ML022490089

Draft - Outlines

ML022490089
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	05/28/2002
From:	Gosekamp M Entergy Nuclear Vermont Yankee
To:	Todd Fish NRC/RGN-I/DRS/OSB
Conte R
References
50-271/02301, BVY 02-36, TDL 02-005 50-271/02301
Download: ML022490089 (18)

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NUCLEAR POWER CORPORATION 40C/oA4 185 Old Ferry Road, Brattleboro, VT 05301-7002

/

(802) 257-5271

-2 P/9/ 1:56 May 28, 2002 BVY 02-36 TDL 02-005 Regional Administrator, Region I Attn: Todd Fish U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pa. 19406-1415

References:

(a)

License No. DPR-28 (Docket No. 50-271)

Subject:

SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS -

VERMONT YANKEE, AUGUST 2002 Enclosed are the examination outlines for the exam to be given to the license candidates at Vermont Yankee the week of August 12, 2002. Included also are the K/A'S that were excluded from the written exam with justifications for exclusion.

The enclosed materials are to be withheld from public disclosure until after the related licensing examination is complete.

If you have any questions, please contact Mr. Mike Gosekamp, Operations Training Manager, in our Brattleboro office at (802) 258-4161.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION Mike Gosekamp Operations Training Manager c:

USNRC Resident Inspector - VYNPS (Attachments Withheld from Public Disclosure)

USNRC Project Manager - VYNPS (Attachments Withheld from Public Disclosure)

Document Control Desk (Attachments Withheld from Public Disclosure)

Vermont Department of Public Service (Attachments Withheld from Public Disclosure)

ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: Vermont Yankee Date of Exam: Aug 12, 2002 Exam Level: SRO K/A Category Points Point Group K

K K

A A

A A

G Total 1

2 3

4 5

6 1

2 3

4 15 1

54 4

i 26 Emergency &

Abnormal Plant 3

17 Evolutions 2

3 3

.2 1

T ier 8

8 6

7 7

43 Totals 1

3 2

2 2

2 2

2 2

2 1

3 23 2.

Plant Systems 2

1 1

1 1

2 1

1 1

1 1

2 13 0

0 0

1 0

1 1

0 0

0 1

Tier 4

3 3

4 4

4 4

3 3

2 6

40 3

Totals

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 l 5 lll 17 Note: 1.

Ensure that at least two topics from every KIA category are sampled within each tier (i.e., the "Tier Totals" in each K/A 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 exam must total 100 points.

3.

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.

4.

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

5.

The shaded areas are not applicable to the category/tier.

6.*

The generic K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

BWR SRO imination Outline Printed:

05/16/'

Facility:

ES - 401 Ver... t Yankee Emergency and Abnormal Plant Evolutions - Tier I / Group 1 Form ES-401-1 E/APE #

E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic I

Points 295006 SCRAM / I X 2.4.29 - Knowledge of the emergency plan.

4.0 1

295006 SCRAM / 1 X

AK 1.02 - Shutdown margin 3.7 1

295007 High Reactor Pressure /3 X

AK1.04 - Turbine load 2.8 1

295007 High Reactor Pressure / 3 X

AK3.05 - Low pressure system isolation 3.2 295009 Low Reactor Water Level / 2 X

AK3.01 - Recirculation pump run back: Plant-Specific 3.3 1

295013 High Suppression Pool Temperature /5 X

AK2.01 - Suppression pool cooling 3.7 295013 High Suppression Pool Temperature / 5 X

AAl.01 - Suppression pool cooling 3.9 I

295014 Inadvertent Reactivity Addition / 1 X _

AA2.04 - tViolation of fuel thermal limits 4.4 1

295014 Inadvertent Reactivity Addition / I X

AK3.01 - Reactor SCRAM 4.1 1

295016 Control Room Abandonment / 7 X

AK3.03 - Disabling control room controls 3.7*

1 295016 Control Room Abandonment / 7 X

AA2.03 - Reactor pressure 4.4*

1 295017 High Off-Site Release Rate /9 X 2.4.7 - Knowledge of event based EOP mitigation 3.8 I

strategies.

295017 High Off-Site Release Rate / 9 X

AKI.02 - tProtection of the general public 4.3*

1 295023 Refueling Accidents / 8 X

AKI.01 - Radiation exposure hazards 4.1 1

295023 Refueling Accidents / 8 X

AK2.04 - RMCS/Rod control and information system 3.4 1

I

BWR SRO amination Outline Printed:

05/16 Facility:

Ve.

sit Yankee rmepruenov and Ahnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-1

i - 4U1.

E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.

Points 295024 High Drywell Pressure / 5 X

EKl.01 - Drywell integrity: Plant-Specific 4.2*

1 295024 High Drywell Pressure / 5 X

EK2.17 - Auxiliary building isolation logic:

3.3 1

Plant-Specific 295025 High Reactor Pressure / 3 X

EAI.07 - ARI/RPT/ATWS: Plant-Specific 4.1 1

295026 Suppression Pool High Water Temperature / 5 X

_ EK2.03 - Suppression chamber pressure: Mark-I&II 3.6 1

295026 Suppression Pool High Water Temperature / 5 X 2.1.33 - Ability to recognize indications for system 4.0 1

operating parameters which are entry-level conditions for technical specifications.

295031 Reactor Low Water Level /2 X

EA2.02 - Reactor power 4.2*

1 295031 Reactor Low Water Level / 2 X

EK3.03 - Spray cooling 4.4*

1 295037 SCRAM Condition Present and Reactor Power Above X

EA 1.06 - Neutron monitoring system 4.1 1

APRM Downscale or Unknown / I 295038 High Off-Site Release Rate / 9 X 2.4.7 - Knowledge of event based EOP mitigation 3.8 1

strategies.

500000 High Containment Hydrogen Concentration / 5 X

EA2.02 - Oxygen monitoring system availability 3.5 1

500000 High Containment Hydrogen Concentration / 5 X

EA1.06 - Drywell sprays 3.4 1

K/A Category Totals:

5 4

5 4

4 4

Group Point Total:

26 2

BWR SRO imination Outline Printed:

05/16/

Facility:

Vera

.it Yankee F.mrr-n--v

œnd Ahnnrmnl Plnnt Evolutions - Tier 1/ GrouD 2 Form ES-401-1 Lb-41.I E/APE #

E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp Points 295002 Loss of Main Condenser Vacuum / 3 X 2.1.6 - Ability to supervise and assume a management 4.3 1

role during plant transients and upset conditions.

295004 Partial or Complete Loss of D.C. Power / 6 X

AA2.04 - System lineups 3.3 I

295004 Partial or Complete Loss of D.C. Power / 6 X

AK3.01 - tLoad shedding: Plant-Specific 3.1 1

295005 Main Turbine Generator Trip / 3 X 2.4.7 - Knowledge of event based EOP mitigation 3.8 1

strategies.

295005 Main Turbine Generator Trip / 3 X

AK2.08 - A.C. electrical distribution.:

3.3 1

295008 High Reactor Water Level / 2 X

__ AK2.04 - PCIS/NSSSS: Plant-Specific 3.3 I 295008 High Reactor Water Level /2 X

AK3.05 - HPCI turbine trip: Plant-Specific 3.6 1

295012 High Drywell Temperature / 5 X

AA2.02 - Drywell pressure 4.1 1

295012 High Drywell Temperature / 5 X

AK1.01 - Pressure/temperature relationship 3.5 1

295018 Partial or Complete Loss of Component Cooling X

AAI.03 - Affected systems so as to isolate damaged 3.4 1

Water / 8 portions 295021 Loss of Shutdown Cooling / 4 X

AK3.04 - Maximizing reactor water cleanup flow 3.4 I

295021 Loss of Shutdown Cooling / 4 X

AK2.04 - Component cooling water systems:

3.1 1

Plant-Specific 295022 Loss of CRD Pumps / I X

AK 1.01 - Reactor pressure vs. rod insertion capability 3.4 295028 High Drywell Temperaturer/ L X

EAL.01 - Drywell spray: Mark-I&II 3.9 1

2909 High Suppression Pool Water Level / 5 1X EA2.03 - Drywelllcontainment water level 3.5 1

I

Facility:

Vei.

.it Yankee ES - 401 BWR SRO amination Outline Printed:

05/16/'

Emergency and Abnormal Plant Evolutions - Tier I/ Group 2 Form ES-401-1 E/APE # IE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp Points 295033 High Secondary Containment Area Radiation Levels /

X EK1.03 - tRadiation releases 4.2*

1 9

295034 Secondary Containment Ventilation High Radiation /

X 2.2.15 - Ability to identify and utilize as-built design 2.9 1

9 and configuration change documentation to ascertain expected current plant configuration and operate the plant.

K/A Category Totals:

3 3

3 2

3 3

Group Point Total:

17 2

BWR SRO E iination Outline Printed:

05/l/

U2 Facility:

Vermont Yankee E1S - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-1 Sys/Ev 1 System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 202002 Recirculation Flow Control System / I X

K 1.10 - Rod pattern 2.6 203000 RHR/LPCI: Injection Mode (Plant X

Kl.16 - Component cooling water systems 3.2 Specific) /2.

203000 RHR/LPCI: Injection Mode (Plant X

K6.01 - A.C. electrical power 3.7 I

Specific) /2 2 209001 Low Pressure Core Spray System /2 X

K4.05 - Pump minimum flow 2.6 1

209001 Low Pressure Core Spray System / 2 X

K5.04 - Heat removal (transfer) mechanisms 2.9 211000 Standby Liquid Control System / I X 2.4.16 - Knowledge of EOP implementation 4.0 1

hierarchy and coordination with other support

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _p r o c e d u r e s.

211000 Standby Liquid Control System / I X

K2.02 - Explosive valves 3.2*

1 215005 Average Power Range Monitor/Local X

A3.06 - Maximum disagreement between flow 3.1 Power Range Monitor System / 7 comparator channels: Plant-Specific 215005 Average Power Range Monitor/Local X

A4.04 - LPRM back panel switches, meters and 3.2 1

Power Range Monitor System /7 indicating lights 217000 Reactor Core Isolation Cooling X 2.2.10 - Knowledge of the process for 3.3 1

System (RCIC) / 2 determining if the margin of safety, as defined in the basis of any technical specification is reduced by a proposed change, test or experiment.__

218000 Automatic Depressurization System /

X A2.02 - Large break LOCA 3.6*

1 3

I

BWR SRO E tination Outline Printed:

05/1'

)2 Facility:

Vermont Yankee fl f

~C_ _

I. (h.-'.n 1 Form ES-401-1 ES - 401 r__at Oy__

_L_

l.

_ _-)

Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 223001 Primary Containment System and X

K2.08 - Containment cooling air handling units:

3.0*

1 Auxiliaries / 5 Plant-Specific 223001 Primary Containment System and X

K6.08 - Containment atmospheric control 3.4 1

Auxiliaries / 5 223002 Primary Containment Isolation X

Kl.06 - Recirculation system 3.2 1

System/Nuclear Steam Supply Shut-Off / 5 223002 Primary Containment Isolation X

AI.03 - SPDS/ERIS/CRIDS/GDS:

2.8*

1 System/Nuclear Steam Supply Plant-Specific Shut-Off / 5 226001 RHR/LPCI: Containment Spray X 2.3.2 - Knowledge of facility ALARA program.

2.9 1

System Mode / 5l 241000 Reactor/Turbine Pressure Regulating X

K3.01 - Reactor power 4.1 1

System /3 261000 Standby Gas Treatment System /9 X

Al.04 - Secondary containment differential 3.3 1

___ pressure 261000 Standby Gas Treatment System /9 X

A3.03 - Valve operation 2.9 1

262001 A.C. Electrical Distribution / 6 X

K3.03 - D.C. electrical distribution 3.2 1

262001 A.C. Electrical Distribution / 6 L

K5.02 - Breaker control 2.9 1

290001 Secondary Containment / 5 X

K4.02 - Protection against over pressurization:

Plant-System 3.5 I

2

BWR SRO E lination Outline Printed:

05/1 02 Facility:

Vernont Yankee ES - 401 Plant Systems - Tier 2/ Group I Form ES-401-1 Sys/Ev #_ System / Evolution Name KI l K2 K3 K4 K5 K6 Al I A2 A3 A4 I G KA Topic Imp.

Points 290001 Secondary Containment 5 X

A2.04 - High airborne radiation 3.7 1

K/A Category Totals:

3 2

2 2

2 2

2 2

2 1

3 Group Point Total:

23 3

BWR SRO F iination Outline Printed:

05/1 02 Facility:

ES - 401 Vermont Yankee Plant Systems - Tier 2 / Group 2 Form ES-401-1 SsE.

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Points 201001 Control Rod Drive Hydraulic System /

X 2.2.33 - Knowledge of control rod 2.9 1

programming.

214000 Rod Position Information System /7 X

K5.01 - Reed switches 2.8 1

219000 RHR/LPCI: Torus/Suppression Pool X

K4.05 - Pump minimum flow protection 3.2 1

Cooling Mode / 5 234000 Fuel Handling Equipment / 8 X 2.1.11 - Knowledge of less than one hour 3.8 1

technical specification action statements for systems.

259001 Reactor Feedwater System / 2 X

A2.06 - Loss of A.C. electrical power 3.2 1

259001 Reactor Feedwater System / 2 X

A3.07 - FWRV position 3.2 1

263000 D.C. Electrical Distribution / 6 X

K3.03 - Systems with D.C. components (i.e.

3.8 1

_ valves, motors, solenoids, etc.)

271000 Offgas System /9 X

A4.05 - Station radioactive release rate 3.9 1

272000 Radiation Monitoring System /7 X

K2.03 - Stack gas radiation monitoring system 2.8 1

272000 Radiation Monitoring System / 7 X

K6.03 - A.C. power 3.0 286000 Fire Protection System /8 X

K1.05 - Main generator hydrogen system:

3.1 1

Plant-Specific 286000 Fire Protection System / 8 X

K5.05 - Diesel operations 3.1*

1 I

BWR SRO F lination Outline Printed:

05/11 02 Facility:

Vermont Yankee ES - 401 Plant Systems - Tier 2/ Group 2 Form ES-401-1 Sys/Ev#

System/EvolutionName KI 1K2 K3 K4 1K5 1K6 Al IA2 A3 A4 G KA Topic Imp.

Points 290003 Control Room HVAC / 9

_X Al.04 - Control room pressure 2.8 1

K/A Category Totals:

I I

I 1

2 1

1 1

1 1

2 Group Point Total:

13 2

BWR SRO E iination Outline Printed:

05/1(

'02 Facility:

Vermont Yankee ES - 401 Plant Systems - Tier 2 / Group 3 Form ES-401-1 Sys/Ev #

System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp Points 215001 Traversing In-Core Probe / 7 X

K6.04 - Primary containment isolation system:

3.4 I

Mark-I&II(Not-BWRI) 233000 Fuel Pool Cooling and Clean-up / 9 X

I K4.07 - Supplemental heat removal capability 2.9 239001 Main and Reheat Steam System / 3 X 2.2.17 - Knowledge of the process for managing 3.5 I

_ maintenance activities during power operations.

256000 Reactor Condensate System / 2 X

A 1.10 - Condenser vacuum 3.1 K/A Category Totals:

0 0

0 1

0 1

1 0

0 0

1 Group Point Total:

4 I

Generic Knowledge and Abilities Outline (Tier 3)

Printed:

05/16/2002 BWR SRO Examination Outline Form ES-401-5 Facility:

Vermont Yankee Generic Category KA KA Topic Imp.

Points Conduct of Operations 2.1.11 Knowledge of less than one hour technical specification action statements for systems.

3.8 1

2.1.33 Ability to recognize indications for system operating parameters which are entry-level 4.0 1

conditions for technical specifications.

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

3.3 1

2.1.29 Knowledge of how to conduct and verify valve lineups.

3.3 1

2.1.23 Ability to perform specific system and integrated plant procedures during different modes 4.0 1

of plant operation.

Category Total:

5 Equipment Control 2.2.22 Knowledge of limiting conditions for operations and safety limits.

4.1 1

2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and 3.7 safety limits.

2.2.27 Knowledge of the refueling process.

3.5 1

2.2.11 Knowledge of the process for controlling temporary changes.

3.4*

1 Category Total:

4 Radiation Control 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 personnel exposure.

2.3.6 Knowledge of the requirements for reviewing and approving release permits.

3.1 I

2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.

3.0 I

2.3.2 Knowledge of facility ALARA program.

2.9 Category Total:

4 I

Generic Knowledge and Abilities Outline (Tier 3)

Printed:

05/16/2002 BWR SRO Examination Outline Form ES-401-5 Facility:

Vermont Yankee Generic Category KA KA Topic Imp.

Points Emergency Plan 2.4.8 Knowledge of how the event-based emergency/abnormal operating procedures are used in 3.7 1

conjunction with the symptom-based EOPs.

2.4.11 Knowledge of abnormal condition procedures.

3.6 I

2.4.15 Knowledge of communications procedures associated with EOP implementation.

3.5 1

2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

3.6 1

Category Total:

4 Generic Total:

17 2

ES-301 Administrative Topics Outline Form ES-301-1 ES-30 1 Administrative Topics Outline Form ES-301-1 Facility:

Vermont Yankee Date of Examination:

Aug 12, 2002 Examination Level (circle one):

RO

/

SRO Operating Test Number:

1 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Short Term JPM - Respond to an NRC "Credible Threat" Notification.

Information K&A-2.1.15, RO-2.3, SRO-3.0 Fuel Handling JPM - Determine if Fuel Handling Can Continue With Inoperable SRMs.

K&A-2.1.9, RO-2.5, SRO-4.0 A.2 Surveillance JPM - Review Completed Surveillance and Take Action for Out Testing of Spec Data K&A-2.2.12, RO-3.0, SRO-3.4 A.3 Knowledge of Significant JPM - Locate and Determine Radiological Conditions for Radiation Inspection of Valve Hazards K&A-2.3.10, RO-2.9, SRO-3.3 A.4 Emergency JPM - Classify an Event Based Upon Simulated Plant Conditions Action Levels and K&A-2.4.41, RO-2.3, SRO-4.1 Classifications

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:

Vermont Yankee Exam Level (circle one): RO / SRO(I) / ISRO(UM Date of Examination: Aug 12, 2002 Operating Test No.:

1 B.1 Control Room Systems System / JPM Title

a. SLC/SLC Initiation with failed pump and squib valve

b. MS/MSIV Slow Closure

c. Radiation Monitoring/Protective Action Recommendation B.2 Facility Walk-Through

a. DC/Transfer DC-3A to DC-1 Type Safety Type Code*

D, A, S Safety Function 1

D, S 5

M, A, S, 9

D 1

6 N, R, L 4

b. RHR/Alternate Shutdown

• 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

Appendix D Scenario Outline Form ES-D-1 Aooendix D Scenario Outline Form ES-D-1 Facility:

Vermont Yankee Scenario No.:

1 Op-Test No.:

1 Examiners:

Operators:

Initial Conditions: Reactor Power-85% with all equipment operable.

Turnover: A reactor downpower is underway, utilizing OP-0105, for a rod pattern exchange.

Reactor power is to be reduced to 80% using Recirc. Reactor Engineering is to be notified at 80% Dower and will provide further auidance at that time.

Event Malf.

Event Event No.

No.

Type*

Description 1

NA R, N -

Continue power reduction IAW OP-0105 SRO 2

NM05A I - SRO APRM fails upscale 3

ED03A RR-Loss of Bus 1 due to bus fault.

4 RR01A M - SRO Small break LOCA 5

FW08C M, C -

Scram, Loss of Feedwater and HPCI failure HP01 SRO 6

RC01 C, M -

RCIC trip, RPVED on loww SRO e~vait frp inc/(vde cF.(Ufd

• /1__

{___s:.....

1___

{_______$

{A__

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

Appendix D Scenario Outline Form ES-D-1 Appendix U Scenario Outline Form ES-D-1 Facility:

Vermont Yankee Scenario No.:

1 Op-Test No.:

1evL Examiners:

Operators:

Initial Conditions: Reactor Power-85% with all eguipment operable.

Turnover: A reactordownpoweris underway, utilizing OP-0105, fora rodpattem exchange.

Reactor power is to be reduced to 80% using Recirc. Reactor Engineerinc is to be notified at 80% rower and will provide further auidance at that time.

Event Malf.

l Event Event No.

No.

Type*

Description 1

NA R, N -

Continue power reduction IAW OP-01 05 SRO 2

NM05A I - SRO APRM fails upscale 3

ED03A R R Loss of Bus 1 due to bus fault.

4 RR01A M - SRO Small break LOCA 5

FW08C M, C-Scram, Loss of Feedwater and HPCI failure, RCIC Flow HP01 SRO Controller failure.

RC03 M__to l

e 6

RC01 M - SRO RCIC trip, RPVED on low level I

1 1

I I

I I

I I

7 7 I (N)ormal, (R)eactivity, (I) nstrument, (C)omponent, (M)ajor