ML13035A240
| ML13035A240 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| 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 POIN;:--'
BEACH September 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 Dockets 50-266 and Renewed License Nos. DPR-24 and Initial Operator License Examination
Reference:
NRC to NextEra Energy Point Beach, LLC dated May In accordance with the requirements listed in the referenced letter, NextEra Energy Beach, LLC is submitting the initial license examination outline for the Point Nuclear Plant. This submittal is made in accordance with the provisions of "Operator licenSing Examination Standards for Power Reactors, Revision 9, Supplement The initial license examination is scheduled for December 3-14,2012.
The following are 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) One Form ES-301-5, Transient and Event Checklist 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 NextEra Energy Point Beach, Enclosure Examination Outline Quality Checklist Form ES*201*2 Item 1. W R I E N 2. S I M U L A T o R 3. W I T 4. G E N E R A L a. Author b. Facility Reviewer (*) c. NRC Chief Examiner (#) NRC Supervisor 2012 NRC Exam Date of Examination:
December 3,2012 Initials Task Description Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KiA categories are appropriately sampled. outline over-emphasizes any systems, evolutions, or generic topics. justifications for deselected or rejected KiA statements are appropriate. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. 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. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2: the outline(s) contain(s) the required number of control room and in-plant distributed among the safety functions as specified on the task repetition from the last two NRC examinations is within the limits specified on the form no tasks are duplicated from the applicants' audit test(s) tlhe number of new or modified tasks meets or exceeds tlhe minimums specified on tlhe form the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form. Verify that the administrative outline meets the criteria specified on Form ES-301-1: the tasks are distributed among the topics as specified on the form at least one task is new or significantly modified no more than one task is repeated from the last two NRC licensing examinations 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. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5. Check for duplication and overlap among exam sections. Check the entire exam for balance of coverage. Assess whether the exam fits the appropriate job level (RO or SRO). 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 (see !\Jote) Type Code* Describe activity to be performed Conduct of Operations R,D Verify Shutdown Margin Calculation 2.1.25 (3.9/4.2)
Ability to interpret reference materials, such as graphs, curves, tables, etc. Conduct of Operations R,D,P Review Quadrant Power Tilt Calculations 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 Radiation Control R,M Remove RMS Channel from Service (RE-230) 2.3.13 (3.4/3.8)
Knowledge of radiological safety procedures 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. Emergency Procedures/Plan R,N Make a Protective Action Recommendation 2.4.44 (2.414.4)
Knowledge of emergency plan protective 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)
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 a. Control Rod Drive System / Recover dropped Rod AOP-6A APE 003 AAl.02 (3.6/3.4)
- h. Chemical & Volume Control System I Manually Makeup To The VCT. 004.A4.l2 (3.8/3.3)
C. Main Feedwater System 1 Respond to a Loss of Secondary Heat Sink. E05.EA2.2 (3.7/4.3)
- d. Reactor Coolant Pump / RCP Malfunction APE 015/017.AK3.03 (3.7/4.0)
(2009 Exam) e. Containment Spray System 1 Adjust Containment Sump pH. 026.A4.01 (4.5/4.3)
- f. Emergency Diesel Generator 1 Island EDG per I-S0P-4KV-OOl 064.A4.01 (4.0/4.3)
- g. Nuclear Instrumentation
/ Return NI to Service. 015.A4.03 (3.8/3.9)
- h. Component Cooling System 1 Shift CCW Pumps 008.A4.04 (2.6*/2.6)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) Type Code" Safety Function I A,D,S 2 L,A,D,S 4S A,D,P,S 4P L,D,S 5 N,S 6 D,S 7 D,S 8 i. Steam Generator
/ Locally Operate the Atmospheric Steam Dump Valve I 035.K6.02 (3.113.5)
D,R,E 4P j. Instrument Air / Start IA Compressor to Depressurized Receiver.
078.A3.01 (3.113.2)
A,D,E 8 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 (A)ltemate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1 Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator Criteria for RO I SRO-II SRO-U 4-6 1 4-6/2-3 s9/s8/s4 :?:1/:?:1/:?:1 1 :?:1 (control room system)
- 2/;::2/:::1 s 3/ s 3/ s 2 (randomly selected)
- ?:1/:::1/;::1 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 C S A B S A B S A B M U A T R T 0 R T 0 R T 0 M(") N Y 0 C P 0 C P 0 C P T P R U 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: 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. 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. 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.
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 C S S M A B A B U A T R T 0 R T 0 M(*) N Y 0 C P 0 C P T P R U E RO RX S 4 S X NOR U 1,4 U SRO-I D I/C R 8 2,6,8 R SRO-U MAJ R 5 7 R D TS 0 0 RX G 4 G NOR 4 A I/C Instructions: 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. 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. 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.