ML20197B316

Forwards Exam Outline for South Texas Project Initial Exams 50-498/97-301 & 50-499/97-301,scheduled for 971020.All Relevant Forms,Per NUREG-1021, Interim Rev 8, Included

ML20197B316
Person / Time
Site:	South Texas
Issue date:	08/19/1997
From:	Lawrence C HOUSTON LIGHTING & POWER CO.
To:	Bundy H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20197B061	List: ML20197B055 ML20197B316 ML20197B330 ML20197B369
References
50-498-97-301, 50-499-97-301, NUDOCS 9803110023
Download: ML20197B316 (47)

Text

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The Light company wuth leias Project I lettr6c Generating Station P.o. Elos 249 % adsworth. letas 774U houston Lighting as Power 3

August 19,1997 Mr. Iloward flundy Chief Examiner U. S. Nuclear Regulatory Commission 611 Ryan Pla7.a Drive, Suite 400 Arlington TX 76011 8064

Subject:

Initial Examination (NRC Inspection Report 50-498/97-301; 50-499/97-301)

Attached is the Exarnination Outline for the South Texas Project Initial Examination scheduled f or October 20,1997. I have included all relev. int forms per NUREG 1021, Interim Revision 8.

Please call me at (512) 972-7652 if you have any questions.

Sincerely, Craig [. Lawrence Facility Representative South Texas Project Nuclear Training Department c: copy ofIr w/o attachment J. I1. Cal T.C.Kow.

9803110023 980805

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PDR ADOCK 050004?O V

PDR Project Slanager on llehalf of the Participants in the South Tetas Project 070 W43// 0023 9

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ES 201 Enansnation outhne Form ES 2012 G*tahty Assurance Checkhst Facility: South Texas Proinct Dare of Examination: 10/21/97 initints item Task Desenption l

a b

c 4

1.

a. Verify that the outhnets) fit (s) the approp.iate model per ES 401, h

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b. Assess whether all six knowledge and four ability crtogones are appropriately sampled.

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c. Assess whether the outhne over-emphasites any systems, evolutions, or ceneric topics.

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h d,. Assess whether the opetition from previous examination outhnes is excessive.

2,

s. Using Form ES 301 S, venf y that the proposed scenano sets cover the required number of j

4 normal evolutions, instrument and component f ailures, and major transients.

m W S

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b. Assess whether there are enough scenario sets (and sparesi to test the projected number l

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and mix of apphcants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at l

least one new scanario and scenanos will not be repeated over successive days, f

c. To the extent possible, assess whether the outhne(s) conform (s) with the qualitative and

/

quantitative enteria specified on Form ES 3014 and described in Appendir D.

It I

3.

a. Verify that the outhne(s) contaan(s) the required number of control room and in-plant tasks and venfy that no more than 30% of the test materialis repeated from the last NRC W

e x amination.

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b. Venfy that the tasks are distributed among the safety function groupings as specified in ES 301: one task shall require a low-power or shutdown condition, one or two shall require the apphcant to implement on alternate path procedure, and one should require entry to the RCA.

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

d. Determine tf there are enough different outhnes to test the projected number and tvux of appheants and ensure that no more than 30% of the items are duphcated on successive days.

4.

a. Assess whether plant-specific priontees (including PRA and IPE insights) are covered in the

/

appropriate exam section.

ti Assess whether the 10 CFR 55.41/43 and 55 45 samphng is appropriate.

E

c. Ensure that K/A importance ratinos forcept for plant specific prionties) are at least 2.5.

A

d. Check for duphcation and overlap among exam sections.

e. Check the entire ewam for balance of coverage.

f. Assess whether the eenm fits the appropriate job level (RO or SROn.

b JP ntndfjam ture Date

//Nm

a. Author Wilham Arbour 2

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b. Facihty Reviewer (*)

Crad Lawrence

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c. Chief Examiner Howard Bundv

d. NRC Supervisor f *) Not applicable for NRC-developed examinations NUREG-1021 24 of 24 Interim Rev. 8 January 1997

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ES 301 Administratis e Topics Outline Form Eh.301 1 l'acility: South Texas Project Date of Examination: 10.'21/97 Examination i.evel : RO Operating Test Number:

Administra.tne Topic / Subject Describe method of evaluation:

Description

1. ONE Administrative JPM, OR

2. TWO Administrative Questions A.I Conduct of 2.1.3[30!3.4] K/O shill turnover practices Operations Review logs prior to accepting shift turnover 21.10 [3 O!3.01 Ability to use computer to obtain data Perform a Thermal Power Calculation A.2 Equipment Control 2.2.13 13.6/3.8] K/O tagging and clearance procedures Write a tagout for the Essential Cooling Water pump A.3 Radiation Control 2.3.10 [2.9] Ability to perform procedures to reduce excessive personnel exposure Locate valve in liigh Radiation Area A.4 Emergency Plan 2.4.39 (3.31 Knowledge of the RO's responsibility in the emergency plan Make the necessary communicatiora for given accident t

4 4

ES-301 Administrative Topics Outline form ES-301 1 l

Facility: South Texas Project Date of Examination: 1021/97 Examination I.evel: SRO Operating Test Number:

Administrath e Topic / Subject Describe method of evaluation:

Description

1. ONE Administrative JPM, OR 2 TWO A.t.., ~ %trative Questions A. I Conduct of 2.1.3 [3.0 '3.4,.,0 shill turnover practices Operations Review logs prior to accepting shift turnover 2.1.19 [3.0'3.0] Abilit) to use computer to obtain data Perform a Thermal Power Calculation A.2 Equipment Control 2.2.13[3.8) Knowledge of tagging and clearance procedures Review a faultert tagout for Essential Cooling Pump A.3 Radiation Control 2.3.10 [3.2) Ability to control radiation rel eases Review and approve gaseous release package A4 Emergency Plan 2.4.44[4.0) Knowledge of emergency plan protective action recommendation Make the necessary recommendation for a given set of conditions l

l l

I bmi indindual % alk through Test Outhne Form 051012 I aciht) Nouth Tesas Pro!ect Date of Esammation 10'20/97 I sam l esel(circle one) $R( hi t Operatinglest No. Il-I2 sptem / JPM fitte ! hpe Codes

• hafety Planned Follow-up Questums Functmo K!AU -Importance Desenptum l CRD5 Perform Rod Operabihty fest I

a 001000K508 3 9.4 4 K/O reasons for shutdown marpm tNWANS) b 001000A216 3 0/3.8 Possible causes for mismatched control rods 2 RCs Determine if NC flow I sist4 MS xl.)

11 a 002090K509 3 7/4 2 K/O relatamship of pressure and temperature b 002000K515 4 2/4 6 K!O reasons for mamtammg subcoolmg marem durmy NC 3 i CCS Raise Accumulator Pressure (MgAx5) 111 a 000000K602 3 43 9 K10 kws of accumulator b 00600t)K4ll 3 9'4 2 Ks0 reset of SIS 4 511/M51V Operabiht) Test (N M S)

IV a 015000K6013 2/3 6 KO the malfunction of M51V b 035000A2014 5/4 6 Abihty to predict the impact of faulted or ruptured S Ti 5 ChS/ Monitor Contamment Spra3 requirements V

a 026000A3014 3/4 5 Abihty to monitor pump starts and correct (DMS KL) sahe positioning b 21.32 3 4/3 8 Abihty to esplam all system hmits and precautions 6 ACil oad I:mergency Dus (DKS)

VI a 062000K104 3 7/4 2 K/O Off Site power sources b 062000A305 3.5/3 6 Abihty to monitor auto operation of indicators and controls 7 NIY Resp.md to SRNi channel failuret DxS)

Vil a Ol5000K505 41/4 4 KO mdications of criticality b 015000A205 3 3/3 8 Abihty to predict the impact on mdicatums of core sonimg 8 DC/Startup Battery Charger (N14 P)

VI a 063000K302 3 53 7 KO loss of DC to components b 063000K302 3 5/3 7 K/O loss of DC to EIXi 9 CRDSlocally trip the Reactor (N N P)

I a 2132 3 4!3 8 Abihty to esplam and apply all system hmits and precautions b 001000K614 4 0/4 i K!O loss or malfunction af re.or trip breakers 10 Al-Wi Relatch and locally Start the TDAFW IV a 061000K5013 6/3 9 K/O relationship between AFW llow and pumgN M P)

RCS beat transfer b 2.132 3 43 8 Abihty to esplam and apply all

• stem limits and precautions

• Type Codes (Durect fram bank. (Mimbfied from bank. (N ew ( Allternate path. (C kmtroi room, tSiimulator (1 wsw-Power (P)lant. (R)CA

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t L tol Indn wiual Watit. ) hinurh I est ( sutime i orm i %-301-2 I a.shh South lesas Project Date of Esiirnination 1020.97 I sam I cs elicircle onel RO / SRQ O Operatmg 'lcst No - U 14 and ROI-R06 Spicm ? JPM Title / h pe Codes

• Safety Planned Follow-up Questions 8imeton K/AU. Importance. Descriptum l CRDVRetriese Dropped Control Rod I

a 001000K409 3.9 41 K/O dropped rod recovery (MH ANS)

b. 001000K407.I 7/3 8 KO rod stops 5 RCS% tart RCP(Dx%NI.)

11 a 003000K30117/4 0 K.O the etTect that a kws of RCP on 'tCS b 003000A202 3 7/3 9 Abihts to predict the impact of an abnormal shutdown 3 [ CCS Transfer to llot i eg Recirc (Dx Sxt )

ill a 006000K 103 4 2/4 3 K/O phyucal connections between ECCS and RCS b 006000K403 3.2/3 6 K!O ECCS interkicks for flowpath through reactor bldg sump 4 l.CW/ Shill runnmg 1.CW pumps (Di(S)

IV a 076000K402 2 9/3 2 K,0 automatic start fc6 iurcs anociated with I CW b 076000A2013 5/3 7 Abdity to predict the impact ofloss of FCW 5 !!)drogen Recombmer' Start flydrogen V

a 028000A1013 4/3 8 Abihty to predict changes m hydrogen Rccombincr (D)t S) concentration b 02dO00A2013 4/3 6 Abihty to determme the recombmer power se' ting 6 EIK11[Xi Standby D-G Operability Test (DXS)

VI a 064000K10141/4 4 K/O physical connections with the AC system b 064000K4013 8/4 i K!O trips while loadmg EDG 7 CCW/ Transter CCW heat Ischangerst uit5)

Vlli a 008000K401310 3 K/O automatic start of standby pump b 008000A308 3 6/3 7 Automatic actions associated with the CCW ssstem 8 DC/Startup ilatter) Charger (NkP)

Vi a 063000K302 3 5/3 7 K/O loss of DC to components

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b 063000K302 3 5/3 7 K/O loss of DC to EIM 9 CRDWally inp the Renetor(NXPW A)

I a 2.I 32 3 4!3 8 Abihty to explain and apply all system hmits and precautions

b. 001000K614 4 0/4 i K!O loss er malfunction of reac ar trip breakers 10 AFW1 Relatch and ta: ally Start the TDAFW IV a 061000K5013 6/3 9 K/O relationship between AFW tiow and pumpN g P)

RCS heat transfer I

b 21.32 3 4 7 8 Abihty to explam and apply all system hmiu and pre-

• Ispe Codes (Dhrect from bank. (M kidified from bank. t N ew. ( Ailtemate path (C

• oom. (S iimulator. f t.)ow Power, ( P)lant. ( R )C A i

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I o vil Indnidual walk Through Test Outhne I orm I 4101-2 I acihts south lesas Protect I) ate of liammation 10/2tF97 I sam l o ct (circle one) SROiU)

Operatmg 'lest No - Ul U2 J

Ny stem / Ji'N1 Title / 1 y pe CoJes' safety Planned I ollow up Questions l' unction KI A'O. Importance - Description 1 RCS1.)etermme if NC llow l-hts (D u $ 1 1.)

ll a 00200f)K509 3 7/4 2 KiO relatninship of pressure and temperature b 002000K515 4 2/4 6 K/O reasons for mamtammg subcoohng margm durmg NC 2 S U/htslV Operabihty Test (Nh 5)

IV a 035000K6013 2/3 6 K/O the malfunction of AISIV b 035000A2014 5/4 6 Abihty to predict thw impact of faulted or ruptured s'G 3 i uel lland Respond to I uel llandimg illdg Vill a 03400()A102 2 9/3 2 Abihty to predict changes m water lesel lAhaust Alarm (DXP) b 2.132 3 4/3 8 Abihty to explam all system hmits and precautions 4 CVC51stabbsh Alternate chargmg flow control l

a 00006AK318 4 2/4 5 K!O reasons of ma.ior steps contained in (Du P)

I ops b 004000A104 3 9J41 Abihty to predict P7R lesel and pressure I

changes 5 14XL1.ocally stop EDG (N)(Px A)

VI a Co4000K105 3 4!)(, Knowledge of the physical connections of startmg air b 2132 Abihty to explam and apply all system limits and precautions for the I:DG 6

a b

7 a

b f,

a b

4 a

b to a

b

' lype Codes (Durect frem bank. I Nt hdined from bank. tN iew. ( Allternate path. ICiontroi rmm. (Shmulator. it.kiw-Power. (P ilant. (R)C A

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.x W ml Indnidual Walk.T hrough Tot ( nutime Form i 4 4012 Iacihn %outh icgas Princet Date of f sammation 10/20 97 laam I csci kircle one) 5RtXU)

Operatmg l'est No ' U3-il4 5ptem / JPM Iule /1 pe Codes

• hafety Planned follow-up Questions-3 I unetion KiA O - Importance - Iwergren I AC/Ahyn !quipment for I oss of AC VI a 062000K410 31/3 5 KA) design and operationi of un-(D N S k L) mterruptible powet supphes b 000057A214 4 0/4 3 Abihty to determine the plant automatic actions that occur from loss ofinstrument bus 2 CR DSAtuck31:sahgned Rod (NX A N S)

I a 001000K423 3 4!) 8 K!O rod motion inhibit b 000005A203 3 5/4 4 Abihty to determme the required actions if more th4m one rod is stuck 3 AC/Startup instrument Inserter (DM P)

VI a 000057A1013 7/3 7 Abihty to operate VitalInstrument lius duiine swar b 1112 3 4/3 8 Abihty I explam all system limits and precautions 4 S tiil ocal Pol 4 V operation (N X P) lV a Om1068 A205 4 2/4 3 Abiht) to momtor the asailabihty of heat smk b 035000K602 31/3 5 K!O malfunction of PORV 5 IASlinke kwal actions for 1.oss o instrument Air Vill

a. 000065A208 2 9 3 3 Alahty to determme the fadure mode of r

( N P) equipment on kws of air

b. 000065K308 3 7/3 9 K/O actions contained in EOP for loss of air 6

a b.

7 a

b 8

a b

9 a

b 10 a

b

• T)pe Codes D>irect from bank. I M iodified from bank. (N iew ( Ailternate path. (Cbntrol mom. (S timulator. (l.iow-Power. (P)lant f R CA

Er av i M kJ b omination Outline '~

term o-401-4 f acility: South Texas Project Date of Exam:10/20/97 Exam Level:R0 K/A Category Points lier Group Point K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

Total k h!

h INS ED 3

4 1

16 1,

1 2

1 5

hEhh Emergency &

2 3

4 3

.h kk 2

4 1

17 Abnormal Mant h k h5 3

0 0

1 0

3 1

1 Evolutions

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u q

y Tier S

5 9 gy

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]

6 9

i 2

36 Totals 7 'h c, 3

e

.M 1

4 1

1 6

2 1

2 1

2 1

2 23 2-2 2

1 3

3 1

1 2

4 1

1 1

20 Plant 3

1 0

2 1

0 0

1 1

1 0

1 8

Systems-Tier 7

2 6

10 3

2 5

6 4

2 4

51 Totals 3.

Generic Knowledge and Abilities

-Cat 1 Cat 2-Cat 3 Cat 4 3

3 2

5-13__

Attempt to distribute topics among all K/A categories; select at least one Note:

• topic from every K/A catego:y 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 K/A topics from a given system unless they relate to plant-specific priorities.-

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

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

N'JREG-1021 30 of 39 Interim Rev. 8. January 1997 w

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p l'/APF a / Name / hatch I unctum 06 KA M abe eterrelatnes tetween 1 aWi tcf deua'mm meter 3o fxxxJul Contmtmars Rod % thdrawal/I 03 ANiin to eterpret drTred rmt 34 (M Wull l) topped Control Rtml / I X

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( *per ations 2129 k1) how to wnduct and scrih sahe Imrups 44 2l 21 2I I otal 2211 L () taremp and clearance pre cdures 16 2222 L t ) hmiting conditions for eperation and ufety hmins 14 1 quipment Control k T) RO duties in the control room durmg f uel handhne 14 2212 22 22 22 lotal 212 L'O facihts Al AR A program 25 2?4 k 0 radiati-m esposure hmits and contamination control 25 Hadiation Contr01 y3 21 21 21 Total j4 2 k (l spicm setpmnis and automatic actions associated with I OP entrs 19 241 Ahihty to iJentity post accident mstrumentation 15 2414 k-() eeneral cuidelmes for i OP usaec 30 g

Praedures and gqan 2412 k't 1 opentor respm se ta loss of al, annunemtors 31 2441 k!() emergency communications ustems and techmques 2R 24 t otal k(

4k e

k I t(

NUREG 1021 1 ?f 39 Int.erim Rev. E

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bJ I

_. _ ~... - _.. _ _ _ _.

[S-401 PWR SRO i nminatinn Outline Form ES 401 3 facility: South Texas Date of Exam: 10/20/97 Exam tevel:SRO K/A Category Points

-Tier Group Point K1 K2 K3 K4 K5 K6

'Al A2 A3 A4 G

Total 1.

1 4

'3 5

Mih ffh hh h h 5

5 2

24 w ~.

}un bw%

Emergency &

2 1

1 6 l'/} M 3

4 4'

I 16 n ma ant 3

0 1

0 N$ N Id 0

lfh 0

3 Evolutions T

s 3

4 1

1 4

2 1

1 1

0 1

1 19 1

2.

2 1

1 2

2 1

1 1

4 1

1 2

17 Plant Systems Tier 5

2 5

7 3

2 2

6 3

2 3

4')

Totals 3.

Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 5

4 2

6 17 Attempt to distribute topics amonc all K/A categories; select at least one Note:.

• topic from every K/A 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 K/A topics from a given system unless they relate to plant-specific priorities.

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

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

NUREG-1021 23 of 39 Interim Rev. 8. January 1997

PW R NRt )I ummatnm Outhne 3 "'" I

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I mercerwy and Abntwenal 1%nt I m3utwas - I act i emp 1 I c Apl a / Name / Natety I urnIam k

A G

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tanW)] t ontmoous Raf Wtthdrawal / I m

W M & mienelate been f asemeMuatam mem 1I 01 Atsdm to mterpret dropped rm!

tg (WWH I)ropped Onetrol %1/ I Of M)the reaves for emerge twwatum m the esent of a stud rod 41 iWHM14 InoperableStud Cimtrol Rod / ! #s IWnilI I aree lircak I OCA / Ill Of K5 ) the operatumal unphcate of natural crrtulatur and ca.ime 44 W 'l 14 I i m ' A i Ntsule Contamment /111 I

Abihts so operate crvnpiments and safets nssems 4o

%.I O2 $1 f crmmatum / !!!

2 W procedures associated wreh NI termmatum 39 EWult 5J17 R('P Malfunctums / IV 22 Abihty to operate memrtm KCP wal fa:Iure malhmetew 4y 11% st 09 Cl /A l 3 %!! 49A l'lO Natural Cnc / IV 3

W manipulatum occontmh requwed to obtam results,durme natural cm.uiatam i es 1

(MNio2 4 I mereencs ikwathm / I #s 01 KO when emergenes horatam es requtred 44 (N o)2r* ( ou of Cornpiment Coolmg Water / Vill X

2 I B Mh to We Wen @nt medum 4o nullr> 1.ow af Component Coolme % ater / Vill 05 Abihts to operate rmmet w f f WS uwee tank 3i 14 Abibt> to operatc >nummy the drrung of contnit rods mia the core t9 Mn)29 Anocrpated Iranuent w:b scram / I 00140 t1t% t 05.CD105. Wif 12) steam Iine Rupture Of KA) the operatumal emphcarnes of I'I N 44

-I scessise iteat Iransfer / IV 2

Abehty to adhere to proper procedures 4g CI /A I 1. W -l OR RCS i hercoolme - PIN / ly EMU)Si Ims of Condenser Vacuum / IV Abdm to determme condstens requrrmg a reactor. rip 4i OtoM5 5tatwm lilackout / VI 07 Abihts to operate egorpenent fiw restoratoim of power from othne 45 (Wp)571 oss of Vital AC I lec Imt lius / VI 19 ANitty to determme plant resprese to lou of m<trument bus

.3 0(uR9 AcculentalI equki RadWaste Ret / IX 01 K.O the mterrelations between Ace Release and hquid nwwntews 2A munts2 I oss of Nuclear scruce Water / IV **

X 2123 Abdm to perform nstem'pluit procedure 4o (notr>7 Plant bre On-site / IX 01 W the fire clamficate b hpe 39 i

(u nio8 (14W/A06) Control Room liac / Vill 01 KN)avuhars shutdown panellawat 4o (ul00t>9 ( W.F 14 ) I oss of C1 M f Inteerrts / y 02 Abdrg to erifv atno amtum of contanunent Manon 44 000074 (Wit 06&E 07)lnad Core Coohng / IV lI K/O the reasons for evidance m i OP f.w Inadequate Co e Coolmg 44 I

InMl76 Iheh Reactor Coolant Actiun / f X 05 KN) correctrse acteom for toch radmacteutv m the RCS t6

!!n /A02A A03 Ims of NNINY / Vll 6

4 3

5 5

5 2

Ciroup Idmt hital 24 K/A Category fotals

P% R SRO Essmmatum Outime kwm i uit.;

ggg i merrency and Absuwmal Plant I volutens - Tier I Uroup 2 K

K K

^

G UA IopMsl Imp ivath l > API _ # / Name / Safety f uNtam p

03 KA) of mtervelatste hips of reactor trrp status pax!

36 otx xu)7 tilW 'l O2&f 10. C13 02) Reactor I rtp.

Stsbehratson - Recmen / I OtXHJ7 (llW 7102Al 10. CF;1021 Reactor 1 rip -

X 2 418 KM) specific bases for FOP's 16 Stahdaratum - Recosen / I I1W/A01 Plant Runback / I f1W/A44 Turbme Trtp / IV 08 Abday to gerate and momfor PR T pressure and temperature 18 000 lit:8 Preuurtref Vapor Space Accident /111 21 KA) actwms contamed m FOPS for srnail break i OCA (KWM)9 Smalllireak 1(M'A /!!!

11Wil OR W,l'01 i f M'A CmAlown. [kpress / IV W/ Ell Ims nfI rnereencs Coolant Recac / IV o

Of Atnlm to determme s.herber charrmg ime leak custs 3g 00t N)22 I oss of Reactor Coolant Makeup / It 07 Abdnv to determme pump cauteam

7 OixiO25 I oss of RilR Sptem / ly Of A'sdrry su operate PZR heaters. sprays and PORVs J9 Of Nm)27 Pressuriier Pressure Centrol Sptein Malfimetum

/ 111 01 K/O the reawns for the startup termmatum on source rance has 16 IXh n)12 Iio of Suurte Ranee NI / Vlj 02 Abdas to determme mdecatums of unrehable IR charmet meraram 36 (xjamill I oss of Intermediate Rance NI / Vil 10 W & reasons fm amanam Mm asmated u nh bgh rad m S G sart ple 37 (o nJ)7 Steam Generator Tube Leak / Ill hnes 05 KK) the reasons for the premutams to mmemi,e SGTR 43 (HM)38 Steam Generator T ube Rupture / lil 02 KA> the unphcatums of introd.sctum of feedwater to hot dn SU 42 Of Mxl54 (CF;} 06p Ims of Mam feedwater / IV 13Wil 04, W,105 Inadequate llent Transfer - E oss of Secondarv fleat Smk / IV 02 W asms catarned in pmede fw km M N 42 (xp)58 I oss of DC Power / VI 05 Abdnv to determme that autornaw safen actm have wwred as a result of rad 42 Osxibo Accidental Gaseous Radwaste Ret / IX 01 Abdm to erwatetor automatic actens 16 (WNMI ARM Sptem Alarms / Vil WTl6 ilech Contamment Radiatum / IX 08 W reawms fa actions maaM m pnxedures fw kiss # m av 19 (XnMS Ims of instrument Air / Vill C0109 l'unctumal Recmen I

I 6

3 4

Group Pomt Total f 6 K!A Categoty Pomt Totals.

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i o hi

( g nens knatcJge and Abihties ( hiihne t Iits 3 h IormI%4ald

_I am <'. h %mih Tesa, Proic,t

1) ate of _I sam to 20 97 I sam I esel A ld i

('ategi n k'A*

Iork Imts Pomts 217 Abihn ta esahute lilant performanse and nuke iudgements 44 2 I li k -O less than one hout 1 % htum statements 18 t ondst of 2112 Abihty hs appis l \\ for a w sicm 40 2 I II k t i t icihty requiremenh for controlhng acum 29 2 I IN Abihty to make accurate innd con ise logs 10 21

'I otal 22l2 (1) surollance procedures 14 221) k 1) tagging and clearanse proecslures 1R

[

c 2222 k<n hmitmg conditions for operation and safet3 'imits 41 I quipment Control 2221 Abihty to trad hmitmp conditions for operation 18 22 22 fotal 232 k O lacilin Al All A progra.n 29 214 k O radution espmure limits and contammation control 3I Radiation Control yg 2\\

21 2.1 Total 242 k?O ustem setpomis and autonuta actions associated with I-(IP entn 41 24i Abilits to identifs post-acendent instrumeiltation

.I R 2414 k U general guidehnet for i OP usage 19 Procedures and Plan 24 I6 k'o I OP implementation hierarchs 40 2419 k-O I OP layout. sym' ois and icons 17 2440 k O NRO.,ponsibilities in t Plan implementation 40 Total

-lier i larget Pomt l etalilu ) % hoi 17 NUREG-1021 1 of 39 Interim Rev. 8. January 1997

Appendix D Scenario Outhne i orm ES-D-l l'acility: South l exas Project Scenario No.: 1 on tr ;0'97 Op-Test No.: 1 laaminers: _. _ _

Operators: SRO U3,U4 RO R5,R6 I?OP il,13 Objectises: 1: valuate the crew's ability to respond to a SGTR esent Imtial Conditi ns: IC 1 100*h power at N10L Failure of Auto Reactor tr;p l umover:

The p; ant has been at 100's for 100 days. The crew is directed to reduce powcr to less than 9096 within the nest hour to perform hts Sahe Operability Test.

Esent h1alf.

Event Event No.

No T ype' Description IC l IC 1 N!A Full power steady state OR-02 01 DOP[C]

AFW pump 14 trips on oserspeed 01-12-01 RO [C]

I'uilure of Auto Reactor Trip SRo[C) 1 N'A Place Charging pump in service 2

N'A RO[R]

Power decrease to support N1S Valve Operability Test SRO1R]

3 05-17-01 DOP[Il Steam Generator il PORV pressure transmitter PT-7412 fails high SRO[Il 4

02-19 02 RO[1]

Pressurizer pressure transmitter PT-456 fails high SROlli 5

02-13 02 RO[C]

Pressurizer PORV 656 fails to close and the associated block valve must SRO[C]

be closed 6

05-03-02 ALL Steam Generator Tube Rupture S'O 1B [0.8 severity (800gpm) ramped

[h1T) over 10 minetes. Initiate when SRO transitions to OPOP05-EO-ES01, Reactor trip response

' (N)onna'. (IOcactivity, (1)nstrument, (C)omponent, (N1)ajor l

l

Appendis D Secr,. trio Outime i. rm 1:S D 1 l atility: South le,as Project. htenario No : 2 on 10'20'97 Op Test No.: I lisammers:

Operators: SRO 11.13 RO 12.14 llOP R$ R6 Objectises: 1:s aluate the crews response to a steam break in containment coincident uith a RCP Seal failure.

Initial Conditions: IC-4 30ae power i A CNMT Spray pump fails to auto start

'lurnoser:

The plant is at 30?h power with a reactor startup in progress.

1he crew is directed to ramp the uni' to 5086 and hold power for chemistry sample.

lhent Malf.

Es ent thent No No.

1)pc' Description IC IC-4 N/A 30*6 Steady $ tate Power

% 16 01 ilOPlc I A CNMT Spray pump fails to auto start SROic l

N!A ROlR) 1.oad increase to 50 t b power SRO[R]

2 06 16-02 RO,il First : age pressure transmitter PT 505 fails high IlO P I)

SitO 11 3

N/A g

Restore pu.nt following 1%s05 failure 1

10 12 07 110P C' l.oss of MCC ElC) results in loss of Letdown 3-SRO C' s

5 03 23 05 RO[C]

RCP No 1 Seal Failure Ramp over 5 minutes f-SROlC) 6 05 02-02 Al.l.

Steam Break in containment MT I-

• (N)ormal, (R)cactiut), it ament. (C himponent. (M)ajor

=

=

N P

l

AppenJn D Ncenario outline l'orm i s D-1 I

I auht) South Tesas Project Scenano No.: 3 on 1020'97 Op lest No.: I lisammers.

Operators: SRo l2,14 RO 11,13 llOP R5.R6 Obje(Inet lialuate the (tew's response to I.OCA with a failure of Phase A and 1:D0.

Initial Conditions-IC-1 100* a l'ull Power i.mergency Diesel does not load l'ailure of Auto Phase A l urnos er:

The plant has been at 100a 6 for 20 days.

T he crew is directed to reduce power to 90a. within the next hour for N15 Valve operability test.

13 cnt h1alf.

I:sent inent No.

No.

Type' Description IC IC-l N'A l'ull power steady state timergency Diesel Generator Pfl 01 12-RO[C]

l'ailure of OClV N10V-00241.etdown ise'ation to close on Phase A 04a SRO[C]

actuation i

N 'A IlOP N Perfonn Power Availability surveillance SRO'N'

~

2 N'A RO[R)

()ecrease power to 90*s to conduct h1S Valse Operability Test SRolR) 3 02 20-01 Roll]

Pressuriier lesel transmi:ter I.T-465 fails high SRoll]

6 4

04 09-0l llOP[C]

1:CW Pump trips SROlC) 5 05-14-01 IlOP[1]

Steam lleader pressure transmitter fails Skoll]

6 02-01-01 Al.l.

RCS Cold leg rupture loop I A N1T tN)ormal. (R)eactiut), (1)nstrument, (C)ortponent. (hilajor

! t,..< 01 Trant,1ent and I verit Og cklist form ES 3015 Of'lRAllNG TLS1 fo. 1 10/?0/97 tiparade SRO Applicantt 113/tl4 Applicant Evolution Minimum Scenario Numter Type Type Number 1

?

3 4

Reac tivi t y 1

Normal 1

Instrument

?

R0 Component

?

Ma.1or 1

Reactivity 1

Normal 0

instrument 1

As R0 Component 1

Ma,1or 1

SRO 1 Reactivity 0

Normal 1

Instrument 1

As SR0 Component 1

Major 1

U3/U4 SRO Reactivity 0

2 Normal 1

1 SRO U instrucent 1

3/4 Component 1

5 Major 1

6 Instructions: (1)

EntertheoperatingtestnumberandrgrmES-D-1eventnumbersforeach evolution type.

(2)

Reactivity manipulations must be sigm ficant as defined in Appendix D.

Authur.

William Arbour Cnief faaminer:

Howard Bundy

(5 331 Transient and Emot 0+cklist form ES 3016 OPERAllNG 1[Si NO.

1 10/20/97 Peactor Operator Applicants RS/k6 Applicant Evolution Mininum Scenarto Number lype Type Number 1

?

3 4

RSR6 R5R6 RSR6 R0 BOP BOP Reactivity 1

2 Normal 1

1 1

Instrument 2

4 2

S R0 Component 2

5 4

4 Ma,1or 1

6 6

6 Reactiv1tv 1

Normal 0

instrument 1

As R0 Component 1

Major 1

SRO 1 Reactivity 0

Normal 1

Instrument 1

As $RO Component 1

Major 1

Reactivity 0

Narmal 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 sigatitcant as defined in Append 1x D.

Author:

William Arbour Chief Examiner:

Howard Bundy

]

!5 30I 1ranstont and ! vent (tinckl t st for m [S.301-b OPERATINS T[ST NO. I 10/70/97 Instant SRO Applicants 11/13 Applicant b olution Mirimum

$cenario Number Type Type Numt3er 1

?

3 4

Reactivity 1

Normal 1

Instrument

?

R0 Component

?

j Major 1

11/13 11/13 BOP RO Reactiv1ty 1

?

Normal 0

Instrument 1

3 3

As R0 Component 1

6 6

i Major 1

6 6

i SRO 1 1113 l

Reactivity 0

1 Normal 1

3 Instrunent 1

2 i

Component 1

4/5 l

Major 1

6 Reactivity 0

Normal 1

l SRO U instrument 1

Component 1

Major 1

Instructions: (1)

Enter the operating test number cnd Form ES-0 1 event numbers for each eiolution type.

(2)

Reactivity manipulations must be significant as defined in Appendix D.

AJthor William ArD0ur

(.hief Examiner:

h ard Bundy l

l 1-

cm el 1, ans mnt w1 ! o nt 0+ci li tt forn [5-331 4 GN kATINS 1( 51 N 1 1

10/;-0 /9/ In:,t ant EPD ArDi > c nnt s l?/14 Applitant i.olution Min % m bc en3r t o tumbr r iype iype Number 1

?

3 4

Prattivitv 1

N:>rm:sl I

instrument

?

RO component

?

Ma lof I

I?/14 RO Reactiv1tv 1

1 Narmal 0

3 Instrument 1

2 As R0 Component 1

5 Ma1or 1

6 SRO 1 12/14 SRO Reactivity 0

2 Normal 1

1 Instrument 1

3/4 As SRO Component 1

4/6 Major 1

6 i

Reactivity 0

harmal 1

SRO-U Instrument I

Component 1

Maior I

Instructions (1)

Enter the operating test number and form ES-D+1 event numbers for each evolution type

(?)

R0rtivity manipulations must be significant as defined in Appendix D.

Author:

Wt11iam Arbour Chief [x3 miner' How3rd Bundy

f5-30)

Competent ms Checklist form fS-301 6 CkiW l Applicant U3 Applicant 11 Applicant 12 SRO-U SRO l SRO-1 Competencies SC[NARIO SClNARIO SCENARIO l-2 3

4 1

2 3

4 1

2 3

4 Understand and interpret 3

3 2

3 2

3 Annunciators and Alarms Diagnose Events 3

3 2

3 2

3 and Conditions Understand Plant 3

3 2

3 2

3 and Sys.sm Pesponse Comply With and 4

3 3

3 2

3 Use 'rocedures (1)

Operate Control NA 3

NA 3

2 NA Boards (2)

Conmunicate and 5

6 6

6 6

6 Interact With the Crew Demonstrate Supervisory 6

NA 6

NA NA 6

Ability (3)

Comply With and 4

NA 5

NA NA 3

Use Tech. Specs (3)

I Notes:

(1) includes Technical Specification compliance for an R0.

(2) Optional for an SRO U.

(3) Only applicable to SR0s.

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

Author:

Willlam Arbour Chief Examiner:

Howard Bundy 1

l

._.___..._._______.____.__.___m>___

_.._..___.__.~._._.m_

1% Al Cornpe t enc l e: C hec k li st form L5 3Dl 6 Lkt W l Applicant R5 Applicant #2-Applicant #3 RO RO/SRO 1/SRO U RO/SRO-1/5PO-t!

Crr w tencies SCI tsar 10 SCENARIO SCINARIO 1

2 3

4 1

?

3 4

1 2

3 4

Understand and Interpret 4

2 4

Annunciatnrs and Alorms Diagnose tvents 4

2 4

and Conditioni, Understand Plant 4

2 4

and System Response Comply With and 4

2 4

llse Procedures (1)

Operate Control 4

2 4

Boards (?)

Communicate and 6

6 6

Interact Witt: the Crew Demonstrate Supervisory NA NA NA Abil1tv (3)

Comply W1th and NA NA NA use Tecn. Specs. (3)

Notes:

(1) Includes fechnical SrKcif tcation compliance for an R0.

(2) Optional for an SRO U.

(3) -Only applicable to SR0s instructions:

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

AJthOr William At'bOur i

Chief liam1het HOWard Bundy l

l

1 i

($ 3'il C(cDetencies Check'151 f orm [S 301 6 CREW 2 Applicant U4 Applicant 13 Applicant 14 4

i SRO U SkO l SRO 1 Competencies SCENARIO SCENARIO SCENARIO i

1 2

3 4

1 2

3 4

1 2

3 4

Understand and interpret 3

3 2

3 2

3 Annunciators and Alarms 1

Diagnose Events 3

3 2

3 2

3 and Conditions Understand Plant 3

3 2

3 2

3 and System Response 1

i Comply With and 4

3 3

3 2

3 Use Procedures (1)

Operate Control NA 3

NA 3

2 NA Boards (2)

Comunicate and 5

6 6

6 6

6 Interact With the Crew Demonstrate Supervisory 6

NA 6

NA NA 6

Ability (3) f Ccepl, With and 4

NA 5

NA NA 3

Use lech Specs. (3)

Notes:

(1) Includes Technical Spec 1fication compliance for an RO.

(2) Optional for an SR0-U, (3) Only applicable to SR0s, i

instructions:

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

Author:

William Art >our Chief Examiner:

Howard Bundy

i 1

1

-\\

( t, - 3 W Lonpetencies Oiecklist iorm L5-301 6 ERlW 2 t

N Applicant R6 Appl 1 cant #2 Applicant #3 R0 K0/SRO 1/SRD tl R0/SRO 1/SRO ll

' ompe Lenc 1 er if[NAR10

'dLNAR10 SCiNARIO 1

2-3 4

1 2

3 4

1 2

3 4

Under s1and and Interpret 4

2 4

Annunciaicrs and Alatms Didanase Lvents 4

2 4

and Conditions Understand Plant 4

2 4

and System Pesponse Comply With and 4

2 4

Ure Procedures (1) 0;wrate Control 4

2 4

luards (2)

Cocxnunicate and 6

6 6

Interact With the Crew Demonstrate Supervisory NA NA NA Ability (3)

Comply With and NA NA NA Use loch. Specs (3)

N?tes:

1.

(1) locludes iethnical Specification compliance for an R0.

(2) Optional for an SRO U.

(3) Oniv applicable to SR0s.

Instructions:

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

Aather Allliam Arbour Chief [3aminer-Howard Bandy w.

M

,-g,,--y,.,

,c

..y--.

-r-.

Appenda D Scenario Outline i orm 1.5 D 1 l'acility: South Tesas Project Scenario Noa i on 100lM7 Op Test No.: 2 laaminers:

Operators: SRO Ul,U2 RO Rl,R3 liOP R2,R4 Objectises:livaluate the crew's response to a SGTR with a failed open hiain Steam Safety Vahe initial Conditions: IC-4 3096 power Rods fail to mose in Auto Turnoser.

The plant is at 30*6 and a return to power is in progress.

t he crew is directed to raise power to 50* b power and hold for chemistry samples.

!!sent h1alf.

Esent Es ent No.

No.

Type' Description IC IC 4 N/A 3096 S::ady State Power i

N/A RO[RI Lead increase to SO 9. power SRO[R]

2 01 09 01 RO[C]

Rods fail to mose in Auto SRO[C]

3 N/A gg Startup h1FP to support power ascension SRO N 4

.02 20-01 gl Pressurizer les el transmitter I.T 465 fails low 05 12-02 IlOP 1]

Ill S'O controlling lesel transmitter fails low SRO.ll 6

HOP C 111 S'O lesel control fails to respond manual SRO C' 7

05-03-02 Al.L Steam Generator Tube Rupture S'O 111 [0.8 severity (800gpm) ramped

[h1T]

oser 10 minutes Initiate when SRO transitions to OPOP05 CO ES01, Reactor trip response 8

05-04 04 BOP [C]

hiain Steam Safety Valve fails open when actions are taken to isolate the SRO[C]

S'O during the SG TR

• (N)ormal, (Rhactivity. (1)nstrument. (C)omponent, (hi)ajor

gpendnD Ster.ario Outline i orrn I&D-l 1

l'acility: South ~lexas Project Sienario Noa 2 on 10'21:97 Op lest No.: 2 laaminets:

Operators: $RO UI.U2 RO R2.R4 1

IlOP Ri,R3 Objectises: 1: valuate the crews response to an ATWi with a failed open Pressurizer Relief vahe.

initial Conditions: IC l 100% MOI.

Iailure of Reactor Trip l'ailure of auto turbine trip l urnover:

1 he plant has been at 100% for the last 100 days.

The crew is directed to reduce power to 85% due to grid instabilities.

thent Malf.

Event incot No.

No.

T>pe' Description IC IC-l N/A l'ull pow er steady state 01 12 01 ROlC]

Failure of auto reactor trip 110 P C l 06Oh01 SRO C Failure of auto turhine trip from SSPS N/A ROlR]

Plant power reduction due to grid instabilities SROlR]

2 li31.008_

llOP[C Ground occurs on 480V t.oadcenter and results in a loss of 1:lill E llll _2 SRO[C l'

3 01 29-10 RO; l]

Power Range Channet N-42 fails high.

IlO P i SRo l 4-N/A RO)N]

Restore plant to stable conditions following the loss of N 42 IlO P N SRO N' 5

02 25-02 MT t.oop i A Cold Leg RTO TT 410li fails high ATWS condition exists 6

02 13 02 Al.l.

. PORY fails open during ATWT actions and cannot be isolated due to the MT loss of power to PORY block vahe

• tN)onnal. (R)eactivity, (1)nstrument,- (C)omponent, (M)ajor

--'4

.,-c-.

m.-

r-:---

---em-,.-.. - - - -

..-____,..,~-m

_______-,n-.m.

- - - - -, ~ -

---.--4.-w--m..-~~~e-

=*w,.-

e.-

--e-we.,-

f; 301 Transient and Event Chectilst form ES 301 5 OPERAllNG TEST !D.

2 10/21/97 Utarade Applicants Ul/U2 Applicant Evolution Minimu:n Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Normal 1

instrument 2

R0 Component 2

Major 1

Reactivity 1

Normal 0

instrument 1

As R0 Component 1

Major 1

SRO-l Reactivity 0

Normal 1

Instrument 1

,\\s SRO Component 1

Major

-1 Ul/02 Ul/U2 Reactivity 0

j Normal 1

3 4

SRO U Instrument 1

4/5 3

Component 1

2/8 2/6 Major 1

8 6

l Ins truc tions : (li-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 0.

Author:

William Arbour Chief Examiner:

Howard Bundy

!!> M l ir 3nt.ient w1 hent ChNili f orm [5 3D15 OPEPAtltG 1[Si fR /

10/21/97 6406:t or Opor ator typ)itant s R1/k3 Applit ant Evolution Mirumum Scenario Number Type Type Number i

1 2

3 4

Rl/R3 Rl/R3 R0 BOP Roactivity 1

1 Normal 1

3 4

Ins t r urnent

?

4 3

ku Component 2

2 2/6 Moor 1

7 6

Reactivity 1

Normal 0

Instrument 1

As R0 Component 1

Malor 1

SRO-1 Reactivity 0

Normal 1

Instrument i

As SRO Component 1

Major 1

Reac tiv i t y 0

Normal 1

SRD-U ins tr umer,t 1

Component 1

Major 1

Ins tr uc tions - (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.

Auttor.

William Arbour Chief [ uminer:

Howard Bundy

15-391 Transwnt and [ vent Checklist f or m [S-301-5 OltRAll!G T[5T NO 2

10/21/97 Reactor Operator Atolicants R2/R4 Applicant

[vulution Minimum Scenario Number 1ype Type Number 1

2 3

4 R2/R4 R2/R4 BOP R0 Reactivity 1

1 Narmal 1

3 4

Instrument 2

5 RO

-3 Comtanent 2

6/8 6

Major 1

7 6

Reactivity 1

Normal 0

Instrument 1

As RO Component 1

Major 1

SRO 1 Reactivity 0

Normal 1

Instrument 1

As SRO Component 1

Major 1

Reactivity 0

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.

Author:

William Arbour r.hief Eseminer:

Howard Bundy

1 11, 391 Competencies Chet611st form iS.301-6 CRlW 3

[

Applicant Ul Applicant R1 Applicant R2 SRO.U R0 R0 Competencies SCENARIO SCfNARIO SCENARIO i

?

3 4

1 2

3 4

1 2

3 4

Understand and Interpret 2

2 2

2 2

2 Annunc1ators and A1atnis Diagnose Events 2

2 2

2 2

2 and Conditions Understand Plant 2

2 2

2 2

2 and System Response Coriply With and 2

2 2

2 2

2 Use Procedures (1)

Operate Control NA NA 2

2 2

2 Boards (2)

Consnunicate and 7

6 7

6 7

6 interact With the Crew Demonstrate Supervisory 7

6 NA NA NA NA Ability (3)

Comply With and 4

3 NA NA NA NA U',e Tech Specs. (3)

Notes:

(1) includes Technical Specification compliance for an RO.

(2) Optional for an SRO.U.

(3) Only apolicable to SR0s.

Instructions:

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

William Arbour Chief Examiner:

Hoard Bundy

iS-301 Competencim Oiecklist form (5 3014 i

CRlW 4 Applicant U2 Ap;)licant R3 Applicant R4 SRO U R0 R0 Competencies SCENARIO SCfNARIO SC[NAR10 1

2 3

4 1

2 3

4 1

2 3

4 understand and Interpret 2

2 2

2 2

2 Annunctators and Alart; 4

01agnose Events 2

2 2

2 2

2 and Conditions Understand Plant 2

2 2

2 2

2 and System Response Comply With and 2

2 2

2 2

2 i

Use Procedures (1)

Operate Control NA NA 2

2 2

2 Boards (2)

Communicate and 7

6 7

6 7

6 Interact With the Crew Demonstrate Supervisory 7

6 NA NA NA NA Ability (3)

Comply With and 4

3 NA NA NA NA Use Tech Specs. (3)

Notes:

(1) locludes Technical Specification compliance for an R0.

(2) -Optional for an SRO-U.

(3) Only applicable to SR0s.

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

Author-W1111am Arbour Chief Examiner:

Howard tiundy

CtilEUX ANLINEJLQUIL!NEERM.ENia -10.111ttlfXMJ_0B0/92 SROlNp_RQ_WRlTIEN Have plant specific priorities been considered as discussed in ES 401, para. D.1.b?

Resolution: PRA Items have been identifled by an asterisk. Plant events have been identified by ##,

i For Tier 1, the KAs have not been identified as abnntmal or emergency plant e

evolution items. One must read the title and check both sections to determine what was intended. This makes the review very tedious and is unacceptable.

Resolution: KA lterns have been identitled by an A or E as applicable.

Tier 2 is incorrectly titled Emergency and Abnormal Plant Evolutions instead of Plant Systems. Resolution: Corrected.

Although 10CFR references have nnt been given in the outline, based on question topics, it appears that sampling of 1M FR55.43(b), items 3,6, and 7, may be deficient. Resolution: Outline charme were made to better cover these items.

RO AND_SaplpMINISTRATIVf10Plc OUTLINES The subjects to be covered by JPMs should be listed in the block following topic numbers where only the topics are presently identified. Resolution: Will specify subjects.

On SRO JPM A.3, the importance rating for KA 2.3.10 should be 3.3 vice 3.2.

Resolution: Corrected.

Considering the fact that the administrative part of the exam is administered over a three day period, there aprears to be too much overlap of subject materialin these outlincs. This is particularly true for SRO applicants where the same outline is being used for all three days.. For example, how many ways can the calculation of thermal power (Topic A.1 on both outlines) or tagging out an essential cooling water pump (Topic A.2 on both outlines) be performed? By the third day, one would expect the applicants to be quite knowledgeable of these procedures, if they realized that all of administrative parts of the exam are from the same outline. This duplication of subjects raises issues on exam security and the discriminatory value of materials for applicants taking the examination later in the week, Resolution:

Outline changes will be made to ensure that the tests are discriminatory, When l

there is day to day overlap 4 subject matter for tasks consideration will be given to i

making the subsequent taas challenging sven if the subject matter wers known in

advance, i

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WAl KTHROUGH OUIMNE Rutlig foLApahganislD and 114 Per ES 301, para. D.3.a, the SRO upgrade applicant should be examined on at least five different safety function. JPMs 1 and 3 cover the same safety function (electricall. Resolution: Replaced JPM 3.

Per ES 301, para. D.3.a, one of the control room systems or evolutions must relate to an engineered safety feature. Neither of the control systems are an ESF.

Resolution: Designated one of the JPMs ESF.

ES 301, para. D.3.b states that one of the plant JPMs should require the applicant to enter the RCA None of the tasks require an RCA entry. Resolution: JPM 3 is now in the RCA.

QUll nq for U1 and IR J

Per ES 301, para. D.3.a. one of the control room systems or evolutions must relate to an engineaed safety feature. Neither of the control systems are an ESF.

Resolution: Changed JPM 1 to ESF.

ES 301, para. D.3.b states that one of the plant JPMs should require the applicant to enter the RCA. None of the tasks require an RCA entry. Resolution: JPM 4 requires an RCA entry.

It appears that JPM 2, MSIV operabmty test, may be too sirnple to discriminate at the required level. Resolution: Changed JPM 2 to alternate ;

.h to increase complexity.

Ruthne for Applicana11 and 12 For exam efficiency, one of the control room systems tasks should be designated for performance in the main control room and should be scheduled for performance with the in-plant JPMs. This task should be duplicated on the outline for 13, I4, and RO1 RO 6. Resolution: Will designate control room JPM af ter validation.

l ES 301, para. D.3 b states that one of the plant JPMs should require the applicant to enter the RCA. None of the tasks require an RCA entry. Resolution: JPM 8 requires an RCA entry.

For JPM 4, see comment for JPM 2 on outline for U1 and U2. Resolution: Same as above.

How many critical steps wi;l JPM 9 have? If it only has one or two critical steps it may not discriminate adequately. Resolutbn:It will have more than two critical steps.

2 mma

l Ouflang intApp1& ants 13, I.t and RO1-R06 m

S3e comment regarding exam efficiency for Applicants 11 and 12. Resolution: Same as above.

ES 301, para. D.3.b states that one of the plant JPMs should require the applicant to enter the RCA. None of the tasks requne an RCA entry. Resolution: JPM 8 will require na RCA entry.

To differentiate between the knowledge level required for RO and SRO applicants, O

f some of the JPM questions for 13 and 14 should be at the SRO level. Resolution:

Some questior's will be wK 'en at the SRO level.

Same comment on JPM 9 as for JPM 9 for 11 and 12. Resolution: Same as above.

SCENMLQR GENERAL Scenarios do not contain out of service equipment that is provided in the turnover.

Resolution: Will incorporate.

No spare scenario outline was submitted. Resolution: W;ll develop spare scenario.

Op Test 1 Scenario 1 to Op Test 1 No comment Scenario 2 to Op-Test 1 It is not clear how event 3 qualifies as a normal evolution since it is part of the recovery from the loss of PT 505. Resolution: Either justification will be provided to consider this a normal evolution or another normal evolution will be developed.

it is not clear which events are expected to generate 2 critical tasks. Resolution.

Willinclude on ES D 2 forms.

Event 4, loss of letdown, may be handled by the RO vice the BOP since the BOP willlikely be involved in Turbine control and the CVCS controls are right to the left of the reactor controls. However, it does not appear that this will present a malfunction coverage problem for any applicant. Resolution: Expect BOP to control letdown.

Scenario 3 to Op Test 1 The relationship between the EDG in PTL and the ECW pump trip is not clear.

Which EDG is in PTL7 Which ECW pump trips? Is the f act that an EDG is in PTL and why part of the turnover? Resolution: Will specify in detailed description.

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a. w a n or it is not clear which events are expected to generate 2 critical tasks. Resolution:

Same as above, it appears that the Power Availability surveillance coupled with a 'l0% power reduction could be very time consun.;og for little evaluative value. Resolution: Will evaluate time requirements during validation. May revise, Op Test 2 Scenario 1 to Op-Test 2 The startup of a MFW pump could be very time consuming with little evaluative value. Resolution: FWP will be running when scenario starts.

The evaluative value of event 2, rods f ail to move in auto, appears low. Resolution:

Will change.

Event 4, Pressurizer level transmitter f ailure, is a repeat malfunction from scenario 3 to Op Test 1. Resolution: Replaced malfunction.

Event 7, Steam Generator Tube Rupture S/G 18, is a repeat major transient from scenario 1 to Op Test 1. Resolution: The SGTR is a complicating event in this

instance, it is not clear that the RO's participation in the startup of a MFW pump wi:1 be sufficient to credit him with a norm:I evolution. The normal evolution in the second scenario is actually a recovery action for a previous malfunction and may be questionable as a normal evolution. Resolution: Will reevaluate using these as normal evolutions, it is not clear which events are expected to generate 2 critical tasks. Resolution:

Same as above.

Scenario 2 to Op Test 2 The activity identified as a normal evolutions is questionable since it is part of the recovery action for a power range channel f ailure. Resc'. ion: Will reevaluate using event as a normal evolution.

The f ailure of auto reactor trip is a repeat from scenario 1 to Op Test 1. Resolution:

This event will have different conditions.

Need to ensure that operator response to event 2, loss of 480 V loadcenter, is significant. These types of events may require nothing more than verification of automatic actions. Resolution: Will evaluate complexity of event during validation.

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