ML17193A965

(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:
References
Download: ML17193A965 (1)

Text

ES-201 Examination Preparation Checklist Form ES-201 -1 Facility: ak Date of Examination: iJ 2/ 2..-(3)b Developed by: Written: Facility NRC LI $ II Operating Facility LI NRC LI Target .

Chief Task Description (Reference) ate Examiners Initials

-180 1. Examination administration date confirmed (Cia; C.2.a and b)

-150 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

-150 3. Facility contact briefed on security and other requirements (C.2.c) (j..

-150 4. Corporate notification letter sent (C.2.d) . t5kol 1

[-120] 5. Reference material due (C.1.e; C.3.c; Attachment 3)

{-90} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301 -2, ES-301 -5, ES-D-1, ES-401 -1/2, ES401 N-1/2, ES-401-3, ES-401 N-3, ES-401-4, and ES4O1N4, as applicable (C.1.e and f; C.3.d)

{-85} 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)

{-60} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-3014, ES-301-5, ES-301-6, and ES4O1-6, ES4O1 N-6, and any Form ES-201-2, ES-201-3, ES-301-1, or ES-301-2 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

-45 9. Written exam and operating test reviews completed. (C.3.f) 4-

-30 10. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)

-21 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-21 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

-14 13. Final license applications due and Form ES-201-4 prepared (CII; C.2.i; ES-202)

-14 14. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 15. Facility licensee management queried regarding the licensees views on the examination. (C.2 j)

-7 16. Final applications reviewed; I or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2i; Attachment 5; ES-202, C.2.e; ES-204)

-7 17. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)

-7 18. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply) to examinations prepared by the NRC.

JpfY Orj ES-201, Page 25 of 28

5 ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Sequoyah Nuclear StatIon 1 82 Date of Examination: 0712512016 Initials Item Task Description =

a b*

1. a. Verity that the outline(s) fit(s) the appropriate model, in accordance with E3401 NA NA NA w

R b. Assess whether the outline was systematically and randomly prepared in accordance with NA NA NA I Section D.1 of ES4O1 and whether all K/A categories are appropriately sampled.

T T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. NA NA NA

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. NA NA NA

2. a. Using Form ES-301-5, verity that the proposed scenario sets cover the required number NA NA NA of normal evolutions, instrument and component failures, technical specifications, S and major transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected number NA NA NA u and mix of applicants in accordance with the expected crew composition and rotation c schedule without compromising exam integrity, and ensure that each applicant can be A tested using at least one new or significantly modified scenario, that no scenarios are T duplicated from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

R NA NA NA

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix Q (IlL of applicants and ensure that no items are duplicated on subsequent days.

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

G E b. Assess whether the 10 CFR 55.41 /43 and 55.45 sampling is appropriate.

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

R d. Check for duplication and overlap among exam sections.

A C e. Check the entire exam for balance of coverage.

f.__Assess whether the_exam_fits_the_appropriate job_level_fRO_or_SROj_

a. Author Owen B Triolo /

CCtt_______________________

Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines fr Jfr\. P4- t j

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 Describe activity to be performed Code*

Conduct of Operations R, M Determine Maintenance of Active License Status. G 2.1.4 (3.3)

Perform a Reactivity Balance Calculation from Conduct of Operations R, D 25% to 100% using 0-SO-62-7, Appendix E. G 2.1.25 (3.9)

Perform a System Operability Checklist when Equipment Control S, M the TD AFW pump is being removed from service and determine the required protected train tag placement. G 2.2.14 (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 bank ( 3 for ROs; 4 for SROs & RO retakes)

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

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

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 has 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 A, D, S 1 Inserted. APE 024 AA 1.04 (3.6)

b. Establish Excess Letdown. 004 A2.07 (3.4/3.7) D, S 2

c. Depressurize an Unisolable Cold Leg Accumulator during a A, D, EN, L, S 3 SBLOCA. EPE 009 EK 3.21 (4.2/4.5)

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.

D, S 5 103 A4.04 (3.5)

g. Transfer 1A-A 6.9 KV SD Board from Alternate to Normal Supply.

A, D, S 6 064 A4.01 (4.0)

h. Respond to a Failure of Power Range Instrument N-44 K/A 015 D, S 7 A3.02 (3.7)

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 D, A, E 6 Open. K/A 062 A4.07 (3.1)

j. Operate Steam Generator Atmospheric Dump PCV-1-12 Locally.

D, E 8 APE 068 AA1.01 (4.3)

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

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

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

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

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 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-63-1, 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 EOPs.)

e. The examinee will assume the shift when the Q-A ERCW pump trips. 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 place control rods in manual using AOP-C.01 Rod Control Malfunctions.

The examinee will then use AOP-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-67-66 A Train Emergency Diesel HX Cooling Isolation fails 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 Generator.

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-1-12, 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-1-12, 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.

Zol -

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility Date of Examination Operating Test Number

1. General Criteria Initials a b c#

a The operating test conforms with the previously approved outline, changes are consistent with sampling requirements çe g 10 CER 55 45. operational importance. safety function distribution) b There is no day-to-day repetition between this and other operating rests to be administered during this examination c The operating test shall not duplicate items from the applicants audit test(s) (see Section D 1 a) T d Overlap with the written examination and between different parts of the operating test is within acceptable limits 1j L

a It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level

2. Walk-Through Criteria -- --

a Each JPM includes the following as applicable

• initial conditions initiating cues

• references and tools including associated procedures

• reasonable and validated time limits laverage time allowed for completion) and specific designation if deemed to be time-critical by the facility icensee

• operationally important specific performance criteria that include detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful compietion of the task identification of critical steps and their associated performance standards restrictions on toe sequence of steps, if applicable b Ensure that any changes from the previously approved systems and administrative walk-through -,

outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (a g item distribution, bank use repetition from the last 2 NRC examinations) specified 7 I on those forms and Form ES-201-2 0

3. Simulator Criteria --

N IAL t4 The associated simulator operating tests iscenaro setsi have been reviewed in accordance with Form ES-301-4 anda copy is attached 4 Printed Name / Si ce Date a Author 3 IR IO 7 7/ 7) b Facility Revieweri itic.L c NRC Chief Examiner #) br,eI fl . Zc.1 7)/fl.

a NRC Supervisor 1 NOTE.

• The facility signature is not applicable for NRC-developed tests

1. Independent NRC reviewer initial items in Column c: chief examiner concurrence required.

JPP R O-1

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 JunelO,2016 10CFR55.5 10 CFR 55.49 Ms. Catherine Haney U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE., Suite 1200 Atlanta, Georgia 30303-1 257 Attention: Mr. G. J. McCoy Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Reactor Operator Examination Outline The purpose of this letter is to transmit the examination outlines for the operating test scheduled to be re-administrated the week of July 25, 2016, as discussed with Daniel Bacon of your staff.

In accordance with 10 CFR 55.49 and NUREG 1021, Operator Licensing Examination Standards for Power Reactors, appropriate measures have been taken to ensure examination integrity and security. Accordingly, it is requested that this letter and the enclosed documents be withheld from public disclosure until the examinations ate completed in accordance with 10 CFR 2.390.

There are no regulatory commitments contained in this submittal. SQNs principal contact is Mr. Matthew McMullin, Operations Training Manager. Should you require additional information regarding this matter, please contact Mr. McMullin at (423) 843-4084 or Mr. Michael McBrearty, Site Licensing Manager at (423) 843-7170.

Sincerely, ffpherJ. Schwar Site Vice President Seq uoyah Nuclear Plant

Enclosure:

Examination Outlines for Reactor Operator Candidate printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 June 10, 2016 JTJ: SKJ bcc: (wlo enclosure)

M. A. Balduzzi T. M. Conner C. R. Dahlman S. M. Douglas M. A. Giacini E. K. Henderson J. T. Johnson T. B. Marshall M. W. McBrearty M. C. McMullin P. P. Pratt E. D. Schrull J. W. Shea H. E. Siercks K. Smith B. K. Sowter S. C. Thomas B. A. Wetzel EDMS I: LicenseOperator Iicense2O1 6\Barker Examination outline 06-13-2016

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 10 CER 55.5 10 CFR 55.49 June 10, 2016 Ms. Catherine Haney U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE., Suite 1200 Atlanta, Georgia 30303-1 257 Attention: Mr. G.]. McCoy Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Reactor Operator Examination The purpose of this letter is to transmit the examination for the operating test scheduled to be re-administrated the week of July 25, 2016, as discussed with Daniel Bacon of your staff. The operating test and supporting reference material have been approved by an authorized SQN representative.

In accordance with 10 CFR 55.49 and NUREG 1021, Operator Licensing Examination Standards for Power Reactors, appropriate measures have been taken to ensure examination integrity and security. Accordingly, it is requested that this letter and the enclosed documents be withheld from public disclosure until the examinations are completed in accordance with 10 CFR 2.390.

There are no regulatory commitments contained in this submittal. SQNs principal contact is Mr. Matthew McMullin, Operations Training Manager. Should you require additional information regarding this mailer, please contact Mr. McMullin at (423) 843-4084 or Mr. Michael McBrearty, Site Licensing Manager at (423) 843-7170.

Si nce rely, GtiuTtopher J. Scfwari Site Vice President Seq uoyah Nuclear Plant

Enclosure:

Operating Examination for Reactor Operator Candidate printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 June 10, 2016 JTJ: SKJ bcc: (wlo enclosure)

M. A. Balduzzi T. M. Conner C. R. Dahiman S. M. Douglas M. A. Giacini E. K. Henderson

]. T. Johnson T. B. Marshall M. W. McBrearty M. C. McMuIIin P. P. Pratt E. D. Schrull J. W. Shea H. E. Siercks K. Smith B. K. Sowter S. C. Thomas B. A. Wetzel EDMS I: LicenseOperator Iicense2O1 6Barker Examination and Requested Information 06-20-2016

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