecnt afy .n.onc 9 la ztes i0r .

S

• 1 Type Codes Criteria for RO I SRO-i / CR0-U (A$ternate oats 4-6 (6) / 4-6 (6) / 2-3 (3)

(c:ontrol room (D)irect from bank 9 (7) / 8(7) / 4 (3)

(E)mergency or abnormal n-plant 1 (1) / 1(1) / a 1 (1)

(EN)gineered safety feature (3) / (3) I al (1) (control room system)

(L)ow-Power / Shutdown 1 (3) I a 1(3> / a 1 (2)

(N)ew or (M)odified from bank including 1 (A) a 2 (4) / 2(4) / a 1 (2)

(P)revious 2 exams 3 (2) / 3(2) / 2 (1) (randomly selected)

(R)CA al (2)/a1(2)/1 (2) f65irnuiato