ML040280020

Examination Outline Submittal for Byron Initial Examination - December 2003

ML040280020
Person / Time
Site:	Byron
Issue date:	12/01/2003
From:	Foss T Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
50-454/03-301, 50-455/03-301
Download: ML040280020 (24)

Text

EXAM1 NATION OUTLl N E SUBMITTAL FOR THE BYRON INITIAL EXAMINATION - DEC 2003

Outline Submittal Contains the following:

Letter ES-201-1 ES-201-2 ES-301-1 ES-301-2 ES-301-5 D-1 ES-401-2 ES-401-3 ES-401-4 Admin Exelon cover letter transmitting the Outline Examination Preparation Checklist Examination Outline Quality Checklist Administrative Topics Outline (RO & SRO)

Control Room/ln-Plant System Outline (RO & SRO)

Transient and Event Checklist Dynamic Simulator Scenario Outline for 2 scenarios PWR Examination Outline (RO/SRO)

Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)

Record of Rejected WAS There were no NRC Comments on the submitted test outlines

~

-~

~-

Nuclear Exelon Generation www.exeloncorp.com Byron Generating Station 4450 North German Church Road Byron, IL 61010-9794 Tel815-234-5441 7

W August 18,2003 LTR:

BYRON 2003-0063 File: I

.06.51 I O Mr. James E. Dyer Regional Administrator U. S. Nuclear Regulatory Commission, Region 111 801 Warrenville Road Lisle, IL 60532-4351 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 4

Enclosed are the examination outlines, supporting the initial operator license examination scheduled for the weeks of December I, 2003, through December 12, 2003, at Byron Station.

This submittal includes all appropriate examination standard forms and outlines in accordance with NUREG-1.021, Operator Licensing Examination Standards, Draft Revision 9.

In accordance with NUREG 1021, Draft 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 W. Grundmann, Regulatory Assurance Manager, at (81 5) 406-2800. For questions concerning examination outlines, please contact Tim Foss at (815) 406-3224 or (815) 406-31 11.

Respectfully, Stepheh E. Kuczyncki Site Vice President Byron Nuclear Generating Station SE WDD/ra h 4

August 18,2003 Mr. James E. Dyer Page 2 I

W

Enclosures:

(Hand delivered to Dell McNeil, Chief Examiner, NRC Region Ill)

Examination Security Agreements (Form ES-201-3)

Administrative Topics Outline (Form ES-301-1)

Control Room/ln-Plant Systems Outline (Form ES-301-2)

PWR Examination Outline (Tier I and 2) (Forms ES-401-2 and 401-1)

Generic Knowledge and Abilities Outline (Tier 3) (Form ES-401-3)

Scenario Outline (Form ES-D-1)

Record of Rejected WAS (Form ES-401-4)

Completed Checklists:

Examination Outline Quality Checklist (Form ES-201-2)

Transient and Event Checklist (Form ES-301-5) cc:

(without attachments)

Chief, NRC Operator Licensing Branch NRC Senior Resident Inspector - Byron Station

ES-201 Examination Preparation Checklist Form ES-201-1 Target Date*

-180 Chief Initials drm Task Description / Reference Examiner's

1. Examination administration date confirmed (C.1.a; C.2.a & b) 11

-120 I 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

I drm

-1 20

[-go]

-75 11

-1 20 I 3. Facility contact briefed on security 8. other requirements (C.2.c)

I drm

4. Corporate notification letter sent (C.2.d)

[5. Reference material due (C.l.e; C.3.c)]

6. Integrated examination outline(s) due (C.l.e & f; C.3.d) drm n/a d rm

12. Examinations reviewed with facility licensee (C.l.j; C.2.f & h; C.3.g)

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

14. Final applications reviewed; assignment sheet updated; waiver letters sent (C.2.g, ES-204)

15. Proctoring/written exam administration guidelines reviewed with facility licensee and authorization granted to give written exams (if applicable) (C.3.k) 1 drm

7. Examination outline(s) reviewed by NRC and feedback provided

-70 I to facility licensee (C.2.h; C.3.e) drm drm drm drm

)I

-45

8. Proposed examinations] supporting documentation, and reference materials due (C.l.e, f, g & h; C.3.d)

II

-30 1 9. Preliminary license applications due (C.l.I; C.2.g; ES-202)

I drm

-1 4

-1 4

-1 4

-7

-7

-7

-7 1

drm

10. Final license applications due and assignment sheet prepared (C.l.I; C.2.g; ES-202) 1 drm

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

I drm

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

Target dates 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 to examinations prepared by the NRC.

[ J

ES-201 Examination Outline Quality Checklist Form ES-201-2 and scenarios will not be repeated on subsequent days.

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.

a. Verify that:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks, '

(2) no more than 30% of the test material is repeated from the last NRC examination, (3)* no tasks are duplicated from the applicants' audit test(s), and 8 (4) no more than 80% of any operating test is taken directly from the licensee's exam banks.*

b. Verifythat:

(1) the tasks are distributed among the safety function groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, 4

Facility: lrw Date of Examination: @/!~I/ZOO~

I '

Unittals I

I

&gn b-

&nW A

drt-.

I M

3.

w J

T w

(4) one in1plant task tests the applicant's response to an emergency or abnormal condition, and '

(5) the in-plant walk-through requires the applicant to enter the RCA.

c. Verify that the required administrative topics are covered.

d. 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.

' t 7 t D. b

@Tn-=

(3) 4 - 6 (2 - 3 for SRO-U) of the tasks require the applicant to implement an alternate path I Drocedure. '

1. Author

1. Independent NRC Reviewer initial items in Column "c"' chief examiner concurrence required.

UREG-1021, Draft Revision 9 24 of 25

ES-301 Administrative ToDics Outline Form ES-301-1 Facility: Byron Generatinq Station Examination Level (circle one): @ SRO Date of Examination: December 2003 Operating Test Number:

Administrative (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan

~~

Describe activity to be performed Perform Change to AMAG FW Flow Calorimetric Computer Constant (KA 2.1.19 RO 2.9)

NONE Perform Normal and Reserve Offsite AC Power Surveillance (KA 2.2.12 RO 3.0)

Perform CNMT Vent Release Rad Monitor Setpoint Change (KA 2.3.9 R02.5)

~

Perform NARs Notification with Failure of ENS (KA 2.4.39 RO 3.3) rclOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-I 021, Draft Revision 9 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Bvron Generatinq Station Examination Level (circle one): RO /e Administrative (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Date of Examination: December 2003 Operating Test Number:

Describe activity to be performed Review Shutdown Margin Surveillance and Determine Inadequate (KA 2.1.25 SRO 3.1)

Initiate a LCOAR (KA 2.1.12 SRO 4.0)

Review Normal and Reserve Offsite AC Power Surveillance (KA 2.2.12 SRO 3.4)

Review and Approve a Liquid Release (KA 2.3.6 SRO 3.1)

Classify Event and Fill Out NARS Form (Site Area Emergency due to Release Rate) (KA 2.4.41 SRO 4.1)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless NUREG-1 021, Draft Revision 9 22 of 27

ES-301 Control Room/ln-Plant System Outline Form ES-301-2 Facility: Byron Date of Examination:

2003 Exam Level (circle one)

/ SRO(I) / SRO(U)

Operating Test Number:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title

a. Start the Standby Containment Chiller

b. Respond to a DRPI Failure

c. Swap SX Pumps cSXl6B Closed) (N-I 09)

d. Synchronize a DG to a Bus & Load to >5400 KW (will not load)

(N-I 9a)

e. Decrease SI Accumulator Pressure (N-4)

f.

NI Adjustment following Calorimetric

g. Restore FW per Attachment C of I BEP ES-0.1 (N-121) 7. Perform a Seal Injection Flow Verification Monthly Surveillance.

Safety N, S, L I 5

In-Plant System (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. Local Emergency Start of a Diesel Generator (cranking air valve D, A 6

closed) (N-35c)

Flow Control Valves

i. Remote Shutdown Panel Local Operation of the Aux. Feedwater N

4

k. Local Initiation of C02 to -B Aux Feedwater Pump Room 1

N,A,R [

8 I

I

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow Power, (R)CA 23 of 27 NUREG-I 021, Draft Revision 9

ES-301 Control Roomlln-Plant System Outline Form ES-301-2 Facility: Bvron Date of Examination:

2003 Exam Level (circle one): RO SRO(1) SRO(U) u Operating Test Number:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System I JPM Title

a. Start the Standby Containment Chiller

b. None

c. Swap SX Pumps (-SXt 6B Closed) (N-109)

d. Synchronize a DG to a Bus & Load to >5400 KW (will not load)

(N-1 9a)

e. Decrease SI Accumulator Pressure (N-4)

f.

NI Adjustment following Calorimetric

g. Restore FW per Attachment C of 1BEP ES-0.1 (N-121)

h. Perform a Seal Injection Flow Verification Monthly Surveillance.

In-Plant System (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Safety NIA NIA

i. Local Emergency Start of a Diesel Generator (cranking air valve closed) (N-35c)

i. Remote Shutdown Panel Local Operation of the Aux. Feedwater Flow Control Valves l

4 N

k. Local Initiation of C02 to -B Aux Feedwater Pump Room

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol 23 of 27 NUREG-1021, Draft Revision 9

ES-301 Transient and Event Checklist Form ES-301-5 OPERATING TEST NO.: 2003 Applicant I

Evolution I Minimum I Scenario Number I

Reactivity I*

1 1

1 Normal 0

1 1

1 Instrument /

2*

2,4 3,8 3,4 2,5, 2,4 3,5 Component 6,8 $6 Major 1

5,6,7 5,6,7 7. 7 7,8 7,8 Instructions: (1)

Enter the o erating test number and Form ES-D-1 eent numbers for each evolu P ion type.

abnorma Y conditions (refer to Section D.5.d) but must be signifcant per replaced with addi P ional instrument or component malbnctions on a one-nt malfinctions should ns that provide insi ht m urn requiremen?.

(2)

Reactivit manipulations may be conducted under normal or controlled Section C.2.a of A pendix D.

• Reactivity and normal evolutions may be for-one basis.

Author:

NRC Reviewer:

NUREG-I 021, Draft Revision 9 24 of 26

Simulation Facility Byron ScenarioNo. 1 Operating Test No. 2003 Examiners :

Applicant:

SRO Preload Initial Conditions:

Turnover: 100% power. 1A CS Pump is 00s for a motor bearing replacement. 1C HD pump is 00s for an alignment and vibration problem.

IC-21, 100% power, BOL, equilibrium Xenon, steady state RPO2A&B 1

CSOlA Fw35c ED06H SRO N BOP SRO 1 SI8801B will not open automatically. Will open manually fiom MCB Ramp down turbine power to 1000 Mwe at directed MWlmin Event

, Type*

M RO SRO BOP 2

3 4

5 6

7 8

M BOP R RO Lower reactor power using rods and/or boration.

SRO RX21A I

RO PT-455 Controlling Pressurizer Pressure channel fails high SRO RX03E, 4.8 I BOP Steam Flow Transmitter FT-532 (input to controlling channel) fails high.

SRO RD09,8 C RO Automatic rod motion fails at 8 step per minute.

SRO EDO5D M BOP RP09A RO (Loop 1D) ATWS SRO RP02A,B BOP SRO BOP pressure SRO (OR) CSOlB C BOP Failure of CS to auto actuate.

MRF RP63 RO SAT feed breaker to bus 159 trips opens, no ABT. Loss of RCS flow M RO Reactor Trip Breakers fail to open / ATWS THO6 M RO Large Break LOCA inside containment. Leads to high-3 containment SRO Event Description Failure of RTB A&B to auto AND manual open. (can be opened locally) 1A CS pump 00s Failure of CS to Actuate on Hi-3 Cnmt Press. Train B CS must be manually started from the MCR 1C HD pump 00s 6.9KV Breaker 1591 fails to ABT.

Preload I (preload note)

I C RO I 1 SI8801A will not auto open nor open fiom the MCB I

I I

I I

I I

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

Simulation Facility Byron Scenario No. 2 Operating Test No. 2003 I BOP SRO Examiners:

Component Cooling (CC) Surge Tank level transmitter level tree leak results in auto makeup and 1B CC pump trip with Applicant:

SRO M BOP Initial Conditions:

Turnover: Ramp to full power requested by Electric Operations. 1A MFP is out of service due to breaker cubicle IC-18,76% power, steady state, BOC.

failure of 1A CC pump auto start on low header pressure.

1A SG Feed line break (2 MLB/HR) inside containment. 4 work.

RO SRO Event No.

Preload faulted steam generators.

All MSNs fail to Close. Stuck open 4

C BOP SRO 5

Pre-loaded. 1A AFW pump fails to start. 1B AFW can only be manually started.

6 7

8 11 Malf. No.

FW48B FW43 RP30 OUT RP37 OUT MSOlA 75 MSOlB 80 MSOlC 60 MSOlD 90 FW45E, 100 Override ZDIlAFO13E AUTO

~

~~~

I Byron 2003 NRC Exam 1

Scenario 03-2 RX29C 65 RX13A, 0 CV09,50 MS04D, 100 CC03B cco 1 c CC02A FWl9A, 2.0 (Pre-loaded) 1A and 1B AFW pumps fail to Start Event I

Event Type*

Description C BOP C BOP 1B AFW pump fails to auto start, can be manually started.

1A AFW pump fails to auto or manually start.

CBoP Failure of Phase A valves to close I

C RO All MSIVs fail partially open, no closure available.

BOP SRO C BOP 1AF005E potentiometer fails to 100% demand.

C BOP lAF013E stuck open.

SRO I R RO SRO N BOP Raise Reactor Power using rods and dilution Ramp up turbine power from 76% to full power.

C BOP I Steam Generator 1C FRV Controller card failure resulting in SRO manual control of FRV I RO 1LT-459, Controlling PZR Level Channel fails low.

SRO I TCV-130A modulates closed C R o SRO I C BOP SRO lMSOl8D, 1D SG PORV fails open.

IL--__

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

ES-401 PWR Examination Outline FORM ES-401-2

-acility Name:Byron Date of Exam: 12/01/2003 I

I RO WA Cateaorv Points

3. Generic Knowledge and Abi I i ti es Categories dote: 1.

Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the Tier Totals in each WA category shall not be less than two). Refer to Section D.l.c for additional guidance regarding SRO sampling.

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.

Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryhier.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

2.

3.

4.

5.

6.*

7.

8.

9.

ES-401-3.

NUREG-1021, Draft Revision 9 22 of 34

00026 Loss of Component Cooling Water I 8 U

00056 Loss of Off-site Power I 23 of 34 NUREG-1021, Draft Revision 9

NUREG-1 021, Draft Revision 9 24 of 34

NUREG-1021, Draft Revision 9 25 of 34

PWR Examination Outline Form ES-401:

ES-401 NUREG-1 021, Draft Revision 9 26 of 34

PWR Examination Outline Form ES-401-ES-401 Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (SRO) 0 2

1 0008 Pressurizer Vapor Space Accident / 3 0001 1 Large Break LOCA / 3 00017 RCP Malfunctions (Loss of RC Flow) 14 00025 Loss of RHR System / 4 4.6 1

Proper actions to be taken it the automatic safetyfunctions have not taken place 4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and 4

1 RCP tripping requirements 4.3 1

Maintaining D/Gs available to provide standby power 4.5 1

When to jog RCPs during ICC controls.

3.8 1

23 of 34 4.4 Actions contained in EOP for loss of vital ac electrical instrument bus A

2 1 4 0

1 WA Topic(s)

01.

28 3.3 1

Knowledge of the purpose and function of major system components and controls.

0 0

0 2 !

2 Group Point Total:

7 0

0 0

0 I I 110 I I I

I o NUREG-1021, Draft Revision 9

)ES-401 PWR Examination Outline Form ES-401-E/APE#/Name/SafetyFunction K

K K

A A

G WA Topic(s) 1 d

1 300001 Continuous Rod Withdrawal I1 000003 Dropped Control Rod / 1 000005 InoperableIStuck Control Rod / 1 05 RPI 300028 Pressurizer Level Malfunction I 2 000032 Loss of Source Range NI I 7 000033 Loss of Intermediate Range NI I7 300036 Fuel Handling Accident I 8 0

0 0

0 000067 Plant Fire On-site I 9 8 300068 Control Room Evac. / 8 300069 Loss of CTMT Integrity/ 5 0

0

~~

~~

((000037 Steam Generator Tube Leak I 3 1

1 1

1 1

1 1

1 7 u

W/E14 High Containment Pressure I 5 000074 Inad. Core Cooling I 4

W/E06 Degraded Core Cooling I 4 0

WE07 Saturated CoreCooling /4 000076 High Reactor Coolant Activity/ 9 Lom-eins, including instrumentation, signals, interlocks. failure modes, and WIEOI Rediagnosis I 3 01 m r W/E02 SI Termination I 3 W/EI 3 Steam Generator Over-pressure I 4 WIE15 Containment Flooding I 5 WIE16 High Containment Radiation I 9

-+

WE09 Natural Circulation Operations I 4 WE10 Natural Circulation with Steam Voide in Vessel withlwithout RVLIS. I 4 WE08 RCS Overcooling - PTS I 4 WA Category Totals:

1 1

0 1

2 0 Group PointTotal:

1 1

1 1

1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

/E03 LOCA Cooldown - Depress. / 4 5

25 of 34 NUREG-1021, Draft Revision 9

ES-401 PWR Examination Outline Form ES-401; A

NUREG-1021, Draft Revision 9 26 of 34

I ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-:

27 of 34 NUREG-1021, Draft Revision 9

ES-401 Record of Rejected WAS Form ES-401-4

.I.

s..<. -.

Tier I Randomly Group 1 Selected WA SRO 111 000007A1.09 SRO1/1 I

000008K2.02

~~

~~

000061 K3.01 SRO 2/1 008000K2.02 Reason for Rejection Unable to write a SRO level question. Replaced with KA 000007A2.02 Unable to write a SRO level question. Replaced with KA 0000082.4.49 Unable to write a SRO level question. Replaced with KA 000061 AA2.06 Unable to write a SRO level question. Replaced with KA 008000A2.02 Unable to write a SRO level question. Replaced with KA 0100002.1.32 SRO2/1 I 012000A3.07 Unable to write a SRO level question. Replaced with KA 01 2000A2.02 SRO 212 01 5000K6.03 194001 2.4.33 ii

~

~~

~~~

Unable to write a SRO level question. Replaced with KA 01 5000A2.03 Unable to write a SRO level question. Replaced with KA 1940012.4.8 NUREG-1021, Draft Revision 9 28 of 34