IR 05000281/2004301

Feb-March 2004 Exam 50-280, 50-281/2004-301 Draft Written Exam Outlines

ML041070257
Person / Time
Site:	Surry
Issue date:	02/19/2004
From:	NRC/RGN-II
To:
References
50-280/04-301, 50-281/04-301
Download: ML041070257 (10)

Text

...

.....

....

-~-.

ES-401 PWR Examination Outline Form ES-401-2 Facility: Surry Date of Exam: 2004 Note:...* Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the Tier Totals in each WA category shall not be less than two). Refer Bo Section D.l.e for additional guidance regarding SRO samplin 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 el from that specified in the table based on NRC revisions. The final WO exam must total 75 points and the SWO-only exam must total 25 point 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 prioritie Systems/evolutions within each group are identified on the associated outlin The shaded areas are not applicable to the category/tie 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 CFW 55.43 or an SRO-level learning objectiv On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (if?)

for the applicable license bevel, 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 80 and SRB-only exam For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-Refer to ES-481, Attachment 2, for guidance regarding the elimination of

-

-

inappropriate WA statement of 34 NUREG-1021, Draft Revision 9

ES-401 PWR Examination Outline Fom ES-401-2 Emergency 11 Plant Evolutions - l7er 11Group 1 (ROJ I SWOx)

I I

/APE # I Name I Safety Function 000007 (BWIE02bE10: ClF.O?] Yeactor T 2. Stabilization - Reccvery 1 oOo0013 Pressurizer Vapor Space Accident I

000009 Small Break LOCA I 3 00001 1 Large Break LOCA I 3 00001Y17 RCP Malfunctions I

000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I4 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control System Malfunction I 3 000029 ATWS I 1

~

000038 Steam Gen. Tube Rupture I 3 000340 (SWIESS; 6EIE05; WE12)

Steam Line Rupture - Excessive Heat Transfer 14 000054 (CEIEOB) Loss of Main Feedwater I 4 000055 Station Blackout I6 000056 Loss of Off-site Power I

030055 Loss of Vital AC Inst. Bus I 6 000058 boss of DC Power I 6 000062 Loss of Nuclear Suc Water 1 4 000065 boss of Instrument Air I 8 rd Abnori r

A G

WA Topic(s)

IR

/ EK2.02: KnoHiladgs dtho inlerrelalionships bemen a reactor 1 2.6 12.E I 1 trip and the tollmuln@ Breakers. relays. aid dwmnecf I L

I

I I

23 Of 34 NUREG-1821 I Draft Revision 9

J W E 0 4 EK3.2: Knowled W E 0 4 LOCA Outside Containment I 3 BWIEM, WE05 Inadequate Heat Trans-fer ~ Loss of Secondary Heat Smk / 4

--

24 of 34 NUREG-1 021, Draft Revision 9

ES-401 PWR Examination Outline Farm ES-401-2 Emergency and Abnomtal Plant Evolutions -Tier 1IGroup 2 (RO/ I SWOx)

I

1

1

1

WA Topic@)

iFl

/APE # I Name I Safety Function 000001 Continuous Rod Withdrawal I

000003 Dropped Control Rod / I 000005 InoperableIStuck Control Rod / 1 00024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 boss of Source Range Ni / 7 000033 Loss of Intermediate Range NI I 7 Nof Selecl@ Nc!4 SeIec!e Nu: Sa!ee!e N@f Salecfe.1 I.2 1 (SW/AOS) Fuel Handling Accident I 8 000037 Steam Generator Tube Leak I

000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. I

O(x1060 Accidental Gaseous Radwaate Rel. I 9 ooO061 ARM System Alarms I 7 Not %!ecta.5 i Mot seieeted 3.5i.7:.4 f Plant Fire On-site I 8 000068 (BW/A06) Control Room hac. / 8 003069 (W/E14) LOSS of CTMT Integrity / 5 000074 (WIE068E07) inad. Core CWling I 4 2.6 1 High Reactor Coolant Activity I 9 4.3 1 WE01 & E02 Wediagnosis Ei SI Termination 13 WlE13 Steam Generator Over-pressure / 4 3.Cf.9 t.7 1 _______~ ________

W/E15 Containment Floodng / 5 MI selscfed WE16 High Containment Radiation I9 BWIA01 Plant Wunback / 1 BWIA028A03 Loss of NNI-XIY i 7 BW/AO4 Turbine Trip I 4 BWIA05 Emeraencv Diesel Actuation t 6 NA NA NA NA 25of 34 NUREG-1 021 Draft Revision 9

.

.

-.4 W E l a E 1 4 EOP Rules and Enclosures CWA11; W/E08 RCS Overmling - PTS / 4 C30up Point Total:

26of 34 NUREG-1 021, Draft Revision 9

iination Outline UGroup 1 (ROJ / SROx)

A A

O

WA Topic(s)

4

I I

r' M:l7 A5ility @ (a) pe;(iel the impam of the 1ol:owlng malfuncl!cm or opsmtion~ on the CVCS and b) b a d o?) those predlc(ions use precedures lo mrrec+. conlrol, o! rimgate he wnsquences operations: Low 01 PZR those pressur rnal!unc+ions or owIsdge 01 the phys!cal and !

or eause.e'fe?t ralationsMps RF'S and the fWUQWlna SyS!WnS:

NA. Surry has no Ice C0nIhfis I I

reoicl sndior moiilor 24 of 34 NUREG-1821, Draft Revision 9

3.9199

I 061 AuxiliarylEmergency Feedwater 3.41 I34

~

2.8i I

-

062 AC Electrical Distribution

'*__-

I 063 D 6 Electrical Distribution

/ A4.01'AbiliIyIo manuallya raleand!or moni:or in the mntm room: $pr braekers end Clnlml pawe, fuse '

K2.01.,Unaxleddgs of h s powr supplias !o me follcwmg: Air comp:essor.7 i 3.1 -

3.9 1 ~

2.5 i Diesel Generator 073 Prqcess Radiation Monilonng I

I 076 Service Water 3.1 1.2 1 Instrument Air 3.51.0 1 Containment

.r A4.04: Abilily to manually 03EraIe and I or monitor in the mnlml room: Phase A and $-aae l

resBI Group Point Total:

28 of 34 NUWEG-1021, Draft Revision 9

ES-401

aminatio er YGroi Xtline Form ES-401-,

2 (Rod / SRQx)

I I

I System # t Name WA Topic@)

NO! Sslrnta I I

I 001 Control Rod Drive 002 Reactor Coolant 01 1 Pressurizer bevel Control No: SSlrnIe I I

I 014 Rod Position Indication I t c 015 Nuclear Instrumentation I l l 016 Non-nuclear Instrumentation 019 In-core Temperature Monitw I I I c

/ A4.Q3: Abilhy la manually a rfile and I w 3.3152

mnitm in Ihe mntrcl room: C I A fan I I

I J / 2.2.12: Knowle&s a1 suweiilance procedure I 028 Hydro en Recombiner and Purge ConSroi 029 Containment Purge I l l 033 Spent Fuel Pool Cooling 035 Steam Generator 041 Steam DumpTTurbine Bypass Control I

l l

045 Main Turbine Generator 055 Condenser Air Removal i

071 Waste Gas Disposal I c 072 Area Radiation Monitoring 075 Circulating Water I l l 079 Station Air

/ I 086 Fire Protecfion I

l k

I:

WA Category Point Totals:

81 8 29of 34 NUREG-I021 I Draft Revision 9

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

Form ES-401-2 Facility: Surry Bate of Exam: 2804 B

I I

I Category lvAW I I

2.1.11 Conduct of Operations 2.1.25 2..1 3 4 Topic

,

Knowledge fff less than one hour technical specification action statements for system Ability to obtain and interpret station reference materials such as graphs, rnunographs, and tables which contain petfotrnance dat Knowledge of shift staffing requirement AbiWy to maintain primary and secondary plant chmfstry wlrnin allowable lirnlt.

Equipment Control 2.2.31 2. eolures and IMtations involved BR Radiation Control Emergency Procedures Plan 2.429 2.4.38 Tier 3 Point Total 27 sf 34 NUREG-1021. Draft Revision 9