ML112160580

Sequoya Retake Initial Exam 2011-301 Draft Administrative Documents

ML112160580
Person / Time
Site:	Sequoyah
Issue date:	06/03/2011
From:	NRC/RGN-II
To:
References
Download: ML112160580 (4)

Text

ES-301 Control Room/I n-Plant Systems Outline Form ES-30 I -a Facility: Seguoyah Nuclear Station 1 & 2 Date of Examination: 4/12/2011 Exam Level: RO SRO-I SRO-U Operating Test No: 2011-301 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Rod Control Urgent Failure During Reactor Startup K/A 001 A1.06 (4.1/4.4) D, A, 5, L 1

b. Align ECCS Pumps to the Containment Sump K/A 006 A4.07 (4.4/4.4) M, S, L 2

c. Isolate the Ruptured Steam Generator (With MSIV Failure to Close) K/A EPE M, A, 5, L 3 038 EA1 .32 (4.6/4.7)

d. Start a Reactor Coolant Pump K/A APE 015/017 AAI .03 (3.7/3.8) D, A, S, L 4P

e. Respond to ERCW Pump Trip K/A 076 A2.01 (3.5/3.7) M, S 4S

f. Transfer lA-A 6.9KV SD Bd From Alternate to Normal K/A 064 A4.01 (4.0/4.3) M, A, 5 6

g. Respond to a Failure of Power Range Instrument N-44 K/A 015 A3.02 (3.7/3.9) D, S 7 In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

h. Uncontrolled Boron Dilution Flowpath Isolation K/A 004 A2.25 (3.8/4.3) D, R, L 2

i. Operate the TD AFW Pump Locally K/A 061 A2.04 (3.4/3.8) M, A, E, R 4S

j. Respond to Decreasing RCS Pressure and Level From the Aux. Control Room D, E 8 K/A APE 068 AA1.12 (4.4/4.4)

All RO and SRO-l 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-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1 / 1 I 1 (N)ew or (M)odified from bank including 1(A) 2/ 2I 1 (P)revious 2 exams 3 / 3 I 2 (randomly selected)

(R)CA 1/1I1 (S)imulator

a. Rod Control Urgent Failure During Reactor Startup -

While withdrawing control rods low in the power range, an urgent failure occurs preventing normal control rod movement. The examinee will stop withdrawing control rods and determine a Reactor Trip is required.

b. Transfer to Cold Leg Recirc The examinee will isolate the ECCS pump suction from the RWST following a LOCA during the performance of ES-i .3 transfer to RHR Containment Sump.

c. Isolate the Steam Generator Tube Rupture (With MSIV Failure to Close)

The examinee will attempt to isolate a ruptured steam generator using the ruptured steam generator MSIV. The ruptured steam generator MSIV will fail to close so the examinee will close all intact MSIVs and the alternate flowpath isolation valves.

d. Start a Reactor Coolant Pump The examinee will start a Reactor Coolant Pump (RCP) while in MODE 3. Shortly after starting the pump, a high motor winding condition develops requiring a manual trip of the RCP.

e. Respond to ERCW Pump Trip While responding to an ERCW pump trip, the examinee will manually start an ERCW pump.

f. Transfer lA-A 6.9KV SD Bd From Alternate to Normal While restoring from maintenance, the examinee will attempt to transfer the 6.9 kv Shutdown Board from the alternate to the normal source. While transferring, the normal supply breaker will fail to close de-energizing the iA-A 6.9 kv bus. The examinee will manually start the iA-A EDG to supply power to the lA-A 6.9 kv Shutdown Board.

g. Respond to a Failure of Power range Instrument N-44.

The examinee will respond to a failure of Power Range Monitor, N-44, defeat its control functions, and prepare for its removal from service.

h. Uncontrolled Boron Dilution Flowpath Isolation In preparation for an outage, the examinee will locally isolate a boron dilution flowpath.

i. Operate the TO AFW Pump Locally While responding to a Loss of All AC condition, the examinee will reset and locally start and control the Unit 1 Turbine Driven Auxiliary Feed pump

j. Respond to Decreasing RCS Pressure and Level From the Aux. Control Room While responding to lowering RCS pressure during a Control Room abandonment situation, the examinee will take local control of the Pressurizer PORVs at the Auxiliary Control Panel and shut the PORVs.

ES-301 Administrative Topics Outline Form ES-301-1 7:? /1-Facility: Seciuoyah Nuclear Station 1 & 2 Date of Examination:4/12/201 1 Exam Level: RO SRO Operating Test No: 201 1-30 1 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations R, M Calculate Subcooling Margin K/A 2.1.45 (4.3)

Conduct of Operations R, N Evaluate Shift Daily Surveillance Log Mode One K/A 2.1.18 (3.8)

Equipment Control R, D Evaluate Arc Flash Clothing Requirements and Tag Verification Requirements during a Clearance Placement. K/A 2.2.13 (3.8)

Radiation Control R, M Pre Job Analysis for Emergent Work in the RCA. K/A 2.3.13 (3.8)

Emergency Procedures/Plan R, M Evaluate Conditions For Emergency Classification K/A 2.4.41 (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.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for RO5; 4 for SROs & RO retakes)

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

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

A.1.a Calculate Subcooling Margin iring a CQntrol Abandonment situation, the examineewiIL determine acuLsubongmargi.ri based on a given set of parameters and calculate results using Steam Tables. Based on the result of the calculation, the examinee will make the decision that RCPs can be stopped based on adequate subcooling A.1.b Evaluate Shift Daily Log During Mode One The examinee will evaluate the data provided in the daily shift log to determine if the data meets the administrative and tech spec acceptance criteria.

A.2 Evaluate Ace Flash Clothing Requirements and Tag Verification Requirements during a Clearance Placement The examinee will determine the minimum protective clothing requirements for manipulating electrical breakers during placement of a clearance and the verification requirements for the placing of the clearance tags in preparation for pre-job brief.

A.3 Pre Job Analysis for Emergent Work in the RCA Acting as the Outage Work Control SRO, the examinee will review an emergent task in the RCA by utilizing survey maps. The examinee will determine the anticipated dose and determine which worker to use based on prior accumulated dose.

A.4 Evaluate change in conditions for Emergency Classification upgrade.

Acting as the Site Emergency Director, and given a set of initial conditions, the examinee will classify and complete a state emergency notification form.