ML17193A965

Sequoyah (Retake) 2016-302 Exam Administrative Items - Delay Release 2 Yrs

ML17193A965
Person / Time
Site:	Sequoyah
Issue date:	07/12/2017
From:	NRC/RGN-II
To:
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Download: ML17193A965 (1)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Sequoyah Unit 1 & 2 Date of Examination:

7/25/2016 Examination Level:

RO Operating Test Number: 2016-302 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R, M Determine Maintenance of Active License Status. G 2.1.4 (3.3) Conduct of Operations R, D Perform a Reactivity Balance Calculation from 25% to 100% using 0-SO-62-7, Appendix E

. G 2.1.25 (3.9) Equipment Control S , M Perform a System Operability Checklist when the TD AFW pump is being removed from service and determine the required protected train tag placement.

G 2.2.1 4 (3.9) Radiation Control N/A Not examined Emergency Plan S , M Complete a NRC Event Notification Worksheet.

G 2.4.39 (3.9) NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from

A.1.a Given a situation with four different Reactor Operators that are not currently on shift, the Examinee will assess the work schedules for four different operators and using OPDP 10 License Status Maintenance, Reactivation and Proficiency for Non

-Licensed Positions determines Operator A, C and D have maintained an active license status and that Operator B ha s not accumulated sufficient time required to maintain an active license status.

A.1.b While acting as an extra RO, the examinee will perform a Reactivity Balance for a power ascension using 0

-SO-62-7, Boron Concentration Control Appendix E, Reactivity Balance.

A.2 Given an emergent condition the Unit 1 TD AFW pump is declared to be INOPERABLE. The examinee will identify the equipment required to be administratively protected to maintain configuration control and determine the placement of protected train tags using 0

-GO-16 SYSTEM OPERABILITY CHECKLISTS.

The examinee will then place the required tags on components in the simulator.

A.3 Not examined.

A.4 While acting as the Site Communicator and given data for a plant emergency, the examinee will use EPIP-5 GENERAL EMERGENCY Appendix D to complete a NRC Event Notification Worksheet. The Emergency Notification System (ENS) phone in the simulator will not function, the examinee will use a simulator phone to transmit the NRC Event Notification Worksheet to the NRC at the designated phone numbers

.

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 Facility: Sequoyah Unit 1 & 2 Date of Examination:

7/25/2016 Examination Level:

RO Operating Test Number: 2016-302 Control Room Systems

• 8 for RO; 7 for SRO

-I; 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function a. Emergency Borate the RCS with Multiple Control Rods Not Fully Inserted. A PE 0 24 AA 1.0 4 (3.6) A, D, S 1 b. Establish Excess Letdown. 004 A2.07 (3.4/3.7)

D, S 2 c. Depressurize an Unisolable Cold Leg Accumulator during a SBLOCA. EPE 009 EK 3.21 (4.2/4.5)

A, D, EN, L, S 3 d. Secure RCP's During a LBLOCA. 003 A2.02 (3.7) A, N, S 4P e. Respond to an ERCW Pump Trip. 076 A2.01 (3.5)

D, S 4S f. Recover from a Containment Ventilation Isolation (CVI) Actuation. 103 A4.04 (3.5)

D, S 5 g. Transfer 1A

-A 6.9 KV SD Board from Alternate to Normal Supply. 064 A4.01 (4.0)

A, D, S 6 h. Respond to a Failure of Power Range Instrument N-44 K/A 015 A3.02 (3.7

) D, S 7 In-Plant Systems

• (3 for RO); (3 for SRO

-I); (3 or 2 for SRO

-U) i. Perform a Local EDG Start with a Failure of ERCW Valve to Auto Open. K/A 062 A4.07 (3.1)

D, A, E 6 j. Operate Steam Generator Atmospheric Dump PCV 12 Locally.

APE 068 AA1.01 (4.3)

D , E 8 k. Locally Control Charging Flow Using 2-FCV-62-93. APE 028 AA1.07 (3.3)

D , R 2

• All RO and SRO

-I control room (and in

-plant) systems must be different and serve different safety functions; all five 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 ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 a. The examinee will assume the shift in MODE 3 following a Reactor Trip with multiple Control Rods that are not fully inserted. The examinee will be directed to initiate emergency boration from the RWST using EA-68-4 Emergency Boration. The examinee will not be able to establish emergency boration using the CHARGING FLOW CONTROL valve and will implement the alternate path to establish emergency boration through the Charging Pump ECCS Discharge (CCPIT) valves. b. The examinee will assume the shift with Letdown isolated. The examinee will place Excess Letdown in service at a rate to cause pressurizer level to be stable or lowering using EA-62-3 ESTABLISHING EXCESS LETDOWN

. c. The examinee will assume the shift during an event with E-1, LOSS OF REACTOR OR SECONDARY COOLANT in progress. The examinee will isolate the Loop 1, 2 and 3 Cold Leg Accumulators (CLA) but discovers the Loop 4 CLA discharge valve will not close. The Examinee will implement the alternate path and vent the Loop 4 CLA using EA 1, VENTING UNISOLATED COLD LEG ACCUMULATOR.

d. The examinee will assume the shift when the Reactor automatically trips. The examinee will use E-0 Reactor Trip or Safety Injection to manually initiate Safety Injection and secure Reactor Coolant Pumps 1, 2, and 3 from panel M

-5. The examinee will then use the alternate path to secure Reactor Coolant Pump 4 by de-energizing Unit Board 1D. (This is a new action due to a recent revision to the EOP's.) e. The examinee will assume the shift when the Q-A ERCW pump trip

s. The examinee will use AOP-M.01 LOSS OF ESSENTIAL RAW COOLING WATER , to manually start another A Train ERCW pump and transfer the emergency power selector away from the Q

-A ERCW pump. f. The examinee will assume the shift following a Containment Vent Isolation event which subsequently cleared. The examinee will use 0-SO-30-3, section 8.4 , Recovery From a Containment Vent System Isolation Actuation to reset the Containment Vent Isolation and align the Containment Air radiation Monitors.

g. The examinee will assume the shift in MODE 1 with the 1A 6.9 kV Shutdown Board aligned to the alternate power source. The examinee will be directed to transfer 1A

-A 6.9 kV Shutdown Board to Normal Feeder at 1

-M-1 using 0-SO-202-4, 6900V Shutdown Boards, Section 8.1.5. The transfer to the normal power supply will fail, and the 1A Emergency Diesel Generator (EDG) will fail to auto start resulting in a loss of power to the 1A 6.9 Kv Shutdown Board. The examinee will use the alternate path to manually start the 1A EDG using 0-SO-202-4, 6900V Shutdown Boards.

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 h. The examinee will assume the shift when a failure of Power Range Monitor N

-44 occurs. The examinee will plac e control rods in manual using AOP-C.01 Rod Control Malfunctions. The examinee will then use A OP-I.01 NUCLEAR INSTRUMENT MALFUNCTION to defeat N-44 control functions, and prepare for removal from service.

i. The examinee will perform a normal, local start of the 1A Diesel Generator using 0

-SO-82-1 Diesel Generator 1A

-A section 8.2. While performing the start of the 1A Diesel Generator, the examinee will determine FCV 66 A Train Emergency Diesel HX Cooling Isolation fail s to open. The examinee will use the alternate path and locally open 1-FCV-67-68D B Train Emergency Diesel HX Cooling Isolation to establish cooling water flow to the 1A Diesel Generato r. j. The examinee will assume the shift in MODE 3 and a Control Room Evacuation in progress. The examinee will be directed to take local control of PCV 12, S/G 2 Atmospheric Dump valve using AOP

-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.1.

The examinee will take local control of PCV 12, S/G 2 Atmospheric Dump valve.

k. The examinee will place 2-FCV-62-93 Pressurizer level Control valve in local manual and control charging and seal flow within normal values using 2-SO-62-1, Chemical Volume and Control System

.