ML20100Q277

Forwards Proposed Integrated Initial Licensed Operator Exam Outline for Voluntary Pilot Exam Program

ML20100Q277
Person / Time
Site:	Fort Calhoun
Issue date:	10/10/1995
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20100Q267	List: ML20100Q277
References
NUDOCS 9603110558
Download: ML20100Q277 (27)

Text

ATTACHMENT 4 ENCLOSURE 1 Omaha Public Power District 444 Soutn 16th Street Maa Omana. Neorasxa 68102-Z247

'02/636-2000 Octocer 10.

995 LIC-95-0192 Mr. Joseen '. Taola Acting Chier'. Operati:rs 3rancr J. 5. Nuc i ea r Regui a::-. :.~.i s s :. Teol cn '.'

611 Ryan >1a:a Cr1ve.. ::a -G Ari1ng:::n. 'X

'601;-c:54

'-ete-9"ces:

..; - ~

._5

^ -

.o r n i

:: D

_. ritter cn;.a:02

uaus:.

H5 1

Cear "r.

~acia:

d'JSJ ECT -

?-coosea teara:e: 'n': tai _:censea C::erator Examination Out!1ne "or

• he.c mn arv

Examinatlun ' caram

~

Enclosec ::iease #1na tre 'mana aci:c 2cwer District s (OPPD) ;:recosea integratea initlai ic sea ocer3:::r eva nration outline for your review as saecifiea in Reference 2.

'he out!1re aas :eveio::ea in acc::raance with NUREG 1021. Revision 7,

Suopienent ;, 'Oceratcr _::ensino Examiner 5tanaaras" ana NUREG/SR-01:2.

Revision 5.

' Examiner -

"a nc:::c <

or Developing Ocerator

.1 censing Written i

Examinations." Addi t1 cna l l y, :r.e incividuais developing the integratea outline ana Examination for the Fort Calhoun Station have providea a craf t coDy of this i

j attline to Mr. Thomas."eacows of your of fice for his review ana comment.

j Also enclosed is an Examination Security Agreement signed by Messrs. Jerry Koske.

Michael Woram and Cari ;ennerfelat, :he inalviduals wno currently have knowleage of the contents of the examinat1on.

As additional Individuals are recuired to l

participate in the examination ceveiocment and validat1on process, they will be 1

added to the security agreement. ana a copy of the revised agreement form will

}

be suppliea to Mr. Meacows.

i j

9603110558 960226 4

PDR ADOCK 05000295

]

G PDR

U. S. Nuclear RegulatoryL Commission-i LIC-95-0192 Page Two l

If you should have any questions concerning the proposed outline, please contact j

Mr. Greg Guliani at 402-533-6025.

e i

Sincerely,

, - ~s

'l) e

~ ~,

l

+=Y T. L. Patterson Division Manager Nuclear Operations Enclosures TLP/dll l

c:

Winston & Strawn.(w/o Encicsures) l L. J. Callan,- NRC Regicnal Administrator, Region IV (w/o Enclosures)

S. D. Bloom, NRC Project Manager (w/o Enclosures) l W. C. Walker, NRC Senior Resident Inspector (w/o Enclosures)

Document Control Desk (w/o Enclosures) l

'i l

i e

l 1

G..

t Exam Outline Contents

1. FCS 50-285. Exam Schedule (1 page) t

2. Count Matrix for RO Written Exam ii page)

3. Count Matrix for SRO Written Exam (l page) 1 B

4.

Overall exam matrix and K/A listings for written RO exam. (7 pagess 5 Overall exam matrix and K/A listings for written SRO exam (7 pagess o RO Administrative Topics Outline I page) 7.

SRO Administrative Topics Outline I page) 8 RO Individual Walk-through Test Outline a i pages SRO(l) Individual Walk-through Test Outline I pages o

1

10. SRO(U) Individual Walk-through Test Outline t I page)

I 1. Simulator Scenario Events (2 pages >

12. Copy of signed Security Agreement (2 pages)

I i

1 Facility: Fort Calhoun Exam Date: 12/04/95 i

1 Knowledge and Ability Record Form i

COUNT MATRIX l

1 Summanzing Counts by FJA Group for PWR - Reactor Operator d

Toul Plant Wide Generics 13 K!

K2 K3 K4 K5

'K6 Al A2 A3 44 5G Plant $vstems !

1 1

1 1

1 1

2 1

4

- 2.,

Plant Systems l!

i 1

1 5

1 1

0 1

1 0

4 20 '

l Plant $s stems ill O

o 2

1 0

0 I

l o

4 EmergencstAbn i O

4 1

4 4

Emergencv/Abn il 2

1 4

1 1

17 Emergency /Abn 111 0

0 1

0 I

1

+

r i

Totals 11 3

11 10 3

2 x

16 1

4 16

=

i Model Total 100 l

i

)

1 I

i t

k t

i i

.. ~....

t Facday Fort Calhoun Exam Date: 12/04/95 l

4 4

Knowledge and Ability Record Form COUNT MATRLY Summanzing Coums by K/A Group i

for PWR - Senior Reactor Operator.

Tod i

Plant Wide Genenes 1*

i i

Kl K2 K3 K4 K5 K6 At 42 A3 A4 SG Plant 5vstems !

2 1

1 i

i 1

2 1

1 1

19

~

Plant shstems li i

1 1

4 2

1 0

2 1

o 2

1-Plant $sstems ll!

0 0

0 1

0 0

4 l

1 l

0 4

i EmergencviAbn 1 o

--- 5 4

24 Emcreencv/Abn 11 2

1 4

2 4

t 16 Emergencv/Abn 111 0

0 1

- -- - o 1

1

[

t

' Totals

-10 3

14 X

3 2

9 13 1

4 14

- Model Total 100 i

i k

i

?

f i

e F

.. - +

e

1 PWR - RO PLA!W SYSEMS - 51%- Groep 1 Gmp Iz - 23%

KI K2 M

K4 M

M

,M M :M :M SG 001 Couud Rod Driw Swtem 01 07 003 R-ai G-Ptag Symem W

10 004

&=M and Volume C-d System W

07 013 F5--wd Safety Features Actuapon System 12 05 5

015 Nuclear Insm-mauon System W

01 017 In-Core Tenverature Manitor Sysem 02 1

02 022 G-a a Coolmg System of l

l

(

15 (

U25 Ice Cc--' - System.

No lee Concenser j

056 O- *- = S sem No K/A niues >=3 3

059 hiain fMwater System 03 '

i l 11 l

l 061 Attuharv/ Emergency Feedwmer System 06 l

l W

i i si1 068 Uguid Radwaste Sssem i

i Wl 071 Waste Gas Disposal Sssem i

29 l l

072 Area inh man hionstonna System lt2 l

l l

l l5 i

l i

Sys. j Mode l K/A a l ltem j 1mpon. j 001 l 000 l K2.01 One-ime alagram or power supply to MG sets lCluten Power duopliesl l 3 5d o l 001 l 010 l A2.07 Idenury and mangate an erroneous ECP.ECC calculanon.

t3m42 i 003 000 K5.W Knowlease or the ettects or RCP shutcown on seconaarv pararra:ters sucn as steam 1.35 i

pressure. steam tiow ano feed flow l

uB j SG l A10 Ability to explam and apply all system imuts ana precauuons.

3 3d o j un l 000 l Kl.04 Knowieage or the relanonsrup octween tne CVCS and RCPs. mctuamg sean unecuon tiows ! 3 4/3 8 j un l WO A2.07 Abihty to prealet and nuncate the consequences or isolanon or letdowwmaxeup.

l 3 4/17 j

013 l 000 K4.12 Knowledge of ESF design teatures and mterlocks wtuch pronae for saretv tmecuan clocx. j 17,3 9 013 000 A1.05 Abihty to predict and/or nnutor changes in rmm steam neaaer pressure unen operanng 34/36 ESF controls.

013 l SG K5 Know1eage or linunng conainons for operanons ano sarety tinuts.

l3w42 i

015 j lxx)

K6AM Know1 edge or performance ana design aanbutes or bistables and logic citants.

ji1/32 015 l000 Al.01 Abihtv to perform an NS caubranon by heat balance.

j 15/3 3 017 l 020 Kl.02 Knowledge or the relanonstup between the flhi sssern and the RCS.

l 13/3.5 017 020 A4.02 Abthty to morutor tw ture ulues used to determme RCS/RCP operanon cunng 38/41 ra irwi== core cooling ti e.. if applicable. average of five highest valuest 022 000 Kl.01 Know1cdge or the retanonsrups between the CCS and the coolmg unter ssstem.

l 15/17 022 SG A15 Abihty to recognize annomni marcanons for system operanng parameters wtuca are entrv 35/18 lent conditions for emergency and abnormal operating procedures 059 000 K3.03 Knowiedge of the ettect that a loss of the MFW system util have on the sGs.

l 15/3 7 059 000 A2.11 Abthty to predict or nungate the enn=== of a tailure or feedwater control system.

10/3.3 061 000 K4 06 Knowiedge of AFW system design teatures and interlocks wtuch provide AFW startup 40/42 pemussives.

061 000 A3.N Ability to rnorutor operanon or automanc AlW isolanon.

41/42 068 000 A4AM Ability to morutor autormac isolation.

18/3.7 071 000 A4.29 Abihty to rnorutor sanpimg oxvgen. hpirogen. arx1 rutrogen concenuanons m WDGS 10/3.6 decay tank inchdaa knowiedge of limits.

O'/2 000 K4.02 Knowiedge of ARM sysem design teatures and imerlocks wtuch provide for ruel buildmg 3.2/3.4 isolation. [ Fuel thndhng alarms and imerlocksl 072 SG K5 Knowierige of imutmg conannons for operanons and saretv imuts.

10/3.6 l

1 1

l 1

PWR-RO PLANT SY5TEMS-51%- Group 2 Grt,w 2 - 20W 10 Ic.

D KA E

E M

M M

M SG 002 R-Coolant System 15 5

l 006 L, y Cote rW Syman 09 s!!

l 010 Pmmunmer P.a Co v; S>sem 02

JOU l

011 P.mm f.ewi Cum ui System i1 012 Rca.iui Pwusion System m

fa 014 Rod Pomuon Indiamon System mi 016 Non-Nuclear instrumentanon Sssem 01 i

j i

026 Cc-- - 1 Sprav System l

l j 02 l 11 i j

029 Contamment Purve Sysem 03 l

l l

l i

i l

033 Spem Fuel Pool Coolmg Sysem i

j j

i 035 Steam Generator Sssem i

01 039 Niun and Rehear Steam System Ox l

055 Condenser Air Removal System No MA miues >=3 i

1 062 AC Becmcal Dismbunon Sssem 01 I I

l 1

l JPM 0347 j

063 DC Becmcal Dismbunon Ssstem l

l l

l i

l j

jr OM Emervency Diesel Generator Ssstem i

I 02 i i

j i

i i

1-

)

073 I Process Radianon Skxutonna System j

l l 01 l l

l l

i i

i 075 Circutanna Water Svstem i

I i

j i

i j

i i

e i

j 079 Stanon Air dsstem 101 l I

1 I

l JPM 0214 086 Hre Protecuon dvstem I

i i

l 01 i

j i

i i to) l i

Sys. l Mode l K/An l Item l Import. l 002 1000 K$.15 Knowiedge or the reason for numtammg subcooled rnanpn aurmg natural circulanon.

l42/46 002 SG K5 l Know1 edge or linunng concinons for operanons and sarety linuts.

j 3.w41 u)6 ux)

K409 l Know1 edge or ECCS desgn reatures wtuch proude for the sarety insecuon valse mterlocks.l 3 8/41 j 010 000 K3.02 Know1 edge or the effect that a loss or the PZR Pressure Control System will haw on the 4 0/4 i RPS.

011 000 A2.11 l Ability to precict and nuncate the consequences or tailure of PZR leses msuument-low l 3 4/3 6 l 012 000 K6.N l Knowledge or the performance and design armbutes or b> pass-block circuits of the RPS.

l 3.3/3 6 l 014 000 A2.W Abihty to precict and nungste the consequences or a nusaligned rod.

34/3.9 016 (XX)

Kl.01 Knowiedge of the relanonstup between the NNIS and the RCS.

3.4/34 026 ux)

A2.02 Ability to precict and mingate the consequences of tiulure of automanc recirculanon 42/44 transter.

026 SG Ai1 Abtlity to recogruze mdicanons for ssstem operanng parameters wtuch are entrv level 12/4.I conditions for tech specs.

029 000 Kl.03 Knowiedge of the relanonsrups between the CPS and enameered sareguards 16/38 035 010 A3.01 Ability to rnonstor automanc operanon of the S/G water level conuol.

40/3.9 039 000 K4.08 Knowiedge of MRSS desgn teatures wtuch provide interlocks on MSIV and bvptss valves.

3.3/3.4 063 SG K5 Knowiedge oflinuung condmons for operanons and sarctv linuts.

3.0/3 6 062 000 K2.01 Knowiedge or power supphes to rnajor ssstem loads.

j13/34 064 000 K4.02 Knowledge of ED'O system desgn teatures and interlocks wtuch provide tor mps ror 3.9/4.2 ERG while tv-nne (nonmi or emergencv).

I 064 SG K5 Knowiedge of linutmg condmons for operanons and safety imuts.

3.4/3.9 073 000 K4.01 Knowiedge of PRM system desgn teatures and intertocks wtuch provide for release 40/4.3 temunation when radiation evecds setpoint.

079 000 Kl.01 Knowkdge of the relanonstups between SAS and IAS.

l3.0/3.1 086 000 K4.01 Knowkdy of Q teanses whidi provide for @a stypiy of waer for FPS.

3.1/3.7 i WM - MU FLANI~ SYNIRRB - Sl% - broep J Greap J:.- 5%...

K1s mz :n nr.8 K5 f ME At A2.. A3 } M ] SG.

005 Rendual !L hawal System 10 NO321 007 Pie Relief Tank /Qan Tank Susem

' 01 l

008 G- --- = Coohng Water Ssstem l

027 Cus.um.c.ui lodine hi vval Ssstem 01 l

l 028 Mdrwm Rouaismer and Purge Control Ssstem 01 JPM 0719 034 Fuel liwuling Eginkm e System I

i i

l j

j Wl Steam Dump Ssstem j

l 1

l 08 l N5 Mun Turbme Generator 12 l

l 1

i i

j 076 Seruce Water System 1

l I

02 l l

078 Insmsruis Air Ssstem t

i t

i 1

.l 103 i Contamment Ssstem I

i j

i i

i 03 i

i i

I Sys. l Mode K/A# l Item l Import. l u)5 (WX)

K410 Knowledge of RHR desicn ti:stures and intertocks which proude for control of RHR heat I 1:31 l eunancer outlet flow

{

u)7 l (XX) l A2.01 Ability to predict and miocate the consequences of stuckspen PORV or coce sarerv.

I i *4 2 027 l000 l Kl.01 l Knowledge of the relatonsrups between the CIRS ano the CSS.

l14/37 l 028 l 000 K5.01 l Knowiedee of explosive h>urogen concentranon as applied to the HRPS l34/3.9 WI 020 A4 08 l Ability to manually operate and morutor the steam dump salves.

l30/3.1 N5 000 K4.12 Knowledee of the desien features and interlocks wnich proude for automanc turome 33/36 runoack.

l A3 02 l Ability to morutor automauc operanon of the S%S. including emerrency heat loads.

3.7/3.7 076 000 103 l 000 l A2.03 l Ability to predict and mmcate the consequences of Phase A and B [contammemiisolanon. l 3 5/3 8 i

t I

i 1

-l l

l i

PWR - RO EMERGENCY PLANT EVOLUDONS - 36%- Group i Gr,1. - 16*4 -

KI.

KZ.. IG M

M

SG.

000 005 Iw-d '= Stuck Couuvi Rod 01 3

000 015 RG Mia MM=rnan 12 000 024 L gf Bu. us 02 JPM0006 000 026 Ims of Caynnent Cooling Water 02 fu 000 027 f.s-inzer fa-are Cuuuul System Maltuncuan 15 000 040 Steam 12ne Rupture W

10 000 051 loss or Caxienser Vacuum 01 l

000 055 less of CE.vis and Onsite Power 05 000 057 loss of Vital AC Bectncal Insuument Bus jul 19 000 067 Plant Fue on Site 17 000 068 Comrol Room Evacuanon l

12l (xx) 069 loss of 0-anment integnty j

j j

j i1 000 074 Ir=w=n'a Core Coolmg j

j 08 smunator 000 076 Hgh Reactor Coolant Acuvity l

l l

j l 11 i

fotals l Cnoup i=in ii !o i4

!a

.4 i

Svs. l Mode l K/A#

l Item l Impon. l (XX) l 005 l EAl.01 l Ability to operate and morutor the CRDS.

l 3 (v3 4 l 000 005 SGK3 l Knowledge of the linuung concitions for operanons and safety limits l31/36 000 015 SGK12 l Ability to utilize sunptom based procedures 2.9/32 000 024 EKl.02 Knowiedge of the relationship between boron addition and reactor power as applied to 3.6/3.9 emergency boration.

000 026 EK3.02 Knowiedge of the bases for the autonunc accons (alignments) within the CC Ssstem 3ev3.9 resulting from the vnmnon of the ESF.

000 027 EA2.15 Ability to detemune accons to be taken if PZR pressure mstnmem fails hich.

37/40 000 NO EK3.N Knowiedge of the basis for accons wiuu=4 in EOPs for steam line rupture 4.5/4.7 000 No EA1.10 Ability to operate and rnorntor the AFW ssstem dunng a steam line rupture 41/4.1 (XX) 051 EK3.01 Knowiedge of the reasons for the loss of steam dump capability upon loss of condenser 2.8/31 vacuum.

000 055 EA2.05 Ability to determine when txurerv is wu.ddng nuly discharged.

3.4/3.7 000 057 EA2.19 Ability to determme the plant automanc acuans that will occur on the loss of a vital AC 40/43 electrical instrument bus.

000 067 EA2.17 Ability to determine what systems may be affected by the fue.

3.5/4.3 000 068 EAl.12 Ability to operate and monitor the auxiliary shutdown panel controls and indicators.

44/44 000 069 SGAl1 Ability to r== nim *---M indications for system operatmg re-wrs which are 40/42 entry level conditions for emergency and abnormal operanng procedures 000 074 EK3.08 Knowiedge of the reason for secunng RCPs.

4.1/4.2 000 076 SGAl1 Ability to rs= nim airou u ! indications for sprem operanng e-:- - i. rs which are 3.4/36 entrv level conditions for emergency and abnormal v. u 3 procedures

PWR - RO EMERGDiCY PIAlVT EVOLUTIONS - 367. - Group 2 Group 1-17W M.

M. :10 A1 AI :E 000 001

c...._ - Rod Witfulumet 02 000 003 A p r,4 C autml R o d 07 000 007 R

Trip 03 000 008 Pressuruer Vapor Space Accident 02 000 009 Small Break IDCA 04 smaalator 000 01i large Break IDCA i1 000 022 loss of Reactor Coolant Makeup 06 000 025 loss of Rendual ficat Remoni System 01 000 029 Anncipated Trannent Without Scram (AIW5) 01 6mdmar 000 032 loss of Sourtz Range Nucicar insuumentanon 04 000 033 loss of Imenn~6*- Range Nuclear instrumentanon 0) i 000 037 Steam Cenerator Fube f.eak M

000 038 Steam Generator Tube Rupture l

39 uuo 054 loss of Mam Feeawater l

l simulator 000 058 loss of DC Power l

01 l

000 059 Accidental Uqmd Radioacuve Waste Release l

l l

11 000 060 Accidental Gaseous Waste Release l

j 7

000 061 Area Radianon Morutonng S3 stem Alarms l

l l

01 I l'ot:us

! fnoup.t=f 7

• - Ii i.4 t.- i-i l

Sys.

Mode K/A#- l Item -

i import.

nummmma 000 001 EK3.02 Knowiedge of the reasons for Tech-Spec imuts on rod operability as thev apply to the 3.2/4.3 Cononuous Rod Withdrawal emergency task.

000 003 EA1.07 Abtlity to momtor m-core and ex-wre insnumentanon.

38/38 000 007 EKl.03 Knowiedge of the rmrm for closmg the mam turtme govemor valve and the mam 3.7/40 turbine stop valw aller a reactor trip.

000 008 EK3.02 Know1 edge of the reason wny PORV or code sarety valve e.ut temperumre is below RCS 36/4.1 or PZR temperantre 000 009 EK2.04 Knowiedge of sensors and detectors.

2.3/2.6 000 011 EA2.ll Abtlity to determme conditions for throtthng or stopping 1-iPI dunng large breax IDCA.

3.9/43 000 022 EK3.06 Knowiedge of the bass of RCP thermal bamer coolmg.

3.2/3.3 000 025 EKl.01 Knowiedge of the effect ofloss of RHR dunng all rnodes of operanon.

3.9/43 000 029 EKl.01 Knowiedge of reactor nuclecrucs and thermal-hyttraulics behavior as apphed to AIMS.

2.8/3.1 000 032 EA2.0%

Ability to determme morwv sourcc-range / intermediate-range overlap.

3.1/3.5 000 033 EA2.02 Ability to interpret indicanons of unreliable interrrreme-range charmel operanon.

3.3/3.6 000 037 SGA8 Ability to rn-i= indicanons for system vi.aug parameters which are enny level 3.1/3.9 conditions for Tech Specs.

000 038 EAl.39 Ability to operate and morntor drawmg S/G into the RCS usmg the Sed and bleed 3.6/3.7 method 000 058 EK3.01 Knowiedge of reason for use of DC connot power by D/Gs.

3.4/3.7 000 059 SGAl!

Ability to =gmw abnonnal indicanons for system operanng ru.usrs wtuch are 3.4/3.8 entry level cmditions for emerBency and abnormal c-;+.g procedures 000 060 SGA7 Ability to explain and apply all system limits and precaunons.

3.1/3.4

000 061 EAl.01 Aixlity to monnor msnmac acmanon of alarms 3.6/3.6 PWR - RO EMERGENCY PLANT EVOLimONS - 36% - C^{=! and Vohane C-d Symem W}

013

%d Safety Features Actuanon System 12 05 014 Rod Posinon Indicanon Svstem 015 Nucicar Inarumentanon S5 stem W

01 017 in-Core Temperanse Monnor Svstem 1 02 j

02l 022 Contamment Coohng System i

l 15 025 Ice Cnndenarr Ssstem i

i 026 Cnnemnment Sprav d5 stern I

i i1 056 Cnr R- - System l

l 059 Mam Feedwater Ssstem 03 j

i i

06i AwoharviEmemency fecowater Ssstem i

06 i

iWi i si1 063 DC Becmcal Distnbunon Ssstem I

i i

i i

i4 068 ljamd Radwaste System i

I l

1 1

I i

iWi 071 Waste Gas Disposal Ssstem I

i j

j i

I i 29 l i

072 Area FMean Monitormg Ssstem i

j I 02 l l

l 1

i i

Sys. l Mode l h/A9 l ltem j import. l uul l000 l kl.01 l Une-itne anagram or power suppiv to M U sets (Cluten Power supply l l 3_v3 o 001 j 010 l A2.07 Idennty and rnincate an erroneous tiCPiECC calculanon.

l l cr3 o 003 000 K5.W Knowicoge or the etfects or RCP shutoown on seconaan parameters sucn as steam 32/3.5 pressure, steam tiow and feed flow.

0W 000 Kl.W Know1 edge or the relanonsrup between the CVCS and RCPs. includmg seat miecnon riowsj 3 468 013 000 K4.12 Knowledge or ESF design restures and mterlocks wtuch provide for satety miecnon olocx. l 3.769 013 000 Al.05 Abihtv to prearcs ana/or morutor chances m mam steam neader pressure wtien operaung 3.4/3o ESF concols.

015 000 K6 W Knowledge of pertomunce ano design armbutes or bistables and logic ciremts.

l3.1/3.2 015 000 Al.01 Abihty to penorm an blS calibranon by heat balance.

l3.5/3.8 017 020 Kl.02 Know1 edge or the relanonsrup between the IDI ssstem and the RCS.

33/3.5 017 020 A402 Abihty to morutor temperature values used to detemune RCSRCP operanon cunng 3.8/4.1 irWma core cooling (i e.. if applicable, average of five highest valuest.

022 SG A15 Abthtv to recogmze abnormal indicanons for system operanng pammeters wtuca are entn-3.5/3.8 lesel conditions for emergency and abnomul operanng procedures 026 SG All Abihty to recogmze mdicanons for system epi.auu3 parameters wtuch are entrv leset 3.2/4.1 conditions for tech specs.

059 000 K3.03 Know1 edge of the etfect that a loss or the MFW ssstem will hase on the S/Gs.

3.5/3.7 061 000 K4.06 Knowledge of AFW system design teannes and unerlocks utuch provide AfM startup 40/4.2 permissists.

061 000 A3.N Abtlity to rnatutor operanon of automane AfW isolanon.

t1/4.2 063 SG K5 Knowtedge of linunng conattions for operancas and sarety linuts.

30/36 068 000 A4.W Abthty to morutor autorranc isolanon.

3.8/3.7 071 000 A4.29 Abthty to mountor Wmg oxygen, hyurogen, and runogen concenuations m WDGS 3.0/3.6 decay tank incidag knowiedge oflimits.

072 000 K4.02 Know1coge of ARM system desgn tcannes and unertocks wtuch prmade for ruel butidmg 3.2/3.4 isolation. [ Fuel Handlmg alarms and interlocks)

i PWR -SRO PLANT SYSTEMS - 40%-Group 2 Group 2 - 17%

M K2 D

M M

K6 Al AZ A.) :M

$G 002 Fasnr Coolant System 15 5

006 F.uw u y Core Coolmg System 09 sil s

010 n-Mzer La C=ui System 02 jo3 011 Pim level Cuanus S> stem i1 012 Reactor Protecuan System (4

1. 12 016 Non-Nuclear instn-i uisuon Svstem 01 027 Contai, rm lodme Runeval System 028 m-drugn Recuihner and Purge Cuntrol Ssstem 01 JPM 0719 029 Contairurs:nt Purge System 03 033 Spent Fuel Pool Coolmg System 034 Fuel ilarmiling Eqturimas S> stem 035 Steam Generator System 01 039 Mam and Reheat Steam Ssstem 08 055 Condenser Air Removal Ssstem 062 AC I]ecmcal Distnbunon Svstem 01 I

JPM 0347 ot4 Ememency Diesel Gerierator System 02 l

5 i

0 73 Process Radianon Monitonrut Svstem of I l

075 Circulanng Water System l

l 079 Stanon Air System 01 JPM 0214 086 Fire Protecuon Svstem l

l jpl 103 Contamment Ssstem j 03 l l

j i

i Sys.

Mode K/An Item l Import.

002 000 K5.15 Know1 edge of the reason for mamtauung suocooiec margm aunng natural careutanon.

42/4o UO2 50 K5 Knowiedge of Imuung condluons for operanons and sarctv linuts.

3.6/4 1 I

(Xb 000 K4 09 Knowieage of ECCS design teatures unsch provide for the sarety mjecuon mjve intenocks.

3 8/4 1 010 000 K3.02 Knowiedge of the ettect that a loss of the P4R Pressure Control System will have on the 4 0/4 I RPS.

uli ux)

A2.11 Ability to predict anc nungate the consequences of failure or PZR levei instrument-low.

3.4/3 o 012 (XX)

K61M Knowledge of the performance and design annbutes of bypass-block circuits of the RP5.

3.3/3.6 016 000 Kl.01 Know1 edge of the relanonsrup between the NNIS and the RCS.

3.4/3.4 l

028 000 K5.01 Knowiedge or explosive hydroge's concenannon as applied to the HRP5 3.4/3.9 I

029 000 KI.03 Knowiedge of the relanonfups between the CPS and engmeered safeguarcs 3.6/3.8 035 010 A3.01 Ability to morutor automane operanon of the 5<U water level conuol.

40/3.9 039 (XX)

K4.08 Knowledge or MR55 design features wtuch provide intertocks on MSIV and bspass nives.

3.3/3.4 0o2 (XX)

K2.01 Knowiedge or power supplies to major ssstem loaas.

3.3/3.4 ot4 O(X)

K4.01 Knowiedge of EDU system design features and interlocks wiuch preside for tnps while 3.8/4.1 loadmg the ED'G (frequency, voltage, and speed).

004 50 K5 Knowledge ofImuung conastions for operations and sarety Imuts.

3.4/3.9 073 000 K4.01 Knowiuhje of PRM system design teatures and interlocks wtuch provide for release 4.0/4.3 temunation when Indiation exceeds setpoint.

l 079 (xX)

Kl.01 Knowledge of the relanonsiups between SAS and IAS.

2.9/3.1 103 000 A2.03 Ability to predict and nungate the consequences of Phase A and B [contamnr:nti isolanon.

3.5/ 3.8 i

PWR-SRO PLANT SY5TEMS - 40%-Group 3 Group 3 -4%.

KI KZ U

K4 K5

. K6 M

M M l M l SG 005 Resdual Iu h,wval Svmem 10 JPM 0323 -

007 T.m Relief Tank /Quss Tank System 01 008 r,...__. Cooling Water S)1 tem 041 Steam Du=p Systcm 08 G45 Main Turtune Generator 076 Senice Water System 02 078 Instmment Air System l

i t

i l

I i

1 Sys.

hixie.

K/A#.-

Item import.

005 000 K4.10 Know1 edge of RHR design features and interiocks which preside for control of RHR heat 3.1/3.1 exchanger outlet flow.

007 (XX)

A2.01 Ability to predict and mitigate the consequences of stuck-open PORV or code safety.

l3.9/42 041 020 A4.08 Ability to manually operate and monitor the steam dump valves.

l30/3.1 076 000 A3 02 Ability to monitor automatic operation of the SWS. including emergency heat loads.

3.7/3.7

PWR - SRO EMERGENCY PLANT EVOLUTIONS - 43% -Group 1 U,,,, g. 24w.

N u

u At u

.w UUU 001 C -*--nE Mod Withdrawal U2 UUU UUJ lhuppW Lunuvi Mod U4 07 UUU ULD 9-_-- - ' '5tudt Uussisui Mod UI J

UUU UIi 1.arge l$rcak LULA 12 II UUU U13 KUP Motor Malfuncuan 21 12 UUU U24 tmergency l$orauon U2 JPM UUUil UUU U26 Loss of LouyuuciE tooling Water U2 fu l l

UUU U29 Anucipated Iransient Without 5 cram (AlW5) 01 scenano i U00 WO 5tcam une Kupture 04 10 UUU V31 Loss otTr. 'mr Vacuum Ui UUU U33 Loss of Uttsite and Unsite Power U2 03 UUU 037 less of Vital AC EJcctncal Instnament l$us jui 19 000 039 AcMmmt Uqmd Madioacuve Waste Release 1i UUU 06/

Plant hre on bite 1/

UUU 06M Lontrol Moom hvacuauon 12 000 069 loss of Lontainment Integnty 11 000 074 Irwimme Lore Coohng US scenano 1 MAJ U/6 High Meactor Loolant Acuvity 11 lotals broup I=24

)

U i

3 4

3 bys.

Mode h/A#

Ite m jImpon.

000 001 thj U2 Anowledge or the rcasons for lecn-5pec ilmits on rou operaollity as Incy apply to u1e il,4.3 Continuous Rod Withdrawal emergency task.

MAJ 003 thi.W Anowledge of the ettects of power level and control posinon on delta ilu..

J.lij./

s 000 003 LAl.0 /

Ability to monitor in<: ore and ex-core instntmentauon.

3 5/3.5 UUU 003 LAl.VI Ability to operate and morutor the LMD5.

J N 3.4 000 003 50h3 Anowledge of the limiting condluons for operauons and safety limits.

3.1/3 o UUU Ull thj 12 AnowiQc of the reason for acDons (2-d urni m EUP for large break LUCA.

4.4/4 6 000 Ull LAZ.l l Ability to determme concluons for throttling or stopping HPI dunng large break LULA.

3.9/4 3 UUU U13 LAl.21 Ability to monitor the develupas;iE of natural circulanon llow.

44/4.3 MXJ U13 5UAll Abtitty to unhze symptom samW procedurcs.

2.9/3.2 000 U24 thl.UI KnowlWgc of the relauonstup between boron addtuon and change m lave as apphed to J.4/J.5 emergency boration.

000 UZ6 th3.02 Anowings of the taases for the automauc accons tahgnmerzts) within the LL System Jhi.9 resulting from the nemarion of the ESF.

UUU U29 thi.UI Anowledge of reactor nucleorucs and thermal-hydraulics behavior as applied to A1%5.

2.5/3.1 000 WO th3.N Anowiedge of the basis for acDons s1-6-1 m LUPs for steam line rupture 4.3/4. /

uMJ WU tAl.IU Ability to operate and morutor the AlW system dunng a steam hne rupture 4.1/4.1 UUU 031 th3 UI knowledge of the reasons for the loss of stcam dump capabihty upon loss of condenser 2X3.1 Vacuum.

UUU 033 thj.02 Anowlsdgu of the basis for acDons unsinused m EUP for loss of ottsite and onsite 4.3/46 power.

MX) 033 LAZ.03 Ab111ty to detemune when ' uncry is appava.laung tully discharged.

J 4 4.7 u

UUU U3/

LAZ.19 Ability to detemune the plant automauc acuans that will occur on the loss of a vital AL 4.0/4.3 electrical instrument bus.

000 039 50All Abthty to m.u5ruze JDhunnal indicanons for system operaung parameters wtuch are J.4/J.5 entry level conditions for emergency and abnormal upumung procedures UUU 06/

EA2.1/

Ability to detemune what systems may be attected by the urc.

3.3/4.3 UUU 068 EAl.12 Abthty to operate and morutor the auxtilary shutdown panel conuols and Indicators.

4 N 4.4 UUU 069 50All Abthty to Icw5:nze aboviumal indicauons for system operating parameters wtuch are 4 3 4.2 entry lewi conditions for emergency and abnormal operating procedures UUU 074 th3.03 hnowkdgu of the reason for secunng KLPs.

4.1/4.2

UUO U/b bOAll Abihty to rs

=hm4 mdimDons for system (-; + g==em wtuch are 3.4/3.6 entry level ma<h= for emergency and abnorrmi operating procedures FWM - 5HU R2MEJOtJR,T PLAIVI tNULU HUr0 - 43%-broup 2 Group 2:.m16%::

.KL IG.

IG Als A2

SG 3

000 007 Reactor Trip 03 000 008 Pressunzer Vapor Space Accident 02 000 009 Srmli Break I.OCA N

sundator.

000 022 Loss of Reactor Coolant Makeup 06 000 025 Loss of Residual &at Remomi System 01 000 027 Pressuizer Plessure Control System Malfuncuon 15 000 032 loss of Source Range Nuclear instrumentation W

4 000 033 loss of Intermediate Range Nuclear instrumentanon 02 000 037 Steam Generator Tube leak 8

000 038 Steam Generator Tube Rupture 39 l

000 054 Loss of Main feedwater 01 simulator 000 058 loss of DC Power 01 000 060 Accidental Gaseous Waste Release 7

000 061 Area R:vimnon Morutonng System Alarms 01 000 065 loss ofInstrument Air 06 lotals Group 2=l6 2

1 4

2 4

3 Sys.

Mode K/As.

Item l Import.

000 007 EKl.03 Knowiedge of the reasons for closmg trae mam turome govemor valve and the mam 3.7,4.0 turbine stop valve atler a reactor trip.

000 008 EK3.02 Knowledge of the reason why PURV or code safety valve exit temperature is below RCS 3tv4.1 or PZR temperature.

000 009 EK2.N Knowledge of sensors and detectors.

i2.3/2.6 000 022 EK3.06 Knowledge of the basis of RCP thermal bamer coolmg.

32/3.3 000 025 EKl.01 Knowledge of the erlect ofloss of RHR dunng all modes of operanon.

3.9/4.3 000 027 EA2.15 Ability to detemune accons to be taken if P4R pressure instrument tails lugn.

3.7/4 0 000 032 EA2.N Ability to determme satzstactory source-range / intermediate-range overlap.

3.1/3.5 000 032 SGK4 Knowledge of the bases in lechrucal Speciticanons for hminng condinons for operanons 2.4/3.3 and safety limits.

000 033 EA2.02 Ability to mterpret indicanons or unrehable intermediate-range channel operanon.

3.3/3.6 000 037 508 Abihty to recognize indicanons for system <vymg pammeters wiuch are entrv level 3.1/3.9 conditions for Tech Specs.

000 038 EAl.39 Ability to operate and morutor drawmg S/G into the RCS. usmg the reed and bleed 3.6/3.7 method.

000 054 EK3.01 Knowledge of the reason for a reactor and/or turbine Inp (manual and automanc) on a 4.1/4.4 loss of main feedwater.

000 058 EK3.01 Knowiedge of reason for use of DC connot power by INGs.

3.4/3.7 000 060 SUA7 Abihty to explain and apply all system hauts and precaunons.

3.1/3.4 000 061 EAl.ol Ability to morutor automanc actuanon of alarms.

36/3.6 000 065 EA2.06 Abihty to determme when to tnp reactor it mstnunent air pressure is decressmg 3o/4.2

PWR - SRO EMERGENCY PLANT EVOLimONS - 43% -Group 3

' -3%.

n xz. :n u u

33

. ',8 T.-level Malfuncuan 01 16 Fuel D- :ing Ir-r '---

5

.b loss of Ga'L. Power 01

~

^ ~

TTTTTT m,..

.cv ant vo unans.

TTT"TT"T" i

• I: _

{

K/M.

Item:

Import.

.- 3 EA2.01 Ability to detennine and interpret PZR level indicators and alaans.

3.4/3.6 6

SGAS Knowiedge of the annunciator alanns and indications, and use of the response 3.4/3.7 instructions.

5 EK3.01 Knowiedge of the basis for the order and time to initiate power for the load sequencer in 3.5/3.9 the case ofloss of offsite power.

~

PWR -SRO PLNU-WIDE GENERIC RESPONSIBILITIES - 17%

Kl.01 Knowi4 of how to n=% and venfy nlw lineups.

1 Kl.02 Knowi4 of tagging and clearance procedures 2

Kl.03 Kim,AJ,; of 100R20 and facahty radiation control requuernents 3

Kl.04 Knowi@ of facihtv AIARA prograrn 4

Kl.05 Knowie of facility requuements for controlling access to vital / control areas.

5 Kl.06 Knowiedge of safety procedures related to rotaung eqmpment Kl.07 Knowledge of safety procedures related to electncal eqwpment 6

Kl.08 Knowledge of safety procedures related to high temperature.

Kl.09 Knowledge of safety procedures related to high pressure.

i Kl.10 Knowledge of safety procedures related to causuc soluuons.

Kl.11 Knowledge of sarety procedures related to chlonne.

Kl.12 Knowiedge of safety procedures related to noise.

i Kl.13 Knowledge of safety procedures owgen deficient ermronments.

7 Kl.14 Knowiedge of saterv procedures related to contined spaces.

Kl.15 Knowledge of safety procedures related to hydrogen.

Kl.lb Knowledge et facility protecuon n:qmrements, mciudmg tire bngade and ponable tire righung eqmpment lX Kl.17 Knowledge of the eqmpment rotauon schedules and the reasomng behmd the rotauon procedure.

Al.01 Ability to obtam and venfv control procecure copy.

o Al.02 Ability to execute procedural steps.

10 Al.03 Ability to locate and use procedures and stanon direcuves related to shitt statting and acmlues.

I1 A1.04 Ability to operate the plant phone, page, and 2 way radio.

12 Al.05 Ability to make accurate, clear. and concise vertxil repons.

13 Al.06 Ability to mamtam accurate, cicar and concise logs. records. status boards and reports.

14 Al.07 Ability to obtam and interpret electncal and nrcharucal drawings.

A1.08 Ability to obtam and interpret ref. matenal, graphs. monogmphs, tables, contaaung system pertormance data.

Al.09 Ability to coordmate personnel acuvines m the control room.

Al.10 Ability to coortunate personnel acmines outside the control room.

Al.11 Ability to ducct personnel acovities inside the control room.

15 Al.12 Ability to direct personnel acmines outside the control room.

A1.13 Ability to locate ctri rm. switches ctris. & inds. and detemune if they are correctly retlecung desired line up.

Al.14 Ability to mamtam pnmary and secondarv plant chemism' within allowable limits.

16 Al.15 Ability to use plant computer to obtam and enluate parametnc mformanon on system and component status.

Al.16 Ability to take accons called for m the facility E-Plan. mcludmg suppomng or acung as Emergency 17

i l

l ES-301 Ar=:.,:= eGye Tooies Outline Form ES - 301 - 1 Examination Level:

RO Facility: Fort Calhoun Week of Eummation:

12/04/95 Exammer's Name (prino:

Admmistrative Desenbe method of evaluauon:

Topic / Subject 1.

ONE Administrative JPM. OR Description 2.

TWO Administrative Ouestions A.!

Plant Parameter Verification Shift Statfmg Requirements A.2 Taggmg and Clearances A.3 Radiauon Control A.4 Emergency Plan Exammer:

Chief Exammer

l l

ES-301 Ad=iai*ative Topics Outline Form ES - 301 - 1 l

Exanunation Level:

SRO j

Facility: Fort Calhoun Week of Examination:

12/04/95 i

Eununer's Name (print):

Administrative Desenbe method of evaluauon:

Topic / Subject 1.

ONE Administrative JPM. OR Description 2.

TWO Administrative Ouestions A.1 Plant Parameter Verification Secunty A.2 Temporary Modifications A.3 Radiauon Control i

A.4 Emergency Plan 1

Exanuner:

Chief Examiner.

.=.

(

ES-301 Indivulual Walk-thmuah Test Owliaa Form ES-301 Frammatmn Level:

RO Facility: Fort Calhoun Week of E.ununation: 12/04/95 E.ununer's Name (print):

l System / JPM Safety Planned Follow-up Quesbons:

l Function K/A/G //Importance // Description

l. 0008 ASP - Emergency I

a.

Boration from the Control q

Room b.

)

l

2. 0323 - Termmate IV a.

Shutdown Cooling b.

)

l

3. 0347 - Unload D/G #1 Vil a.

b.

4. 0778 - Adjust T-cold IX a.

I calibration on the RPS Panel b.

5. 0138 - Operate CVCS 11 a.

to makeup to the SIRWT b.

Simulator JPMs above this line. Plam JPMs below this line 6.

0719 - Startup VI a.

Ilydrogen Purge System b.

7. 0295 - Switch inverter VII a.

Supply from B) pass to Normal (modify to b.

l alternate path)

8. 0214 - Shift insemce Vill a.

Air Compressors b.

9.

0010RW - Loss of X

a.

Component Cooling WateriRaw Water) b.

10. New - Makeup to the V

a.

Emergency Feedwater Storage Tank using b.

Diesel Fire Pump Eummer:

Chief E.uminer:

l l

ES-301 1-- M."-- ' Walk-thmuah Test C '

F-ES 3012 Exammanan Level:

SRO(I)

Facility: Fort Calhoun Week of Exammation: 12/04/95 Exammer's Name (print):

System / JPM Safety Planned Follow-up Quesuons:

Function K/A/G // Importance // Description

1. 0008 ASP - Emergency I

, a.

Boration from the Control Room b.

2. 0323 - Termmate IV a.

Shutdown Cooling b.

3. 0347 - Unload D/G #1 VII a.

b.

4. 0778 - Adjust T-cold IX a.

calibration on the RPS Panel b.

5. 0138 - Operate CVCS 11 a.

to makeup to the SIRWT b.

I Simulator JPMs above this line. Plant JPMs below this line 6.

0719 - Startup VI a.

Hydrogen Purge System b.

7. 0295 - Switch laverter Vil a.

Supply from B pass to 3

Normal (modify to b.

alternate path)

8. 0214 - Shift inservice Vi!!

a.

Air Compressors b.

1

9. 0010RW - Loss of X

a.

Component Cooling l

Water (Raw Water) b.

l.

10. New - Makeup to the V

a.

Emergency Feedwater Storage Tank using b.

Diesel Fire Pump Exammer-Chief E.ummer:

l l

l

f l

ES-301 8 r +. " ' W alk i _-- Test Oasi-F-

ES-301-2 1

Ey====eion Level:

SRO(U)

Facility: Fort Calhoun Week of Exanunation: 12/04/95 Examiner's Name tprint):

System / JPM Safety Planned Follow-up Questions:

Function K/A/G // Importance // Description a.

b.

a.

b.

a.

b.

I a.

b.

1 a.

1 b.

Simulator JPMs above this line. Plant JPMs below this line 6.

0719 - Startup VI a.

j Hydrogen Purge System b.

7. 0295 - Switch inverter Vl!

a.

Supply from Bypass to Normal (modify to b.

alternate path)

8. 0214 - Shift inservice Vill a.

Air Compressors b.

9.

0010RW - Loss of X

a.

Component Cooling Water (Raw Water) b.

10. New - Makeup to the V

a.

Emergency Feedwater i

Storage Tank using b.

Diesel Fire Pump l

Exammer:

Chief E.ununer:

I l

ES-301 Sc==rio Events Form ES-301-3 Simulation Facility: Fort Calhoun.

Scenario No.: FCS-1 Exammen:

Applicants:

Initial Conditions : 100% power - BOL Tumover FW 54 ( Diesel driven AFW pump) and SI-2C (HPSI pump) tagged out of senice. Continue full power operation.

Event M alf.

Event Event Description No.

No.

Type

• 1 C

Dropped Control Rod 2

R/N Reduce power to 70% within I hour as required by Tech Specs 3

i Pressunzer Pressure channel fails "as is" 4

1 FT-910 fails high causmg turbine bypass valve to open 5

M/C Loss of all Feedwater - hiadvertant Steam Generator isolanon. AFW pumps will not start 6

C ATWS - Manual Divene Scram System inp required l

(

(N)ormal.

(R)eactivity.

(1)nstrument.

(C)omponent.

(M)ajor Examiner-Chief E.ununcr-i l

l

]

1 l

l ES-301 Sc= ado Fvents Form ES-301-3 l

l Simulation Facility: Fort Calin,usi Scenario No.: FCS-2 Exanuners:

Applicants:

1 1

I InitialConditions: 50% power-MOL l

l Turnover: FW-54 ( Diesel driven AFW ptunp) and SI-2C (HPSI pump) tagged out of senice. !?ontinue increastng power toward 100*4 l

l Event l Malf.

Event Event Description l

No.

I No.

Type

• 1 R/N Contmue Power increase i

2 1

PT-210 fails low causmg loss at letdown slow 3

I FT-907 (steam flowl tails low requinng manual SiG level control I

4 M

Small LOCA i

i 5

C 161 kV breaker to bus I A3 lails to close - No power to bi 2A 6

C D/G 1 licl:111 ashing tailure 7

C Remauung HPSI pump (SI-28) fails to start l'

l (N)ormal.

(R)eactivity.

(!)nstrument.

(C)omponent.

(M)ajor Exanuner; Chief Exammer:

i ENCLOSURE 2 E ACHMENT 2 l

SIMULATION FACILITY REPORT l

Facility Licensee:

Fort Calhoun Station Facility Docket No..

50-285 Oper6 ting Tests Administrated on:

December 5. 1995 These observations do not constitute audit or inspection findings and are not.

without further verification and review. indicative of noncomoliance with 10 CFR 55.45(b).

These observations do not affect NRC certification of approval of the simulation facility other than to provide information wnicn may be used in future evaluations.

No licensee action is reouired in respcase to these observations. While conducting the simulator r.,ortion of the operating tests. the following unidentified discrepancies were observed:

! TEM DESCRIPT!CN None