ML20155G112
| ML20155G112 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/23/1998 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | Hironori Peterson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20155F786 | List: |
| References | |
| RTR-NUREG-1021 NUDOCS 9811060206 | |
| Download: ML20155G112 (14) | |
Text
O>mmonwealth Edison Company liraidwood Generating Station s
Route 81,llox K4 liraceville. !!. 60407 'X,19 Tel H15-4W2801 j
June 23,1998 Mr. Hironori Peterson U. S. Nuclear Regulatory Conunission Region Ill 801 Warrenville Road Lisle, IL 60532-4351
Dear Mr. Peterson:
Enclosed is the reactor operator written examination outline which Braidwood Generating Station is submitting for review, comment, and approval for the Initial License Examination scheduled for the week of September 14, 1998, at Byron Generating Station.
This outline has been developed in accordance with Interim Revision 8 of NUREG-1021 (" Operator Licensing Examiner Standards").
Please ensure that these materials are withheld from public disclosure until after the examinations are complete.
If you have any questions or concerns regarding this outline, please contact Scott Deprest at (815) 458-3411 extension 2250 or Paul Hippely at (815) 458-3411 extension 2235.
Sincerely, Ti thy J. Tulon e Vice President BraMwood Nuclear Generating Station cc w/o enclosures:
Regulatory Assurance B. Wegner J. Walker L. Weber C. Cerovac P. Hippely
$10gj$0[gabbO$56 T. Berton PDR S. Deprest v
P. DiGiovanna Class File nrc.. 98037tjt. doc A I)nicom Q>mpany
Turnbull, MI hell 3 A.
From:
Bash, Faye A.
Sent:
Tuesday, June 23,1998 8:17 AM T;:
Tumbu:1, Michelle A.
Subject:
FW: NRC ILT Sample Plan Submittal Cover Letter This is for Tim's signature.
---Onginal Message-1 From:
Hippely, Paul J.
l Sent:
Monday, Jun? 22,199811:03 AM TI:
Bash, Faye A.
l
Subject:
NRC ILT Sample Plan Submittal Cover Letter
- Faya, Attached is the sample plan cover letter that will be attached to the sample plan material when submitted to the NRC.
The cover letter requires Site VP/ Station manager signature as directed by Terry Simpkin. Please re-format and place on Braidwood letterhead for signature approval. Dave Hoots will pick up the letter tomorrow, Tuesday, after it has been signed.
Thank you, Paul Hippely SAMPSUB. doc l
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ES-201 Examination Outline Form ES-2012 Ouality Assurance Checklist Factity:
Braidwood Unite 1 and 2 Date of Examination: September 14,1998 initiale item Task Description a
b c
l 1.
- a. Verify that the outline (s) fit (s) the appropriate model per ES-401.
- b. Assess whether all six knowledge and four abiity categories are appropriately sampled.
- c. Assess whether the oudine over-emphasizes any systems, evolutions, or generic topics.
- d. Assess whether the repetition from previous examination oudinee le excessive.
2.
- a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component falures, and maior transiente.
S I
- b. Assess whether there are enough scenario sets (and spares) to teet the projected number M
and mix of applicante in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at least one new scenario and scenarios wpl not be repeated over successive days.
- c. To the extent possible, assess whether the outline (s) conformle) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
3.
- a. Verify that the oudine(s) contain(s) the required number of control room and in-plant tasks and verify that no more than 30% of the test material is repeated from the last NRC W
examination.
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- b. Verify that the tasks are distributed among the safety function groupings as specified in ES-301; one task shall require a low-power or shutdown condition, one or two shall require the applicant to implement an alternate path procedure, and one should require entry to the RCA.
- c. Verify that the required administrative topics are covered, with emphasis on performance, based activities.
- d. Determine if there are enough different oudines to test the projected number and mix of applicante and ensure that no more than 30% of the items are duplicated on successive days.
4.
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appropriate exam section.
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- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
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- c. Ensure that K/A importance ratings (except for plant opecific priorities) are at least 2_5.
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- d. Check for duplication and overlap among exam sections.
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- e. Check the entire exam for balance of coverage.
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- f. Assess whether the exam fits the appropriate job level ('40 or SRO).
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Printedpame / s nature Date ho 77 M. h.orw /.fe/b% b' LAAn.d
- a. Author 4
ff
- b. FacNity Reviewer (*)
bM#/ /Iod d
- c. Chief Examiner
/4/amW/ Mv/%60
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- d. NRC Supervisor M S
- M A M M [C b W f*
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(*) Not applicable for NRC-developed unaml nations NUREG-1021 22 of 24 Interim Rev.
8, January 1997 l
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ES-401 PWR RO Examination Outline Form ES-401-4 c
Facility: Braidwood I & 2 Date of Exam:
September 14,1998 Exam Level: RO K/A Category Points Tier Group Point K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
Total 1.
1 2
2 2
4 6
16 Emergency &
h !
6 2
2 3
2 3
Abnormal Plant
?
"d I
17 Evolutions 3
1 IiE
% lf h
1 1
3 Tier Totals 5
4 6
I1 9
1 36 1
3 2
1 2
2 1
1 2
3 4
2 23 2.
2 2
2 2
2 1
2 2
3 2
2 20 Plant Systems 3
2 1
1 1
1 1
1 8
Tier Totals 7
2 4
5 4
2 3
5 7
7 5
51
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 13 5
3 2
3 Note:
Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.
Actual point totals must match those specified in the table.
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
Systems /cyclutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category / tier.
NUREG-1021 30 of39 Interim Rev. 8, January 1997 i
PWR RO Examination Outline Facility-Brcidwood Exrm D to:
9/14/98 Excmination Level: RO Section Title Generic Knowledge end Abilities
~
. RO Group 1
System / Evolution K/A RO KA Statement Level Question Topic Conduct of Operations 2.1.1 3.7 Knowledge of conduct of operations requirements. 8 Evaluation of requirement for" active" license 2.1.1 3.7 Knowledge of conduct of operations requirements. B Direction of NLO personnel 2.1.2 3.0 Knowledge of operator responsibilities during all B
Operating Daily Orders modes of plant operation.
2.1.14 2.5 Knowledge of system status criteria which require B MOV Stroke Time actions the notification of plant personnel.
2.1.23 3.9 Ability te perform specific system and integrated B
Procedure required usage plant procedures during all modes of plant operation.
Equipment Control 2.2.13 3.6 Know' edge of tagging and clearance procedures. B MSIV OOS Hang to prevent opening 2.2.26 2.5 Knowledge of refueling administrative B
RCS level discrepancy during refueling requirements.
j 2.2.32 3.5 Knowledge of RO duties in the control room during B RO duties in Control Room during refueling fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
Radiation Control 2.3.1 2.6 Knowledge of 10 CFR: 20 and related facility B
Radiation exposure determination radiation control requirements.
2.3.10 2.9 Ability to perform procedures to reduce excessive R Fuel Handling Accident Response l
i levels of radiation and guard against personnel exposure.
Emergency Procedures 2.4.16 3.0 Knowledge of EOP implementation hierarchy and B Performance of Status Trees / Function Restoration
/ Plan coordination with other suppori procedures.
2.4.20 3.3 Knowledge of operationalimplications of EOP B
Applicability of EOP Operator Action Summary Page wamings, cautions, and notes.
2.4.31 3.3 Knowledge of annunciators alarms and B
Identification of inoperable CR annunciators indications, and use of the response instructions.
Tuesday, June 16,1998 4:02:58 PM Page 1 Prepared by WD Associates, Inc.
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PWR RO Examination Outline Facility-Brridwood Ex m D:ta:
9/14/98 Examination Level: RO -
Section Title Pl:nt Systems RO Group '
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System / Evolution K/A RO KA Statement Level Question Topic Control Rod Drive 001 A2.06 3.4 Effects of transient xenon on reactivity B
Effect of Xenon Transient & compensation System 001 K1.03 3.4 CRDM B
Application of DC Hold Reactor Coolant Pump 003 A1.06 2.9 PZR spray flow B
RCP and Pzr spray operations System 003 K2.01 3.1 RCPS R
RCP Breaker & interlocks Chemical and Volume 004 A3.11 3.6 Charging / letdown R
Charging & letdown flows (including seal injection)
Control System 004 A4.07 3.9 Boration/ dilution B
Calculation of RCS Boron dilution 004 K6.01 3.1 Spray / heater combination in PZR to assure R
Boron mixing uniform boron concentration i
Engineered Safety 013 A3.01 3.7* Input channels and logic B
CNMT Spray / Phase B Features Actuation System 013 K413 3.7 MFWisolation/ reset R
FW Isolation - P14 Nuclearinstrumentation 015 A2.02 3.1 Faulty or erratic operation of detectors or B
SR NIS discriminator failure System compensating components 015 K2.01 3.3 NIS channels, components, and interconnections B SR NIS -loss of control power 015 K5.06 3.4 Suberitical multiplications and NIS indications R
Eval for 1/M - Eightfold increase In-Core Temperature 017 K4.01 3.4 Input to subcooling monitors R
CETC failure effect on Subcooling Monitor /lconic Monitor System Display Containment Cooling 2.1.32 3.4 Ability to explain and apply all system limits and R
RCFC operations requirernents System precautions.
Main Feedwater 2.1.7 3.7 Ability to evaluate plant performance and make B
SG Level program -low power System operationaljudgments based on operating characteristics, reactor behavior, and instrument interpretation.
059 K1.04 3.4 S/GS water level control system R
Effect of failure of SG steam pressure channel Auxiliary / Emergency 061 A3.01 4.1 AFW startup and flows B
AFW Startup Feedwater System Tuesday, June 16,1998 4:03:00 PM Page 2 Prepared byWD Associates,Inc.
E R baM b M k Facility Brtidwood Exnm D ta:
9/14/98 Ex mination Level: RO -
Section Title Plant Systems RO Group 1
- System / Evolution K/A RO KA Statement
- Level Question Topic Auxiliary / Emergency 061 K5.02 3.2 Decay heat sources and magnitude B
AFW flow requirements for cooldown Feedwater System Liquid Radwaste 068 A4.04 3.8 Automaticisolation B
RCDT operation - effect of CNMT isolation System 068 K1.07 2.7 Sources ofliquid wastes for LRS R
CNMT Sump sources of input during normal operations -
Waste Gas Disposal 071 A4.05 2.6* Gas decay tanks, including valves, indicators, and R Waste Gas Decay Tank Operations System sample line Area Radiation 072 A4.03 3.1 Check source for operability demonstration R
Check Source operation Monitoring System 072 K3.02 3.1 Fuel handling operations B
Loss of FHB Overhead Crane rad monitor i
L Tuesday, June 16,1998 4:03:01 PM Page 3 Prepared byWD Associates,Inc.
Facility: Brcidwood Exam Data:
9/14/98 Examination Lovel: RO Section Title Plant Systems i-RO Group 2
System / Evolution
=K/A RO KA Statement Level Question Topic Reactor Coolant 002 A1.11 2.7 : Relative level indications in the RWST, the B
Relationship of !evels during refueling operations System refueling cavity, the PZR and the reactor vessel during preparation for refueling t
002 A3.01 3.7 Reactor coolant leak detection system R
RCS leak Detection Systems t
002 K4.09 3.2 ' Operation of loop isolation valves.
R Use of Loop Isolation Valves f
' Emergency Core 006 A2.13 3.9 Inadvertent SIS actuation B
Systems response to SI/ Actions Cooling System p
006 K3.02 4.3 Fuel B
10CFR50.46 Design Criteria 006 K6.03 3.6 Safety injection Pumps
.B Evaluation of flow ECCS pumps
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4 Pressurizer Pressure 010 A1.08 3.2 Spray nozzle DT B'
Spray using Normal and Aux Spray j
Control System 010 K5.01 3.5 Determination of condition of fluid in PZR, using B
Evaluation of Pzr conditions i
j steam tables Pressurizer Level 011 K1.04 3.8 RPS B
Pzr Level ReactorTrip l j
Contml System Reactor Protection 012 A3.07 4.0 Trip breakers R
Operation of BOTH Bypass Trip Breakers
.f System j
012 A4.03 3.6 Channel blocks and bypasses B
Input that can be bypassed & plant conditions
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'012 K5.01 3.3* DNB R
OTdTinputs & effect of changes
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Rod Position Indication 2.4.31 3.3 Knowledge of annunciators alarms and R
ROD BOTTOM Alarm operation System indications, and use of the response instructions.
Non-Nuclear 016 K3.02 3.4* PZR LCS B
NR RTD Failure effects Instrumentation System Containment Spray 026 A2.08 3.2 Safe securing of containment spray when it can B
Sequence for securing CNMT Spray System be done) 026 A4.01 4.5 CSS controls R
Pump operation interlocks l
Spent Fuel Pool Cooling 033 K1.05 2.7* RWST R
RWST Purification Loops System j
Tuesday, June 16,1998 4:03:03 PM Page 4 Prepared byWD Associates,Inc.
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PWR RO Examination Outline Facility Brcidwood
' Ex m Datz 9/14/98 Examination Level: RO Section Trtle Plant Systems RO Group 2
System / Evolution '
K/A
. RO KA Statement Levei Question Topic D.C. Electrical 2.1.30 3.9 Ability to locate and operate components, B
DC bus battery charger Distribution including local controls.
Emergency Diesel 064 A3.07 3.6* Load sequencing B
Sequencing of CNMT Spray pumps - SI & SI w LOP Generators Fire Protection System 086 K4.06 3.0 CO2 B
Effect ofloss of DC - CO2 actuation s
9 Tuesday, June 16,1998 4:03:03 PM Page 5 Prepared byWD Associates,Inc.
PWR RO Examination Outline Facility Brmidwood Exam D;ts:
9/14/98 Ex mination Level: RO Section Title Plant Systems RO Group 3
System / Evolution K/A RO KA Statement Level Question Topic Residual Heal Pe"" val 005 K1.12
- 3.1 Safeguard pumps B
Recire interties to S1 Pumps & CV Pumps System 005 K4.10 3.1 Control of RHR heat exchanger outlet flow R
Failure of Hx Outlet Valve Pressurizer Relief 2.4.50 3.3 Ability to verify system alarm setpoints and R
PRT conditions causing alarm / response Tank / Quench Tank operate controls identified in the alarm response System manual.
Component Cooling 008 A2.05 3.3* Effect of loss of instrument and control air on the R.
Determination of effect of va!ve positioning Water System position of the CCW valves that are air operated Containment lodine 027 A4.03 3.3* CIRS fans R
Charcoal Filters response to deluge Removal System Steam Dump System 041 A3.02 3.3 RCS pressure, RCS temperature, and reactor B
Steam Dump input malfunction end Turt>ine Bypass power Centro!-
Main Turbine Generator 045 K1.20 3.4 Protection system R
Turbine Control response to Failed impulse Channel System Instrument Air System 078 K3.02 3.4 Systems having pneumatic valves and controls B
Evaluation of eqpt affected for slow loss of lA Tuesday June 16,1998 4:03:04 PM Page 6 Prepared byWD Associates,Inc.
PWR RO Ex mination Outline Facility: Brcidwood Exam Data:
9/14/98 Examination Lcvel: RO Section Title Em;rg:ncy (nd Abnormal Pl;nt Evolutions RO Group 1
System / Evolution K/A RO KA Statement Level Question Topic Reactor Coolant Pump 015 AA2.10 3.7 When to secure RCPs on loss of cooling or seal B
Evalloss of cooling flow (CCW)
Malfunctions injection 015 AK2.07 2.9 RCP seals B
Eval of RCP seal failure Emergency Boration 024 AA2.05 3.3 Amount of boron to add to achieve required SDM B Time / amount E-boration for condition Loss of Component 026 AA1.05 3.1 The CCWS surge tank, including level control and B Evaluation of CCWleak Cooling Water level alarms, and radiation alarm Pressurizer Pressure 027 AA1.01 4.0 PZR heaters, sprays, and PORVs B
Pressure controller step change Control Malfunction 027 AA2.15 3.7 Actions to be taken if PZR pressure instrument B
Non-Controlling channel failure fails high Steam Une Rupture 040 AA1.01 4.6 Manual and automatic ESFAS initiation B
Steamline isolation 040 AK1.06 3.7 High-energy steam line break considerations B
Eval of Leak Loss of Condenser 051 AA2.02 3.9 Conditions requiring reactor and/or turbine trip B
Eval of conditions V;;cuum Station Blackout 055 EK3.02 4.3 Actions contained in EOP forloss of offsite and B
Identification of RCP seal LOCA/cooldown onsite power Loss of Vital AC 057 AA2.19 4.0 The plant automatic actions that will occur on the B Eqpt affected on bus loss instrument Bus loss of a vital ac electricalinstrument bus Control Room 068 AA1.21 3.9 Transfer of controls from control room to shutdown B Operations required for transfer Evacuation panel orlocal control inadequate Core 074 EK1.03 4.5 Processes for removing decay heat from the core B Major action categories Cooling High Reactor Coolant 076 AA2.02 2.8 Corrective actions required for high fission product B Actions for reducing activity Activity activity in RCS Pressurized Thermal E08 EK2.2 3.6 Facility's heat removal systems, including primary B Identification of heat removal process Shock coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the faciiity.
Tuesday, June 16,1998 4:03:06 PM Page 7 Prepared by WD Associates, Inc.
MWt RO Examination Outlinei Facility: Brcidwood.
.' Ex:m Datx 9/14/98 Ex:mination Levet RO :-
Section Title Emergency and Abnorm I PI:nt Evolutions RO Group.
1 System / Evolution K/A -
. RO KA Statement Level Question Topic -
Natural Circulation E09 EK3.1 -
3.3 Facility operating characteristics during transient B Natural Circ conditions and limits Operations.-
- conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity
. changes and operating limitations and reasons for y
these operating characteristics.
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s Tuesday, June 16,1998 4:03:06 PM Page 8 Prepared by WD Associates, Inc.
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PWR RO Examination Outline Facility-Brcidwood Exam Data:
9/14/98 Examination Level: RO Section Title Emergency and Abnormal Pitnt Evolutions RO Group 2
System / Evolution K/A RO KA Statement Level Question Topic -
Continuous Rod 001 AA2.05 4.4 Uncontrolled rod withdrawal, from available B
Evaluate conditions - unwarranted rod withdrawal Withdrawal indications Dropped Control Rod 003 AK3.10 3.27 Rlland PDIL B
P/A vs. Group Step Counters Reactor Trip 007 EA1.03 4.2 RCS pressure and temperature B
Stabilized RCS temperature with failure of Steam Dumps 007 EK2.03 3.5 Reactortrip status panel R
Reactor Trip requirements Pressurizer Vapor 008 AK1.01 3.2 Thermodynamics and flow characteristics of open R Tail-Pipe conditions Space Accident or leaking valves Small Break LOCA 009 EA1.10 3.8* Safety parameter display system B
Calculation of subcooled margin on iconic Display Larg Break LOCA 011 EA1.03 4.0 Securing of RCPs B
RCP trip criteria evaluation Loss of ReactorCoolant 022 AA1.08 3.4 VCTlevel B
VCTlevel tr mitter malfunction
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Makeup Loss of Residual Heat 025 AK1.01 3.9 Loss of RHRS during all modes of operation B
Calc of time to saturation / core boiling Removal System 025 AK3.01 3.1 Shift to attemate flowpath B
Altemate RCS cooling Anticipated Transient 2.4.48 3.5 Ability to interpret control room indications to B
AMS conditions Without Scram verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.
Loss of Source Range 032 AK1.01 2.5 Effects of voltage changes on performance B
Evaluation of SR NIS voltage failure Nuclear instnamentation i'
Loss of Intermediate 033 AA2.04 3.2 Satisfactory overlap between source-range, E
of failed IR channel on SU Range Nuclear intermediate-range and power-range Instrumentation instrumentation Steam Generator Tube 037 AA1.02 3.1* Condensate exhaust system R
Monitors for SG Tube leakage Leak Steam Generator Tube 038 EK3.06 4.2 Actions contained in EOP for RCS waterinventory B Loss of subcooling Rupture balance, S/G tube rupture, and plant shutdown procedures i
Tuesday, June 16,1998 4:03:08 PM Page 9 Prepared by WD Associates, Inc.
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Facility: Braidwood Ex m Data:
9/14/98 Exr_mination Level: RO Section Title Emergency and Abnormal Plant Evolutions RO Group' 2
System / Evolution K/A RO KA Statement Level Question Topic Loss _of Secondary Heat EOS EK2.1 3.7 Components, and functions of cor. trol and safety B Interiocks affecting reestablishment of feed Sink systems, including instrumentation, signals, inteiiocks, failure modes, and automatic and manual features.
Loss of Emergency E11 EA1.1 3.9 Components, and functions of control and safety B Reason for rapid SG depressurization -
Coolant Recirculation systems, induding instrumentatior,,' signals, intertocks, failure modes, and automatic and manual features.
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Tuesday, June 16,1998 4:03:09 PM Page 10 Prepared by WD Associates, Inc.
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Facility Braidwood Ex m D:ta:
9/14/98 Ex mination Level: RO
- Section Title Emergency and Abnormil PI:nt Evolution RO Group 3-System / Evolution K/A~
RO KA Statement Level Question Topic Pressurizer Level 028 AK3.05 3.7 Actions contained in EOP for PZR level -
B ~ Failed level channellow.
Control Malfunction malfundion Loss of Off-Site Power 056 AA1.21 3.3* Reset of the ESF load sequencers B
Reset of sequencer 056 AA2.4'3 4.2 That the ED/Gs have started automatically and B
Eval of electric bus status that the bus tie breakers are closed L
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L Tuesday, June 16,1998 4:03:09 PM Page 11 Prepared by WD Associates, Inc.