ML13035A240

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2012 Point Beach Nuclear Plant Initial License Examination Outline Submittal
ML13035A240
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 12/03/2012
From: Chuck Zoia
NRC/RGN-III/DRS/OLB
To:
Florida Power & Light Energy Point Beach
Shared Package
ML11354A218 List:
References
Download: ML13035A240 (8)


Text

2012 POINT BEACH NUCLEAR PLANT INITIAL LICENSE EXAMINATION OUTLINE SUBMITTAL

NEXTera ENERGY~

~ POIN;:--'

BEACH September 12,2012 NRC 2012-0074 Mr. Hironori Peterson, Chief Operations Branch U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Initial Operator License Examination Outline

Reference:

NRC to NextEra Energy Point Beach, LLC dated May 30,2012 In accordance with the requirements listed in the referenced letter, NextEra Energy Point Beach, LLC is submitting the initial license examination outline for the Point Beach Nuclear Plant. This submittal is made in accordance with the provisions of NUREG-1021, "Operator licenSing Examination Standards for Power Reactors, Revision 9, Supplement 1".

The initial license examination is scheduled for December 3-14,2012. The following materials are enclosed:

  • One Form ES-201-2, Examination Outline Quality Checklist
  • One Form ES-201-3, Examination Security Agreement
  • Two Forms ES-301-1, Administrative topics Outline (one each for Reactor Operator [RO]

and Senior Reactor Operator [SRO])

  • Two Forms ES-301-2, Control Room/In-Plant Systems Outline (RO and SRO-I)
  • Three Forms ES-D-1, Scenario Outline (one for each projected scenario)
  • Two Forms ES-401-2, Pressurized Water Reactor (PWR) Examination Outline (one each for Reactor Operator [ROJ and Senior Reactor Operator [SRO])
  • One Form ES-401-3, Generic Knowledge and Abilities Outline (Tier 3)
  • One Form ES-401-4, Record of Rejected Knowledge, Skills and Abilities
  • One Description of Random Sampling Methodology, and Knowledge and Ability Suppression Report NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 ENCLOSURE TO BE WITHHELD FROM PUBLIC DISCLOSURE UNTIL EXAMINATIONS ARE COMPLETE

U. S. Nuclear Regulatory Commission Page 2 Pursuant to the provisions of NUREG-1021. Revision 9. Supplement 1, these materials shall be withheld from public disclosure until after the examinations are complete.

Please contact Mr. Randall Amundson at 920/755-6860 if you have questions regarding this submittal.

Very truly yours.

NextEra Energy Point Beach, LLC Enclosure

ES*201 Examination Outline Quality Checklist Form ES*201*2 2012 NRC Exam Date of Examination: December 3,2012 Initials Item Task Description

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

W R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all KiA categories are appropriately sampled.

T T outline over-emphasizes any systems, evolutions, or generic topics.

E N justifications for deselected or rejected KiA statements are appropriate.

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

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

o c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R

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) tlhe number of new or modified tasks meets or exceeds tlhe minimums specified on tlhe 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 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.

N

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

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

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

f. Assess whether the exam fits the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)
c. NRC Chief Examiner (#)
d. NRC Supervisor

~~~~~~~~~~~

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

  • Not applicable for NRC-prepared examination outlines

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Point Beach U1/U2 Date of Examination: Dec 3, 2012 Examination Level: RO D SRO [8] Operating Test Number: 2012301 Administrative Topic Type Describe activity to be performed (see !\Jote) Code*

R,D Verify Shutdown Margin Calculation Conduct of Operations 2.1.25 (3.9/4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc.

Review Quadrant Power Tilt Calculations Conduct of Operations R,D,P 2.1.37 (4.3/4.6) Knowledge of procedures, guidelines, or limitations associated with reactivity management. (2011 NRC Exam)

Equipment Control R,D Review Completed Surveillance 2.2.12 (3.7/4.1) Knowledge of surveillance procedures Remove RMS Channel from Service (RE-230) 2.3.13 (3.4/3.8) Knowledge of radiological safety procedures Radiation Control R,M pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

R,N Make a Protective Action Recommendation Emergency 2.4.44 (2.414.4) Knowledge of emergency plan protective Procedures/Plan action recommendations 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 (S 3 for ROs; S 4 for SROs & RO retakes)

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Point Beach Date of Examination: Dec 3, 2012 Exam Level: RO ~ SRO-I D SRO-U D Operating Test No.: 2012301 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code" Safety Function

a. Control Rod Drive System / Recover dropped Rod AOP-6A I

APE 003 AAl.02 (3.6/3.4)

h. Chemical & Volume Control System I Manually Makeup To The VCT.

A,D,S 2 004.A4.l2 (3.8/3.3)

C. Main Feedwater System 1 Respond to a Loss of Secondary Heat Sink.

L,A,D,S 4S E05.EA2.2 (3.7/4.3)

d. Reactor Coolant Pump / RCP Malfunction A,D,P,S 4P APE 015/017.AK3.03 (3.7/4.0) (2009 Exam)
e. Containment Spray System 1 Adjust Containment Sump pH.

L,D,S 5 026.A4.01 (4.5/4.3)

f. Emergency Diesel Generator 1 Island EDG per I-S0P-4KV-OOl N,S 6 064.A4.01 (4.0/4.3)
g. Nuclear Instrumentation / Return NI to Service.

D,S 7 015.A4.03 (3.8/3.9)

h. Component Cooling System 1 Shift CCW Pumps 008.A4.04 (2.6*/2.6) D,S 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Steam Generator / Locally Operate the Atmospheric Steam Dump Valve I D,R,E 4P 035.K6.02 (3.113.5)
j. Instrument Air / Start IA Compressor to Depressurized Receiver. 8 A,D,E 078.A3.01 (3.113.2)
k. G05 Gas Turbine / Locally start G05.

A,N,E 6 EPE 055.EA2.03 (3.9/4.7)

@ 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 I SRO-II SRO-U (A)ltemate path 4-6 1 4-6/2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant  :?:1/:?:1/:?:1 (EN)gineered safety feature 1 :?:1 (control room system)

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

(R)CA  :?:1/:::1/;::1 (S)imulator

ES-301 Transient and Event Checklist Form ES-301-5 int Beach Date of Exam: December 3, 2012 Operating Test No.: 2012 A E Scenarios P V 1 2 3 M P E I L N CREW CREW CREW N I T POSITION POSITION POSITION I M

C S A B S A B S A B U A T R T 0 R T 0 R T 0 M(")

N Y 0 C P 0 C P 0 C P R U T P E

RO RX 4 X

NOR 1,4 SRO-I D I/C 8 2,5,7 SRO-U 5 6 D TS RO RX 4 D NOR 4 1,2 SRO-I X I/C 2, 3,4 SRO-U MAJ 5 6 5 4,6 NOR 1,4 4 IIC 2,3 1,2,5 3,8 MAJ 5 6 5 TS 2,3 1,3 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (IIC) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (..) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicanfs competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

ES*301 Transient and Event Checklist Form ES*301*5 Facility: Point Beach Date of Exam: December 3,2012 Operating Test NO.:201230 A E Scenarios p V 1 2 M P E I L N CREW CREW N I T POSITION POSITION I M

C S A B S A B U A T R T 0 R T 0 M(*)

N Y 0 C P 0 C P R U T P E

RO RX S 4 S X

NOR U 1,4 U SRO-I D

SRO-U I/C R 8 2,6,8 R MAJ R 5 7 R D TS 0 0 RX G 4 G NOR 4 A I/C Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position. one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or control/ed abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.