Text

Transmits Proposed Integrated Exam Outline for 971103 Licensing Exam at Plant
	ML20217Q531
Person / Time
Site:	FitzPatrick
Issue date:	08/22/1997
From:	Michael Colomb; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Meyer G; NRC
Shared Package
ML20217Q521	List: JAFP-97-0309, Transmits Proposed Integrated Exam Outline for 971103 Licensing Exam at Plant; JAFP-97-0357, Transmits Written Exams for 971103 Licensing Exam at Plant. Remaining Exam Matls Will Be Forwarded,Per Schedule Agreed Upon by D Florek & Je Morris; ML20217Q518;
References
	JAFP-97-0309, JAFP-97-309, NUDOCS 9803120284
	Download: ML20217Q531 (51)
	v • d • e

Jarnes A. FitzPatrick Nuclear Power Plant P.O. Bom 41 Lycoming. New York 13093 315-342 3840 A NewYo.rkPower ri-n ,ia Coiome tv Authonty vecce Oner August 22, 1997

.JAFP-97-0309 s

Mr. Glenn W. Meyer Chief Operator Licensing and Human Performance Branch Division of Reactor Safety United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415

SUBJECT:

SENIOR REACTOR OPERATOR AND REACTOR INITIAL EXAMINATONS - J.A. FITZPATRICK, DOCKET 50-333 TRANSMITTAL OF PROPOSED EXAMINATION OUTLINES

Dear Mr. Meyer:

As directed by your letter of July 18, 1997, this letter transmits the proposed integrated examination outline for the November 3, 1997 licensing examination at the James A.

FitzPatrick Nuclear Power Plant.

The examination outlines are contained within the enclosed, sealed envelope that is conspicuously marked "FOR OFFICIAL USE ONLY" and "TO BE OPENED BY ADDRESSEE ONLY."

Attachment 1 to Section ES-201 of NUREG-1021, Operator Licensino Examination Standards for Power Reactors, requires that I direct you to withhold these materials from public disclosure until after the examinations are complete.

If you have any further questions, please contact James E.

Morris at (315) 349-6480.

~

Very truly yours,

\

l -

\

MI 'L J. CO A ...'

MJC/JEM/smz h

Enclosure:

Sealed envelope containing examination outlines.

cc w/o enc: D. Florek - Chief Examiner C. Faison - Director, Nuclear Licensing, NYPA J. Maurer - General Manager of Support Services

, A. Zaremba - Licensing, JAF RMS File l 9003120284 980309 j PDR ADOCK 05000333 l V pg

ES-201 Examination Outlins Form ES-201-2 Quality Assurance Checklist l

l Facihty: J.A. FitzPatrick NPP Date of Examination:11J03/97 Stem Task Description a b c 1

a. Verify that the outhne(s) fit (s) the oppropriate model per ES 401.

WTN

b. Assess weiether all sin knowledge and four ability categories are appropriately sesspied. e4

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. M

d. Assess whether the repetition from previous enemination outlines is oncessive. e4

2. a. Using Form ES-301-5, verify that the proposed scenarie sets cover the required number of normal evolutions, instrument and component failures, and major transients, g

b. Assess whether there are enough scenetto este (and operes) to test the pregocted number and mim of map = ate in accordance with the espected crew compoestson and rotation schedule withest compromsesng esem integrity,eneere each applicant can be g tested using at toast one new scenario and scenarios will not be toposted over successive days.

c. To the entent possible, ====== whether the outline (s) conform (s) with the quaestative and quantitatsve criterie specilled on Form E8-301-4 and described in Appendia D. g

3. a. Verify that the estiine(s) centsin(s) the required number of centrol room and in-pient teoks and wortfy that no amore than 30% of the test materialis repeated from the lost g WIT NRC examination.

b. Verify that the tasks are distributed among the safety lunction groupings as specified in ES-301; one task stall require a low-power or shutdown condition, one or two shall require the applicant to inspiement an alternate path procedure, and one shovid M require entry to the RCA.

c. Verify that the required administrative topics are covered, with emphasis on performance-based activities. M

d. Determine if there are enough different outlines to test the projected number and mim of apphcents and ensure that no more than 30% of the items are duplorated on successive 4 days.

4. a. Assess whether plant specific priorities (i. eluding PRA and IPE insights) are covered in the approg riate enom section. e4 GEN

b. Assess whether the 10 CFR 55.41M3 and 55.45 EW is appropriate. M

c. Ensure that KlA ' ; "- n retings (except for plant-specific prierthes) are atleast 2.5. M

d. Check for duplication and overtop among exam sections. M -

e. Check the entire enam for batence of coverage. M

f. Assess whether the enom fles the ; -@te job level (RO or SRD). M Printed Name iS' nature Date

a. Author \ \ b .

b. raesty Revise::rr) J.t Mews b8A B/trJ97 -- s

c. Chief Eammuner U

d. OfRC Supeevisor

() Not apphcable for NRC developed eneminetsons

t ES-401 BWR SRO Examination Outline Form ES-401-2 l

Facility: J.A. FitzPatrick NPP Date of Exam: 11/03/97 Exam Level: SRO Tier Group K/A Category Points Point Total

, K1 K2 K3 K4 .K5 K6 A1 A2 A3 A4 G l

! 1. 1 2 7 7 6 3 1 26 9' 2 3 4 4 / 3 2

- 1 17 AbnormalPlant TierTotals 5 11 11 9 5 2 43 Evolutions l

2. 1 1 2 3 3 2 2 3 1 3 1 2 23 Plant 2 2 2 2 1 2 1 2 1 13 Systems 3 1 1 1 1 4 TierTotals 4 2 5 6 3 4 3 3 5 3 2 40

3. Generic Knowledge and Abilities Cat 1 Cal 2 Cat 3 Cat 4 I

5 5 3 4 17 Note: Attempt to dstribute topics among all KIA categories; select at least one topic from every KlAcategory within each tier. l Actual point totals must match those specified in the table.

Select topics from many systems; avoid selecting more than two or three KIA topics from a given system unless they relate to plant-specrfic pnontes.

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

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

1

-g l

NUREG-1021 2 of 2 Interim Rev. 8, January 1997 l }

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ES-401 Generic Kicf;$ and Ab4bes Outline (Tier 3) Form ES-401-5 Facility: J.A.FitzPatrick NPP Date of Exam- 11/03/97 Exam Level: SRO Category K/A# Topic imp. Points .

Conductof 2.1.04 Krc#;S of shift stalling requrements. 3.4 1 Operations 2.1.10 Krcd; license.$ of conditions and Imtabons in the facility3.9 1 2.1.13 Kric#;M of facilit 2.9 1 vital control areas. y requirements for controlling access to 2.1.25 Ability to obtain andin stabon reference material 3.1 1 I such as graphs, andtables whichcontain l l systemperformance .

t l 2.1.34 Ab4ty to maintain pnmary and secondary plant choristry 2.9 1 .

within allowablelimits l Total 5 Equipment 2.2.06 Knowledge of the process for making changes in 3.3 1 pr oedures as described in the salety analysis report.

CoWol 2.2.11 Knowledge for the process for controlling temporary 3.4 1 changes. 1 l

i 2.2.17 Knowledge of the process for managing maintenance 3.5 1 activities during power operatiois.

l 2.2.18 Krcd; 3.6 1 activitie$ of the s during process shutdown for managing maintenance operations l

l 2.2.31 Knowledge of SRO fuel handling requirements. 3.8 1 Total - 5 Radiation 2.3.02 Kicf;@ of the facility ALARA program. 2.9 1 l

l Control 2.3.04 Krc#; of radiation exposure limits and contamination 3.1 1 l control E'uding paiirissible levels in excess of those authorimd.

2.3.09 Knowedge of the process for performing a containment 3.4 1 purg3.

Total 3 l Emergency 2.4.01 Kicf;M of EOP entry condibons and 'unmediale action 4.6 1

@ s.

l Procedures 2.4.14 Knowledge of general guidelines for EOP llowchart use. 3.9 1 I and Plan 2.4.20 Knowledge of operabonal nip;ceikiris of E0P warnings, 4.0 1 m caubons and notes.

2.4.41 K of he emergency action level thresholds and 4.1 1 class'. ns.

Total 4 Tier 3 Target PointTotal(SRO) 17 l

I ES-401 BWR RO Examination Outline Form : ..'-401-2 1

! Facility: J.A. Fit 1 Patrick NPP l Date of Exam: 11/03/97 Exam Level: RO l

! Tier Group KlA Category Points Point

! Total !

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

1. 1 2 3 2 3 1 2 13 Emergency &

2 3 5 5 5 1 19 AbnormalPlant 3 2 1 1 4 Evolutions TierTotals 5 8 9 9 3 2 36

2. 1 4 1 1 4 2 2 4 2 4 2 2 28 Plant l 2 2 1 3 5 1 2 1 1 3 19-Systems 3 1 1 2 4 TierTotals 7 2 5 9 3 4 4 5 5 5 2 51

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 I l

4 3 2 4 13 Note: -

Attempt to distribute topics among all KlA categones; select at least one topic from every KlA 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 KlA topics from a given system unless they relate to plant-specific pnonties. _

Systemslevolutions within each group are identified on the associated outline.

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

i l

NUREG-1021 1 of 2 Interim Rev.8, January 1997

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ES-401 Generic Knowledge and Abilities Outline (Ter 3) Form ES-401-5 Facility: J.A. FitzPatrick NPP Date of Exam: 11/03/97 Exam Level: RO l Category KlA# Topic imp. Points Conductof 2.1.01 Knowledge of conduct of operations requirements. 3.7 1 Operations 2.1.20 Abilityto execute procedure steps. 4.3 1 2.1.28 Knowledge of purpose and function of major system 3.2 1 components andcontrols.

2.1.32 Ability to explain and apply all system limits and 3.4 1 precautions.

Total 4 Equipment 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 Control 2.2.22 Knowledge of limiting conditions for operations and safety 3.4 1 limits.

2.2.32 Knowledge of RO duties in the control room durin 3.5 1 handling,such as alarms from fuel handling area, g fuel wmmurucabon with fuel storage faciiity, systems operated from the control room in support of fueling operations and suppor1inginstrumentation.

Total 3 Radiation 2.3.01 Knowledge of 10 CFR 20 and related facility radiation 1 Control ""#I'*9" ***"

2.3.10 Ability to perform procedures to redu excessivelevels of 1 radiation and guard against personnel exposure.

l Total 2 Emergency 2.4.11 Knowledge of abnornal condition procedures. 1 Procedures 2.4.13 Knowledge of crew roles and responsibilities during EOP 1 l and Plan flowchart use.

~ l 2.4.14 Knowledge of general guidelines for EOP flowchart use. 1 2.4.20 Knowledge of operationalimplications of EOP warnings, 1 l cautions and notes.

Total ~-

4 Tier 3 Target Pc;ntTotal(RO) 13

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ES-301 Administrativs Topics Outline Form ES-301-1 Facility: J.A. FitzPatrick NPP Date of Examination: 11/03/97 Examination Level: BQ Operating Test Number.1 Administrative Describe method of evaluation:

. Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Temporary Modification Question 1 Topic - Actions required when it becomes clear of Procedures that a certain procedure cannot or should not be performed as written.

l Question 2 Topic - Requirements for and approvals necessary to institute temporary procedure modification Plant parameter Question 1 Topic - Use of plant computer to verify short verification - heat term and longer term thermal power trends balance Question 2 Topic - Relationship of nuclear instrumentation to plant thermal power (Gain Adjustment Factors).

A.2 Familiarity with and use Question 1 Topic - Use P&lDs to describe the flowpath of piping and instrement taken by main steam if the Intercept Valves close with the drawings plant at full power Question 2 Topic - Identify the fail position of selected air and solenoid operated valvas from the P&lDs A.3 Radiation Exposure Question 1 Topic - Describe the limits on whole body Limits extemal and intemal dose at the plant Question 2 Topic - Describe approvals necessary to exceed these limits.

A.4 Emergency Facilities Question 1 T6pic - Response of licensed personnel who are on site but not on watch during the declaration of I various EPE levels.

1 Question 2 Topic - Role of RO assigned to be Emergency .

Communicator. i 4

m .-

ES-301 Adminttrative Topics Outline Form ES-301-1 Facility: J.A. FitzPatrick NPP Date of Examination: 11/03/97 Examination Level: BR.Q Operating Test Number: 1 Administrative Describe method of evaluation:

- Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Reactor Plant Startup Question 1 Topic - Approvals required before a plant I Requirements startup can begin.

]

Question 2 Topic - Verification of Tech Spec status f required before mode change.

Plant parameter Question 1 Topic - Use of plant computer to verify short ,

verification - heat term and longer term thermal power trends balance i Question 2 Topic - Relationship of nuclear instrumentation l to plant thermal power (Gain Adjustment Factors).

A.2 Tagging and clearances Question 1 - Actions required if a component if found out of its tagged position. 1 Question 2 - Procedure to allow testing of tagged components.

A.3 Control of Radiation Question 1 - Determine if present flow rate is sufficient to Releases make a liquid waste release.

Question 2 - Describe the conditions that would cause you, as Shift Supervisor, to disapprove a Release Permit.

A.4 Emergency Facilities Question 1 Topic - Classify EAL following simulator '

scenario Question 2 Topic - Describe method of decreasing EAL and securing from E Plan. -

he mesume

ES-301 Adminiatrctiva Topics Outlina Form ES-301-1 Facility: J.A. FitzPatrick NPP Date of Examination: 11/03/97 l Examination Level: BQ Operating Test Number 2 Administrative Describe method of evaluation:

- Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Shift Tumover Question 1 Topic - Obtain and explain RO's tumover checksheet.

Question 2 Topic - Required review of logs following a prolonged absence from shift.

Key Control Question 1 Topic - Obtain a vital area key including logging requirements.

Question 2 Topic - Actions required if a key is lost.

A.2 Familiarity with and use Question 1 Topic - Use P&lDs to describe operation of of piping and instrument CRDH during a reactor scram.

drawings Question 2 Topic - Use electrical diagrams to explain the normal, backup, and emergency sources of 4160 VAC power to safeguards loads.

A.3 Radiation Instruments Question 1 Topic - Use of RM-14 to identify contamination.

Question 2 Topic - Actions required if exit monitor alarms when leaving the RCA A.4 Emergency Facilities Question 1 Topic - Identify the EALs at which the various on-site support facilities are manned.

Question 2 Topic - Responsibility of personnel during a site evacuation.

I e = me.

ES-301 Adminttritiva Topics Outlina Form ES-301-1 Facility: J.A. FitzPatrick NPP Date of Examination: 11/03/g7 Examination Level: $RQ. Operating Test Number: 2 Administrative Describe method of evaluation:

. Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Fuel Handling Question 1 Topic - Control Room SRO's responsibilities during conditions requiring ovacuation of fuel handling areas.

Question 2 Topic - Instrumentation and communication

. requirements during fuel handling.

Piant parameter Question 1 Topic - Actions required if thermal power verification - heat exceeds license limit.

balance Question 2 Topic - Relationship of nuclear instrumentation to plant thermal power (Gain Adjustment Factors).

A.2 Temporary Modification Question 1 Topic - Approvals required to install a of Systems temporary modification.

Question 2 Topic - Logging requirements for temporary modifications.

A.3 Procedures to guard Question 1 Topic - Procedure and approvals required for against personnel entry into Locked High Radiation Areas exposure.

Question 2 Topic - Approvals required to exceed plant admin limits of annual exposure in non-emergency conditions.

A.4 Protective Action Question 1 Topic - Classify EAL following simulator Recommendations scenario.

Question 2 Topic - Describe the Emergency Director's responsibilities conceming Protective Action Recommendations.

%9Me

r l

Appendix D Scenario Outline Form ES-D-1 l

F l

Facility: J.A. FitzPatrick NPP Scenario No.: 1 Op-Test No.: 1 ,

Examiners:

l Objebives: Evaluate the operator's ability to address many of the issues involves in a Maior PRA concern - Prolonoed Station Blackout.

Initial Conditions: 75% Power. 'A' & 'C' EDGs out for ma;ntenance.

Tumover Maintain full power: SW oumo shift and 'B' diesel surveillance due immediately after tumovE Event Malf. Event Typ* Event b'o. No. Description g

1 N x x Shift running SW pump.

2 C x x Start 'B' EDG for quick start test. - Fails to start.

3 Management directs orderly shutdown due to common mode DG concems.

4 R x x Crew commences orderly shutdown.

5 i x x Feed flow master fails as is. RV level will increase if not rectified. Operators can take manual control to restore proper level.

6 M x 'x x Thermal Hydraulic instability starts due to feed flow transient. Manual Reactor Scram required.

7 C x x Failure of fast transfer to offsite power. Residual (manual) Transfer required to repower non-safeguards loads.

8 C x x x Ground fault on bus 10600. Loss of all safeguards AC.

Enter EOPs. __

Entries are listed in the following order, event type, participation of SRO, participation of - . ._. s l NCO, and participation of BOP. Individuals are listed as either 11-14 (instant SRO l candidates 1-4) or R1-R4 (RO candidates 1-4).

I

i l

l Appendix D Scenario Ou'iria Form ES-D-1 i

l Facility: J.A. FitzPatrick NPP . Scenario No.: 2 Op-Test No.: 1 Examiners-l Objectives: Evaluate the operator's ability to address many of the issues involves in a Maior PRA concem - ATWS Initial Conditions: 60% Power - ascent to full power in DroQress.

Tumover: Continue increasino oower to full oower.

Event Malf. Event Type

Event Description No. No.

T 11 12 R1 1 N x x Shift operating RWCU pumps.

2 R x x Continue powerincrease.

3 1 x x RV Level transmitter fails high.

4 1 x x x A second RV Level transmitter fails high - both FW pumps trip - turbine trip. Reactor should scram.

5 M x x x ATWS - reactor fails to scram - no rod insertion will be possible for the duration of the scenario.

6 C x x Bypass valves fail to open in auto - can be opened manually. This will accelerate the need to inject SLC.

7 C x x One train of SLC fails to inject which should exceed BilT curve requiring EOP Power Level Control.

Entries are listed in the following order: event type, participation of SRO, participation of I NCO, and particoatum of BOP. Individuals are listed hs either 11-14 (instant SRO candidates 1-4) or R1-R4 (RO candidates 1-4).

1

Appendix D Scenario Outline Fcrm ES-D-1 Facility: J.A. FitzPatrick NPP Scenario No.: .3 Op-Test No.: 1 Examiners:

4 Objectives: Evaluate the aoolicant's ability to chance power. respond to recire c.ontrollet malfunction. respond to steam flow transmitter failure and respond to a LOCA in the DW with the failure of a vacuum breaker.

Initial Conditions: 100% Power.

Turnover. Decrease power by 80 MWe.

Event Malf. Event Type

Event Description No. No.

T 13 R3 14 1 N x x Transfer RB HVAC fans.

2 1 x x Flow input to RBM fails low. Generates Rod Block.

3 R x x Decrease power using Recire flow.

4 1 x x During power decrease, a recirc flow controller fails upscale.

5 C x x SRV fails open and torus sparger fails bypassing )

suppression function of torus.

6 M x x x Manual Reactor Scram - Torus spray require'd.

7 C x x x Torus to DW vacuum breaker fails open. DW spray I required.

Entries are listed in the following order: event type, participation of SRO, participation of NCO, and participation of BOP. Individuals are listed as either 11-14 (instant SRO candidates 1-4) or R1-R4 (RO candidates 1-4).

.-._ l

Appendix D Soenctio Outline Form ES-D-1 Facility: J.A. FitzPatrick NPP Scenario No.: 4 Op-Test No.: 1 Examiners:

Objectives: Evaluate aoolicant's ability to chance power. respond to instrument malfunctionc. and respond to a RB steam tunnel leak.

Initial Conditions: 80% Power.

Tumover: Decrease by 80 MWe per Load Dispatcher.

Event Malf. Event Type

Event Description No. No.

13 14 R3 1 1 x x APRM 'A' fails upscale. Respond, bypass and reset half scram.

2 R x x Decrease power by 80 MWe per load dispatch.

3 N x x Transfer EHC pumps.

4 1 x x Inadvertent HPCI initiation due to logic failure.

5 C x x One Turbine Control Valve fails closed.

6 M x x x Unisolable LOCA in HPCI steam line.

1 One MSIV fails to close. High temp in two or more areas 7 C x x x requires Emergency Depressurization.

Entries are listed in the following order: event type, participation of SRO, participation of ~

NCO, and participation of BOP. Individuals are listed as either 11-14 (instant SRO candidates 1-4) or R1-R4 (RO candidates 1-4).

m .

I

l 1

l I

Appendix D Scenario Outline Form ES-D-1

\

Facility: J.A. FitzPatrick NPP Scenario No.: 5 Op-Test No.: 2 Examiners:

Objectives: Evaluate the aoolicant's ability to chance power. respond to instrument failure and recire Dumo seal failure. Also to respond to a Rx water level transmitter failure and to a LOCA in the DW with no DW coolino.

Initial Conditions: 80% Power, Turnover: Increase to Full Power.

a,: ..

Event Malf. Event Type

Event Description No. No.

T 12 R2 11 1 R x x Start powerincrease.

2 1 x x APRM 'C' fails upscale. Respond, bypass and reset half scram.

3 C x x Recire pump 'B' upper seal failure. j 4 1 x x RV .evel instrument fails downscale.

5 N x x Shift operating RBCLC pumps.

6 C x x Loss of RBCLC to DW.

7 M x x x Failure of Recirc pump 'B' lower seal. LOCA to DW.

8 No DW cooling.

Entries are listed in the following order: event type, participation of SRO, participation of NCO, and participation of BOP. Individuals are listed as either 11-14 (instant SRO candidates 1-4) or R1-R4 (RO candidates 1-4).

i

Appendix D- Scenario Outline Form ES-D-1 Facility: J.A. FitzPatrick NPP Scenario No.: 6 Op-Test No.: 2 Examiners:

Objectives: Evaluate the aoolicant's ability to chanoe power. transfer station power from turbine-oenerator to offsite source. Also to respond to a loss of DC power and an ATWS with the condenser not available.

Initial Conditions: 100% Power. APRM 'A' failed and bvoassed.

Tumover: Reduce power to 75%.

Event Malf. Event Type

Event Description No. No.

T 12 11 R2 1 N x x Realign site loads from Aux. (turbine generator) transformer to Reserve (Offsite) transformer for testing of Aux. transformer. 1 2 R x x When electrical lineup change is complete, commence power reduction to 75%.

3 1 x x APRM 'C' fs:Is upscale. Cannot be bypassed (APRM

'A' already bypassed). Place channel in trip.

I 4 C x x x Condenser air in leakage results in slowly degrading vacuum. Reduce power to maintain vacuum.

5 C x x x Prior to reactor scram, complete failure of condenser vacuum.

6 M x x x ATWS with condenser not available.

Entnes are listed in the folkumg order: event type, participation of SRO, participation of NCO, and participation of BOP. Individuals are listed as either 11-14 (instant SRO candidates 1-4) or R1-R4 (RO candidates 1-4).

l l

1 l

i Appendix D Scenario Outline Form ES-D-1 Facility: J.A. FitzPatrick NPP Scenario No.: Z Op-Test No.: 2 Examiners:

Objectives: Evaluate the aoolicant's ability to chanoe power. start a FW oumo and respond to a FW oumo trio. Also to respond to loss of hotwell level control and trio of all condensate pumps on low suction pressure. This is followed by a non-isolable leak in the RB.

Initial Conditions: 50% Power.

Tumover: Increase to full power.

Event Malf. Event Type

Event Description No. No.

T 14 R4 13 1 R x x Commence power increase.

2 N x x Start a second FW pump.

3 C x x x One FW pump trips. Hold power increase.

4 1 x x When FW Master Level Controller is retumed to auto, level control fails low req Jiring manual control.

5 1 x x Hotwell level fails high. Actual hotwell level decreases until condensate pumps lose suction.

6 M x x x Condensate and FW pumps trip due to low hotwell level.

Reactor Scram.

7 C x x x SDV break upon reactor scram. Leak into reactor building.

8 i x x x RPS fails to reset - SDV cannot be isolated. Results in high radiation in RB.

Entries are listed in the followng order event type, participation of SRO, participation of

, NCO, and participation of BOP. Individuals are listed as either 11-14 (instant SRO candidates 1-4) or R1-R4 (RO candidates 1-4). -w

l Appendix D Scenario Outline Form ES-D-1 l

l Facility: JA FitzPatrick NPP Scenario No.: 3 Op-Test No.: 2 Examiners:

Objedtives: Evaluate the aoolicant's ability to conduct a reactor startuo. shift TBCLC oumos !

and rescond to failure of the RWM The respond to the violation of a MCPR Safety Limit.

Initial Conditions: Plant startuo in oroaress. Power level 15%.

Turnover: Continue startuo to full power.

Event Malf. Event Type

Event Description No. No.

T 14 13 R4 1 R x x Withdraw control rods to increase power.

2 N x x Shift operating TBCLC pumps.

3 i x x Failure of RWM. This vrill stop rod motion until bypassed.

4 C x x RWCU temperature fails high but RWCU fails to isolate.

I Crew should note failure of expected auto action.

5 M x x x EHC pressure regulator failure caut.es Turt>ine Bypass valves and TCVs to fail full open. Uncontrolled cooldown, i Initial decrease in power level will be followed by an i increase and possible inadvertent criticality.

6 C- x x MSIVs fail to close - cooldown continues - this results in violation of MCPR safety limit - Manual Scram required. ,

7 C x x Manual closure of MSIVs. One steam line remains open.

Cooldown continues.

8 Enter Minimize Steam Loads Procedure. !

1 l

Entries are listed in the following order: event type, participation of SRO, participation of NCO, and participation of BOP. Individuals are listed as either 11-14 (instant SRO candidates 1-4) or R1-R4 (RO candidates 1-4). ,,_.

I i

I ES-301 Transient cnd Event Checklist Form ES-301-5 OPERATING TEST NO.: 1 & 2 Applicant Evolution Number Scenario Number Type Type Regr'd 1 2 5 6 Reactivity 1 4 Normal 1 1 0#1 Instrument 2 3,4 Component 2 8 6,7

, Major 1 6 5 I

l i

Reactivity 1 2 Normal 5 As RO Instrument 1 3 Component 1 3,6 4,5 l

Major 1 7 6 SRO-l # 1 _ )

Reactivity 4 2 Normal 1 1 1 As SRO 3,4 Instrument 1 5 Component 1 2,7,8 6,7 Major 1 6 5 Reactivity Normal 1 SRO-U Instrument 1 Component 1 Major 1 ----

Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations must be significant as defined in Appendix D.

I Author 3.E.tAccess S,[zt97-Chief Examiner

ES-301 Tr:nstnt cnd Event Checklist Form ES-301-5 OPERATING TEST NO.: 1 & 2 Applicant Evolution Number Scenario Number Type Type Regr'd 1 2 5 6 Reactivity 1 1 Normal 1 1 lnstrument 2 2,4 l Component 2 4,5 Major 1 7 6 Reactivity 1 2 Normal 5 As RO Instrument 1 3 Component 1 3,6 4,5 Major 1 7 6 SRO-l # 2 Reactivity 2 Normal 1 1 As S O 4 Instrument 1 5 Component 1 2,7,8 Major 1 6 5 Reactivity 1 2 Normal 1 5 1 SROW 2,4 Instrument 1 3 Component 1 3,6 4,5 Major 1 7 6 - - . .

Instrudens: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations must be significant as defined in Appendix D.

Author: 3,E,meeris g[zz/97 j M '

Chief Examiner:

l j

1 1

ES-301 Tr nstnt cnd Event Checklist Form ES-301-5 OPERATING TEST NO.: 1 & 2 Applicant Evolution Number Scenario Number Type Type Regr'd 3 4 7 8 Reactivity 1 3 Normal 1 3 Instrument 2 2,4 4 Component 2 7 5,7 Major 1 6 6 Reactivity 1 1 Normal 2 As RO Instrument 1 4,5 3 Component 1 3,7 Major 1 6 5 ,

l SRO-l # 3 Reactivity 3 2 Normal 1 1 3 As SRO Instrument 1 2,4 1,4 Component 1 5,7 5,7 Major 1 6 6 Reactivity Normal 1 SR% instrument 1 Component 1 Major 1 ---

'nstructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) React?/ity manipulations must be significant as defined in Appendix D. -

Author: 3.E.moceu d s/trl97 Chief Examiner:

u

ES-301 Tr nsient pJ Event Checklist Form ES-301-5 OPERATING TEST NO.: 1 & 2 Applicant Evolution Number Scenario Number Type Type Regr'd 3 4 7 8 Reactivity 1 1 Normal 1 2 Instrument 2 8 4 Component 2 3,7 6,7 Major 1 6 5 Reactivity 1 2 Normal 1 As RO Instrument 1 1 Component 1 5,7 7 Major 1 6 6 SRO-l # 4 Reactivity 1 1 Normal 1 2 2 As SRO Instrument 1 4,5 3,4 Component 1 3,7 6,7 Major 1 6 5 Reactivity Normal 1 Instrument 1 Component 1 Major 1 _.

Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each l evolution type.

! (2) Reactivity manipulations must be significant as defined in Appendix D.

Author: 3.t. g.geis g/nlg7 Chief Examiner.

ES-301 Competencies Checklist Form ES-301-6 Instant SRO #1' Instant SRO #2 instant SRO #3 SRO-l SRO-1 SRO-l Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Understand and Interpret 6 3 8 4 3 3 Annunciators and Alarms Diagnose Events 8 7 6 3 5 5 7 4 3 3 and Conditions Understand Plant 4 3 2 3 5 4 4 5 and System Response Comply With and 8 7 5 2 1 2 7 7 2 1 Use Procedures (1)

Operate Control 5 2 1 2 2 i Boards (2)

Communicate and 8 7 7 6 5 5 7 6 6 6 4 5 !

Interact With the Crew Demonstrate Supervisory 8 7 7 6 1 7 Ability (3)

Comply With and 2 2 3 1 2 Use Tech. Specs. (3)

Notes:

l l (1) Includes Technical Specification compliance for an RO.

l (2) Optional for an SRO-U.

l (3) Only applicable to SROs. l Instruchons:

Circle the applicant's license type and enter the event numbers that test the competency for each scenario in the set. l Author: LE Mett's b BI*di' u

Chief Examiner

ES-301 Camoetencies Checklist Form ES-301-6 MO #4 RO #1 RO #2

RO RO Competencies SCEN, O SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Understand and Interpret 4 4 8 8 4 2 4 Annunciators and Alarms Diagnose Events 5 4 7 6 6 6 2 4 and Conditions Understand Plant 4 6 5 6 7 4 4 and System Response Comply With and 7 3 6 5 6 1 1 1 Use Procedures (1) .

Operate Control 4 3 4 1 1 1 Boards (2)

Communicate and 6 6 6 5 6 4 7 6 Interact With the Crew Demonstrate Supervisory 6 5 Ability (P Comply With and 3

Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

1 Circle the applicant's license type and enter the event numbers that test the competency I

for each scenario in the set.

Author: $ .E . mee eis O tlttl91 Q

Chief Examiner:

ES-301 Competencies Checkli t Form ES-301-6 RO #3 RO #4 RO RO Competencies SCENAftlO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Understand and Interpret 6 5 6 4 Annunciators and Alarms Diagnose Events 6 5 6 4 and Conditions Understand Plant 2 5 6 7 and System Response Comply With and 2 6 1 2 Use Procedures (1)

Operate Control 2 6 1 2 Boards (2)

Communicate and I 6 6 6 5 Interact With the Crew Demonstrate Supervisory Ability (3)

Comply With and Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

~

(3) Only applicable to SROs.

Instructions:

'~'

Circle the applicant's license type and enter the event numbers that test the competency for each scenario in the set.

Author: 3.E. r4ece 6 s/ttl17 Chief Examiner:

.

JAFP-97-0309, Transmits Proposed Integrated Exam Outline for 971103 Licensing Exam at Plant

Contents

Text

SUBJECT:

Dear Mr. Meyer:

Enclosure:

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JAFP-97-0309, Transmits Proposed Integrated Exam Outline for 971103 Licensing Exam at Plant

Text

SUBJECT:

Dear Mr. Meyer:

Enclosure:

Navigation menu

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