ML120810234
| ML120810234 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/23/2012 |
| From: | Bielby M NRC/RGN-III/DRS/OLB |
| To: | |
| Shared Package | |
| ML12053A029 | List: |
| References | |
| Download: ML120810234 (15) | |
Text
2012 BYRON STATION INITIAL LICENSE EXAMINATION OUTLINE SUBMITTAL
ExelonSM Exelon Generation Company, LLC Nuclear Byron Station 4450 North German Church Road Byron, I L 61010-9794 October 13, 2011 LTR:
BYRON 2011-0146 File:
1.10.0101 Mark Satorius Regional Administrator - Region III United States Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Byron Station, Units 1 and 2 Facility Operating License Nos: NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Submittal of Initial Operator Licensing Examination Outline Enclosed are the examination outlines, supporting the Initial License examination scheduled for the weeks of January 23, 2012 through January 30, 2012, at Byron Station.
This submittal includes all appropriate Examination Standard forms and outlines in accordance with NUREG-1021, "Operator Licensing Examination Standards", Revision
- 9.
In accordance with NUREG-1 021, Revision 9, Section ES-201, "Initial Operator Licensing Examination Process", please ensure that these materials are withheld from public disclosure until after the examinations are complete.
Should you have any questions concerning this letter, please contact Mr. David T.
Gudger, Regulatory Assurance Manager, at (815) 496-2800. For questions concerning examination materials, please contact Mr. William F. Hochstetter at (815) 406-3111.
Respectfully,
..~
Ti YJ. Tulon S* ~
Vice President Byron Nuclear Generating Station T JTIWH{fH/jh
Enclosures listed below will be hand delivered to Mike Bielby, Chief Examiner, NRC Region III Examination Security Agreements (Form ES-201-3)
Administrative Topics Outline(s) (Form ES-301-1)
Control Room lin-Plant Systems Outline (Form ES-301-2)
PWR Examination Outline (Form ES-401-2)
Generic Knowledge and Abilities Outline (Tier 3) (Form ES-401-3)
Scenario Outlines (Form ES-D-1)
Record of Rejected K/As (Form ES-401-4)
Completed Checklists:
o Examination Outline Quality Checklist (Form ES-201-2) o Transient and Event Checklist (Form ES-301-5) cc:
Chief, NRC Operator Licensing Branch (w/o enclosures)
NRC Senior Resident Inspector, Byron Station (wlo enclosures)
bcc:
Byron Station Project Manager, NRR Site Vice President, Byron Station Regulatory Assurance Manager, Byron Station Vice President - Licensing and Regulatory Affairs Director, Licensing - Midwest Regional Operating Group Manager, Licensing - Byron Station Byron Nuclear Licensing Administrator Exelon Document Control Desk Licensing - OeD Human Resources, Byron Station Training Manager, Byron Station W. Hochstetter, Byron Station
ES-201 Examination Outline Quality Checklist Form ES*201*2 Facility:
Date of Examination:
Initials Item Task DeScription a
b*
c#
- 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 0.1 of ES-401 and whether all KIA categories are appropriately sampled.
T T
- c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
E N
- d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.
- 2.
- a. UsingFonn ES-301-5, verify that the proposed scenario sets cover the required number of nonnal 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 testes), and that scenarios will not be repeated on subsequent days.
o
- c. TO the extent possible, assess whether the outline(s) confonn(s) with the qualitative R
and quantitative criteria specified on Fonn ES-301-4 and described in Appendix D.
- 3.
- a. Verify that the systems walk-through outline meets the criteria specified on Fonn 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 1
(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 testes)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the tonn (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 Fonn ES-301-1:
(1) the tasks are distributed among the topics as specified on the tonn (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. Detennine 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
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
E N
- c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5.
E
- d. Check for duplication and overlap among exam sections.
R A
- e. Check the entire exam for balance of coverage.
L
- a. Author
- b. Facility Reviewer (*)
Lobu.."'" 4wtuL /,...,-L-.."
.-ttl!!
- c. NRC Chief Examiner (#)
rn,'dUAl', ~,'... 1~ l h I.../II.JLI.1t, Ll P~/I rJA.. !:>7 t?
/
- d. NRC Supervisor J<AJ..I..
,.... [l \\J~l-"'\\AlllMiA, P KuP\\.."1,>>-J~J-
!O (y,J 0\\\\
~
Note:
- Independent NRC reviewer initial items in Column "CO; chief examiner concurrence required.
- Not applicable for NRC-prepared examination outlines ES-201, Page 26 of 28
ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:Byron Date of Exam:01/30/2012 Tier Group RO KIA Category Points SRO-Only Points K
1 K
2 K
3 K
4 K
5 K
6 ~I~
A 3
A 4
G Total A2 G*
Total
- 1. Emergency Abnormal Plant Evolutions 1
3 3
3 N/A 3
3 N/A 3
18 3
3 6
2 2
2 1
2 1
1 9
2 2
4 Tier Totals 5 5
4 5
4 4
27 5
5 10
- 2.
Plant Systems 1
3 2
3 3
2 2
3 3
2 2
3 28 3
2 5
2 1
1 1
1 1
1 1
0 1
1 1
10 0
2 1
3 Tier Totals 4 3
4 4
3 3
4 3
3 3
4 38 I
5 3
8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
2 3
2 3
2 2
2 1
Note: 1.
Ensure that at least two topicS from every applicable KIA category are sampled within each tier of the RO and SRQ-only outlines (i.e., except for one category in Tier 3 of the SR0-only outline, the "Tier Totals" in each KIA category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified In the table.
The final point total for each group and tier may deviate by +/-1 from that specified In the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, Site-specific systems that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (I) for each system and category. Enter the group and tier totals for each category In the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter It on the left side of Column A2 for Tier 2. Group 2 (Note 11 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog. and enter the KIA numbers. descriptions, IRs, and point totals (I) on Form E8-401-3. Umit SRO selections to KIAs that are linked to 10 CFR 55.43.
ES-401, 21 of 33
ES-401 2
Form E8-401-2 PWR Examination Outline ElAPE # I Name I Safety Function KJA Topic(s)
Reactor Trip* Stabilization* Recovery 11 Pressurizer Vapor Space Accident I 3 RCP MaHunotions I 4 to secure RePs on loss of cooling or seal injection RCP MaHunOlions (Loss of RC Flow) I 4 Releltlonshio between charging flow and PZR level water or closed oooling waler pumps adjustments needed to maintain proper T-ave. and S/G conditionS and immediate action Loss of Off-sile Power 16 Loss of Vital AC Inst. Bus 16 Interpret the significance of each Loss of DC Power 16 Loss 01 Nuclear Svc Water I 4 indicating signals, and remedial with the Loss of Secondary Heat Sink ES-401, 22 of 33 Form ES-401 IR 3.5 0
4.1 0
3.7 3.0 2.7 0
4.0 4.5 3.1 0
4.0 4.8 0
3.3 4.1 4.0 2.9 3.8 3.8 3.9 3.6
Continuous Rod Withdrawal/1 Dropped Control Rod /1 Pressurizer Level MaHunction /2 Loss of Source Range NI/7 Loss of Intermediate Range NI/7 Steam Generator Tube Leak 13 Accidental Liquid RadWaste Rel./9 Accidental Gaseous Radwaste Rei. 19 Loss of CTMT Integrity 15 3 Steam Generator Over-pressure /4 nOperations 14 E8-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2 (RO)
~--~-A-P-E-#-I-N-a-m-e-I-s-a~---F-un-~-o-n--~~~~~~~-~~-A~
~~A-T-OP~i~~S)----------II-I-R~--,~1 o
rod drive power supplies and logic circuits 2.5 o
o 01 3.8 rO.l8rE;uoo,.es. Including proper sv.itch positions 2.7 3.0 o
of makeup !low and letdown !low for various modes 3.1 04 2.5 o
3.1 4.2 o
o o
3.4 o
o o
o o
o 02 02 2
05 01 2
03 2
ES-401, 23 of 33
E8-401 4
Form ES-401-2 PWR Examination Outline Fonn ES-401 Plant KIA Topic(s)
IR 2.7 Chemical and Volume Control minimum and maximum flow rates for letdown 2.6 3.7 3.4 Pressurizer Relief/Quench Tank I
of the waste gas vent header 2.5 Component Cooling Water 2.9 enthalpy expansion through a valve 2.6 3.4 Safety Features 3.0, 2
3.4 alarms. Indications. or response 4.2 2
2.5 Containment Spray 4.2; 2
4.5 Main and Reheat Steam 2.9; 2
2.8 2.7; 2
4.2 Auxiliary/Emergency Feedwater 3.1 AC Electrical Distribution 3.5; 2
3.5 DC Electrical Distribution 2.9; 2
2.7 3.8 Process Radiation Monitoring Intensity ohanges with source distance 2.5 Service Water 2.5 3.0 pressure, temperature, and humidity 3.7 0
ES-401, Page 24 of 33
ES-401 5
Form ES-401..2 ES-401, Page 25 of 33 PWR Examination Outline Form ES-401 r--___________,.-...--"'T"""-r--r--r_PT'a_nt Systems - Tler...,;2f:....G:....r...;.oU.;,:p:....2.;...:.--.:_________-r-_...--__U IR 4.2 0
3.1 0
4.1 6 Non-nuclear Instrumentation 0
7 In-core Temperature Monitor 3.7 0
Recombiner and Purge 0
0 01 annunciator alarms. indications. or response 4.2 0
4.0 Steam DumplTurblne Bypass Control and positioners. inctuding IeS. SIG. CRDS 2.7 Main Turbine Generator 0
Condenser Air Removal 0
0 0
Waste Gas Disposal 2.6 Area Radiation Monitoring 2.5 3.4 0
0 10
ES-401 2
Form E8-401-2 PWA Examination Outline Fonn ES*401 Emergency and Abnonnal Plant Evolutions - Tier 1/Group 1 (SAO)
~----------------------~~~-r~--
~~--~--------~--~--~I K
A IA ElAPE 4# I Name I Safety Function KIA Toplc(s)
Reactor Trip* Stabilization* Recovery /1 0
4.2 0
4.4 5 RCP Malfunctions 14 0
7 RCP Malfunctions (Loss of RC Flow) 14 Loss of Rx Coolant Makeup 12 0
4.2 Loss of Component Cooling Water /8 of a leak in the CCWS 3.5 Pressure Control System 0
0 0
between steam line rupture and LOCA 4.7 o
o 4.7 o
o o
o o
o o
Gel~eflltor Voltage and Electric o
/6 6
ES*401, 22 of 33
E8-401 3
Form E8-401-2 Fonn ES-401 PWR examination Outline IR EIAPE # I Name I Safety Function Emero!em:vand Abnonnal Plant Evolutions - Tier 1/Group 2 (SRO) r---------------------~_r_,--~
KKK A 1
2 3
1 KIA Toplc(s)
Continuous Rod Withdrawal I 1 0
Dropped Control Rod 11 0
Inoperable/Stuck Control Rod 11 0
4.2 Pressurizer Level Malfunction I 2 0
0 Loss of Intermediate Range NI/7 0
0 Steam Generator Tube Leak 13 0
0 AccIdental liquid RadWaste ReI. { 9 0
Accidental Gaseous RadWaste Rei. / 9 0
4.1 1
0 0
0 o
High Reactor Coolant Activity / 9 0
0 Steam Generator Over-pressure / 4 4.4 Containment Flooding 15 0
High Containment Radiation 19 0
procedures 4.2 0
0 4
o 0
0 0
ES-401, 23 of 33
E5-401 4
IR 0
86 Chemical and Volume Control 4.3 87 Residual Heat Removal pressure. flow. pump molOr ampe. moIOr 2.9 tank level inst!\\lmentalion 88 4.0 89 Pressurizer Relief/Quench Tank procedures are 4.5 Component Cooling Water 0
0 0
Safety Features 0
0 Ice Condenser 0
0 Main and Reheat steam 0
0 0
0 0
Process Radiation Monitoring 0
90 Service Water 3.7 0
0 0
Category Totals:
5 ES-401. Page 24 of 33
E5-401 5
Form ES-401-2 ES-401, Page 25 of 33 PWR Examination Outline Form ES-401 Plant Systems - Tier 21Group 2 KIA Topic(s)
IR 1#
0 4.2 0
3.3 0
6 Non-nuclear Instrumentation 0
0 Recombiner and Purge 0
0 0
Fuel Handling Equipment 0
0 0
Main Turbine Generator 0
0 0
0 Waste Gas Disposal 0
Area Radiation Monitoring 0
Circulating Water 0
0 actuation of the FPS due to clrou~ failure or 2.9 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form E8-401-3 ES-401, Page 26 of 33
~
Date of Exttlll:01/30/2012
"'vllILY '..... II'C....Y'VIi
"¥ Category KIA #
Topic BQ SFK I-Onlv IR 1#
IR 1#
66 2.1.39 of consel'\\rative decision making prac1ices 3.6 1
'r---
67 2.1.45 Ability to identify and interpret divelSll indications to validate the response of another indicator.
4.3 1
r---
94
- 1.
1 2.'.20 Ablil\\y to interpret and execute procedure steps.
4.6 1
Conduct of 100 Operations 2.1. 32 !Abilily to explain and apply $¥Stem limits and precautions.
4.0 1
r---
!2.* *
!2.'
- 1~lIhtnts:ll
~
68 1 2 *2
- 01 I:~~*n' procedures for the facility, including operating those controls associated 4.5 1
~
......*nt that could affect reactivity.
69 1 2.2.04
!Abliity,explain variations in control board layouts, systems, instrumentation, and procedural 3.6 1
1'lVn~ """"'"** units at a facifily.
r---
70
- 2.
1 2 *2
- 41 !Abllity to obtain and interpret station electrical and mechanical drawings.
3.5 1
~
Equipment 95 2.2 07 !knOwledge of the process for conducllng special or infrequent tests 3.6 1
~
Control 96 2.2 17 the process for managing maintenance acIIvlties during power operations, such as risk 3.8 1
work prioritization, and coordination with the transmission sYStem operator.
r--
2.2 1~llhtnts:ll 2
71 2.3 04 of radiation exposure limits under nonnal or emergency conditions.
3.2 1
r--
!Abilily to., radiation monitoring
, such as fixed radiation monitors and alanns, portable SUNel 72 2.3 05 2.9 1
~
I;not",m.."t. """",,,,01 monitoring equipmen~ etc.
97 3,
2.3. 11 !Abllily to control radiation releases.
4.3 1
~ Radiation
,or
,proceDures pena,mng lO
. OUII"S, suen as response 96 Control 2.3.13 !radiation..v.. i.~ ~~.. ~,
3.8 1
~
12.3.
r--
2.3.
1~llhtntA
~
73 2.4.25
- of fire protecllon procedures.
3.3 1
74 2.4. 27 KoowIad"" of "fire in the plant" procedures.
3.4 1
75
- 4.
2.4.43
"". 01 emergency communications sYStems and techniques.
3.2 1
Emergency
- v"~_ vi facHiIy protection requirements, Including fire brigade and I 99 Procedures f 2.4. 26 portable fire fighting equipment usage.
3.6 1
=
Plan 2.4.
2.4.
~llhtnh:d EII+/-
!Tier 3 Point Total