ML20090H290
ML20090H290 | |
Person / Time | |
---|---|
Site: | Byron |
Issue date: | 07/23/1984 |
From: | George Alexander COMMONWEALTH EDISON CO. |
To: | Harold Denton Office of Nuclear Reactor Regulation |
References | |
9011N, NUDOCS 8407260215 | |
Download: ML20090H290 (95) | |
Text
' , Commonwealth Edison j one rot Nabonal Pina. Chjcigo. Ilknois
! ) Addr:ss Riply to. Post Offics Box 767
/ Chicago. Illinois 60690 July 23, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Generating Station Operating Shift Staffing for Unit 1 NRC Docket Nos. 50-454/455 References (a): May 25, 1984 letter from D. G. Eisenhut to D. L. Farrar (b): March 19, 1984 letter from T. R. Tramm to H. R. Denton
Dear Mr. Denton:
Reference (a) requested that we provide the following information concerning the experience level of individuals assigned to shift operating positions at Byron Station and the planned use of shift advisors.
Shift Advisors Byron Station does intend to use Shift Advisors to supplement those shifts which do not meet the Hot Participation Experience requirements stated in the referenced NRC letter. Two of our Shift Foreman have completed a six week Hot Participation Experience program at Zion Station have completed this program by July, and two 31,more Shift Foreman willPresently, two of our 1984.
licensed Shift Engineers meet the Hot Participation requirements for Shift Supervisors. Two other supervisors also meet those requirements, but are presently in SRO license training. Upon completion of the July NRC Exams we expect to have a total of four people who meet the Hot Participation Experience requirements for Shift Supervisors.
Overall, then, we will have enough experienced personnel to cover 4 shifts without the need of a Shift Advisor. The two remaining shifts will have a Shift Advisor assigned.
8407260215 840723 PDRADOCK05000pgg / $
t < ?
L
Operating Shift Experience Reference (b) provided information regarding the experience level of -individuals assigned to shif t operating positions as of 3-19-84 In the last several months, we have had some personnel changes due to resignations, etc. We have therefore updated our Operating Shift Experience forms to reflect these changes, plus the additional 10 weeks of shift experience due to the fuel load date slipping to September 15, 1984, additional shift crew simulator time, and the 6 weeks of Hot Participation Experience. Attachement A contains the updated information on Operating Shift Experience.
Following is an item by item response to Enclosure 2 of the referenced NRC letter.
- 1) A resume of.each Shift Advisor is included in Attachment B.
- 2) Copies of the procedures which apply to the Shift Advisor position are provided in Attachment C.
- 3) Attachment D presents the Shift Advisor training program.
- 4) The written exam given to the Shift Advisors is enclosed in Attachment E.
- 5) Attachment F provides a description of, and notes regarding, the Shift Advisors oral exam.
- 6) The shift crew training program on Shift Advisors is in Attachment G.
- 7) Medical qualifications are in Attachment H.
- 8) Evaluation procedures (rough draft) are enclosed in Attachment I.
Please direct any further questions regarding this matter to this office. -
Very truly yours,
%ylexandercspa Greg Nuclear Licensing Administrator cc: L. N. Olshan Attachment 90llN L
r-
. - '. ;^y ATTACHMENT A OPERATING SHIFT EXPERIENCE
AWE & 8'/ ,,,,,,,,,,,,,,,,,,,,,,t.,,, ,
PuerP anIIB BYRod s
ettLITtcmuw2JWEALTR EDisod Joe Tatt.Es AnMid1STAATrot)
@.L. SATE F-is-N ,,,,,,em pouBR PUNP EEPERREIICE WOR OPERAftWG Sutr? POSITION (NOTW %) ENTER DATAs NONTIIS/MOIrfM E WB30ET1NS PACTOR WEtattIIG IIARINuge 8 ' N 3 4 S 8 7 TYPE OF ERFERIEIICE PACToft CRE0t? E 3
- 1. SAIS TTPE COIsIEmCIAL Saps 1.00 WO LIMIT g
- 3. OrWER COIWW3CIAL S30 .75 II0 Lint? M 1 SAME TYPE ColeIEnCIAL 30 1.00 NO LtMt?
- 4. OTNE3 COIGIERCIAI. 30 9.75 NO Lirtt?
- 5. MAVT (MILITARY) IIUCLFAR (110. Eles, E00W, PFWS) 4.58 36 MossTMS 5f 3 [fy (OTHER) 0.25 4 SIMULATOR 12 MOIffttS #Yg 76 (EEFEftERICE PLAftT) 5.00 (12 MONTHS) g p, oy (SIMILAR) 3.09 (9 MONTHS) y n, fyjt_s; M 7. NUCLEAR 9LAIIT EXPERIE10CE Ott SWIFT (ONII PIANT) 24 MONTitS *
(LESS TNAN 1 1/2 YEARS PRIOR TO F.L.) 0.75 (12 TNT 115)
(MCRE TNAII 1 1/2 YEARS PRIOR TO F.L.I 0.50 (12 MONTilSt r
- 9. LICE *3 SED CIASSR00It' TRAINING AND EXAM 0.50 1 MCacTHS (OWN PtANT)
- 9. PARTICIPATION AT OPEllATING PEAIIT 0.75 13 McM ?!S
- 13. OTHER IIUCLEAR FIAlf? EXPElt!ENCE 0.25 12 NONTHS fg /$ ,
- 11. CONOUCTtWB LICWISE TaktNIIBG 9.25 9 M00tTNS
- 12. DEGREE (WISTIIERSE1IG, APPLIED SCIEIICE OR E2UtvAInwT) 12 MoimiS /o7, /fL /A /A (BActIEIAltS DEGREEl (12 MONTHS) i (ASSOCIATES DEGREE) (6 McNTtIS)
TOTAL NUCt. EAR PLANT EXPERIENCE: 33 fl.A5 5Y.9 Sfo NOT PARTICIPATices EXPERIEIICE TifW
- 20% h (IIES)
STAltTUP & SNUTOGIIN (TBS /IIO)
M000TNS CII SWIFT f242, k
. ~.
IIOTE II SEE *IIISTitOCTIONS FOR USE OP leUCLEAR POWER FIAlff EXPERIE10CE FACT 0stS FOR CNBCE ONE OF TIIE FOLt4ItINGI OPERAT11BG SIIIFT POSITICIIS (OL APPLICAleTSl*
a- sintet =8 iaar= ==== 6= ===* == =ata=er th. h*= ParticiP=ttaa IIOTE 2 s IIICLUDE ALL 838tFT SUPEftVISOAS (SS)*, 838tFT SIIO'S, ItEACTOR OrtstATOIIS (RO) O emperience" rectutrements of the utility plan.
AND SNIFT TEGINICAL ADVISOIIS (STA) .
- f TN/S 'RME 15 AA3EO OAJ 75$ NAH-. ABluTY O *
- 5,,,,***
Q**y ** ** * * * * ' *" ** *** *** ** '*" *** *""
0F C E. C O. xto u A/UcLEAR fowsA sTATroAl-
- $N//7 ExkRIEyce A403ccTED TNAOMU JO'X /& Mfy
anat la-A^i-TA ' .
' l E ymm , , ,
' wrtLITTen-uwrAt rH EDI5od JEB TITlas S#lFT ENC,ldfFO (SS)(SRO O.L. BIITE f-15-Tr*4 _
,,gggg, ,qggg gg,y ggggggg, (5055 28 een CPEnnflus SetPT PostTroms aussE at aseen onTAI n0erus/ncurus a uBtouttmo Pac roe i
uttW TEWS SuuttIque -
TTPE W EXPERIENCE PACTOR CMOt? 1 2 3 4 5 6 7 8 9 10
- 1, Safe TTPE COIcenctAL See 1.09 WO LIMIT 2.ormEn m As.Sao .Ts so I. tut?
I L S4f5 TYPE COISIERCIAL 30 1.90 WO LIMt? $(,
1
- 4. OTWER COIeIEnctAL 30 0.75 150 LIMt?
I.
- 5. IIAVT (MILITART) IIUCLEAa 34 sICIrtnS (IIO, EWS, 200W, PPNS)
MTHER) 4.54 33/
S.25 I 4. SIMUEATOR
(./l.5 %.s "Y15 4 (REPSIWuCE PLAerT) * . 00 12 IIONTIIS (12 sIDHTIIS) 0.3g 0 3g DJgg Oog (S!IIt TAR) g, 3.09 (9 FIONTMS) 0,
.35 JS 25 j i YF. NUCLEAR PLRIIT EXPERIEIICE 0f8 SWIFT (ONN PIANT) 4 j ILESS TnAIO 1 1/2 TEARS PRIOR TO F.L.) 0.75 14 IIOUITWS (12 MONTHS)
%g y//E 9 26 IMORE TIBAls 1 1/2 TEARS PRIOR TO F.L.I 0.50 kpl *
(12 IIONTHS) N//2 N//a W/5L
- 9. LICCISED CtASSpo0R TRAINING AND EXAM 0.50 (OWN PLANTI 9 MONTM$
IO/5 o/S /d/5 '#/5
- 9. PARTICIPATICII AT OPERAftIIG RtJul? 0.15 12 FIONTNS s
! 10. OTHER IIUCLEAR FIAlt? EXPERIEMCE 0.25 12 FIONTNS pf/33 Y(( f 75
- 11. COIIOUCTEMB LICENSE TRAtatuG 9.25 9 80tartWS 1 4.4 1
' 12. ' DEGREE (WSilIEERING, APPLIED SCIENCE OR '
E3U1VALENTI EBACIIELOlts DEGREE) 12 MONTWS (12 MoltTIESS M
( ASSOCI ATES t'EGREE) (6 MONTHS) ,
TOTAL NUCLEAR PtANT EXPERIENCE:
f.(,5 N51.5 9.Y SY.'/
{ 20t PARTICIPAft01B EXPERIENCE TIf5 m 20% (uBS)
STARTCP & SNUTOONil (TES/IIO) fr.i l PIDIfTWS OIf SEEPT g( ff IIers 1: . ..
SEE *tIISTRUCTICIIS FOR USE OF NUCLEAR PCIIER PLAIIT EXPERIEIICE PACTORS FOR OPERAftIIG SIIIPT POSITICIIS (OL APPLICAgrFS)* CIIECE ONE OF THE M NG:
IIOTE 28 INCLuot ALL SatPT SUPERVIS0eg (SS), SetPT SAO's, IIRACT0ft OPERATORE (RO) Q a. Shift advisore enset be used to setiety the
- hot participation f#h [g$,'r *
/ C(Cois 7/.w Mucce/A esperience* requirements of the utility plan.
g b. Shift adytoors w111 probably be required, at least for same shifts.
fwell 4 T97s
/ &-
M 4 sH/FT EXPEA/EAJCE //d3ECTED TNAoJGP SEW /S, NgyQ o. De met,,g,,,,
,,,,,, plan to see shift advisore unless some unforeseen circu-r-
BAER b-25 -fY g,g,,,,,, ggy, gg,,,gggg psame sans nyfou .
e-WetLITTCOAAAAoMkEALTIJ E0130M e,s. ante f-15 -24 Joe TITsas srenM c.oMNL'foMA MlNEER (SCRE)
(nort 2)
-mem Poe oPEnAT!aG SatrP Pos!TIOms anout it unrEn oATA: nowres/nouves E attenTtuo FACTom
- usten?!aG nnatsas TTPE OF EXPERIERICE FACTOR CMSIT 3 4 3 4 7 8 9 1 2 le
- 1. SANE TrPE ColeIEnCIAL Sao 1.ee no L!nt?
- 2. orwEn CossuaCIAL SRo 75 no L!nt?
- 4. orftI2 CopetERCIAL IBO 0.75 ISO LIMIT
- 5. NAVY (MtLITARY) le 34 Mogr!#S iRO. E.S. E001,UCtz,,AR
.P es) ..s.
(orHER) . 25 4 SIMutATOR IIIEFEIIERICE PLAle?) 1.00 12 MONTRS (12 Moltt1ES) 0'US 'Es a'E6 'NE gyb6 oJy' 'i (SIMIIAA) 3.00 (9 PIDISTHS) O' o p,N.26 g . 5 JM 'M CI*. MOCLEAR Pt.AsIT EXPERIEleCE Cet SWIFT (ONIs PIAMTi (LESS TNAN 1 1/2 YEARS PRIC4 TO F.L.) 0.75 24 MOIITNS (12 McNTilst f 3-T/f M/k5 8/(, #/75 '
i IMORE THAN 1 1/2 YEARS PRIOR TO P.L.) 0.50 112 MONTftS) 4 LICE:ISED CIASSRdDDE TRAINING AND EXAM (CW's PtANTI 0.50 9 *10NTHS 10/5 #/S #/6 "/5 /0/5 '#/5 .
8 PARTICIPATICII AT OPERATING RIANT 0.75 12 MONTMS !
1 OTHER seUCLEAR FIAll? EXPERIEMCE O.25 12 MONTMS '*
LS 3M 6 M o86 '
- 1. ColeDUCT!WG LICBISE TRAIN!!OC ;
9.25 9 secuTuS
- 2. OEGIE3 (ENGtWERRING. APPLIES SCIE 1BCE OII EQUIVAIANT) 12 MOIrTNS /g g / jb g /g IRACtIEIARS DECREE) (12 MONTHS) _
( ASSOCI ATES I'ECREE) (6 MONTHS) '
TOTAL NUCLEAR PLANT EXPERIENCE:
ny gg 3gey y.(,5 37./5 3K/5 IIOT PAIITICIPATICII EXPEntEIICE TIPE e 20% (GRES)
STAIITUF & SNUTOONW (YES/ ISO)
P90 NTH 3 010 SIIIPT IeOTE 1: SEE *IseSTIIUCTIONS Post USE OF ItUCLEAR POWER FIAIIT EXPERIE10CE PACTORS FOR OPEllATIIOG SIBIPT POSITIOtss (OL APPLICANTS)* CNECE 0888 0F THE M NG:
teOTE 2: IIOCLUDE ALL SittPT SUPEmy! Song (SS), ShtPT SAO'S, IIEAC1gR OPERATORS (IBO) O a. Shift advisore must be used to setlefy the " hot participettom A3IO SN!PT TECNNICAL ADVISORS (STA). emperience* restutrements of the utility plan.
p Plt ,Y SN/77 EXEA/6/>CE' mmc 7ED 7//# 0v C N O c. on not plan to see shift advisore unlese seen unforeseem etrer,-
stance artooe.
SCW /& 0W i
. --..___~ ,
Mase mee_ avmakt ' . ' '*
'M8&NW h " u stM TngEDI$g 0.t. ean f-15-N susam seen peasy surements '.BW
' " * "T' Tsss ' $bil 5'T C'O D hA W (i d *[S( O) son essaartas Surre ses Troms anom ti_ m,,un I~ mournefnentus , ,,,,,,, ,,,,,, 4 Tres or aussatence assentras anatsum ,
eneven =, 1 a 4 s 3 a T e s to
- 1. sase Tres ComenCIAL sao f 1.ee- so usett f,f/jf ff/y- /g/gf /f/pf
.T. ormes comenC At. see .Ts. po Itute N[5'i
- 1. SAIS TTPE COISIENCIAL ROf 1.98 tIo Lint?
- 4. . OFIIt2 COIsmeCIAL 30 32 12 9.7s No LIMIT
- 5. IIAWT (MI.Lt? ART.).NUC.l2AS, ilio, II i o=., . , . II, IS ..s. )$ MONTWS M[0
. 2. 3 .s- 2
- s. Stian.AToa
!S"""Tl" '"""
12 nOnenS
- % *K, %g %s M *b Yic 'N b 75 177 Mutt.rAn et. ANT carentsmC oN Satrv tem punt:
?::: 'i' "ll"'"ll 24 w arns
.m om axs *L '
oms "Ks *L 'Ls 'L "%s 9 75 stess Tuan 1 t/2 TrAns enton To r.t.: o.75 6/,45 d75 ll's S (12 m wTress g'#"g A5gz l *
(Mens TuaII t t/2 vtans raton To r.L.: o.So y
- i. T.!C:nsco CuSsanon TsArntNo ANo ex,vl a12 Mowfissa Y/2 Y#/2 1 yA YJ 5fm o.so Wra PtANTI , xNTus
/0/5 #8/5 '#/5 #/5 30/5 '/!5 ' /5 ' /5 ! '
7 PARTICIPATIMI AT OPERAT!!IG PtAIIT o.75 12 MONTMS i
- 3. OTHE2 NUCLEAR PtAIIT EXPERIENCE 0.25 12 MONTHS Ogg fg,g 7g.f7 Y5 .25 .E 75 E M
- 1. COIIDUCT3INI LICEnst TRAtWIIBG 9.25 9 MONTIIS
- 2. DECEEE (EIIGRIIstWIIUC. APPLIED SCIENCE OR C3UIVAt.EIIT)
(SActIELopS DECREtt 12 MOIITWS (A3SOCIATES t'EGREC) (12 MONTHS) >
(6 MONTHS) b i Tof - Nuet.cAn runt emntcNC 23.15 19. 4 %2 3 7.15 24 9 3o.5 %.35 3 4.15 1oA 44.65 !
NOT PAllTICIPATICII EXPERIEIICE 7 TIE
- 204 (IIRS) h h SYY STAIITOP & SWWT90NII (TES/IBO)
MOIrTIIS CII SIIIFT 1 Ilot i, l gg 22 j
I mena = or nacs Aa so=== eune amat==C= raC== = C= ca a= ae Tim rot.uint=, , ,.
OrtaAftHG SIIEFT POSITICIIs (OL APPLICafffSl*
S. - -- - -> O a- shtr*ri** 5=. r=
t.C A,5. S.I.T _S ... . .t.T S =il==
=tisa,t,a., a== parttetratta
e g t
-1 bat.===* == .m .
jf j p opv 1 TY 0/# C6'# # J#eu A* / @ b.
shift adet r.will . cob.bly h. c.quir.4, .t 1 V V S///F7 ggEA/EA/M /3 MoE" "#* t for .o shift..
j O .. a. t ,i .IItre .or.
i .t.re. .ri .
- t. cor. .i, 34'/7. 5, 0$
aa?E wna -6'1 l puur sans RWou openneiss sense expantenes ,
wett TrtanAAAAnouarAf"TQ (pl$0A) c.L. esten R-15-N ,333 T3933 ggr f 5: AE YTNTIOd ODF DATnR/EQUlf/nE# OPERMOR.( ko) m ,,,,, ,use suremrames ' " ' "
Poe OctaAT!aG SatPT Postvtoms (sous li_ surse onTA newens/nowres E unicertus raevoa '
WEIGNT!Is0 Ouuttee
- TYPE Cr EmPEnttuCE rACTon crest ,se 1 a 3 4 5 8 7 8 ' 18
- 1. Sant TYPE CoseitaCIAI. Sao 1.ee no unt?
- 2. OrmEn COssiEnctat. Sao .25 no s. Int?
- 4. OTHER CopeEERCIAL 30 0.75 too LIttt?
i
- s. SinutATOR 4
(REFERENCE PLaseT)
(sin 1LAR 5.00 12 securseS (12 secoffstS) 0.3b5 *b 715 [ss 'b5 s.5 S J5 b5 25 0-]g "%g "h #7/6 /1 36 o.5/
3.De (s re0errnSi g,5ff. 5 0.75/
o.7M5u O[./E / /. 6 0./5/. 6 y V f. NUCLEAR PLam? EXPERitwCE Or surrt (cme PtANT tLESS TnAm 1 1/2 TEARS PRtog 70 r.L. 24 MouTus 1.45 #b/ls #NI.%6 M6 '!5J5 #6///.2s 7 7/5.25L/625 0.75 (12 MCwTitSt IMCRE THAN 1 1/2 YEARS PMIOR 'O F.L.) 0.50 (12 MostTIISI @//g ygjO tys/,
A/J. 6 N/11
- e. t.!CE aSto CtASSR00n TRArntze A so Ex.vi I
(Oma PtANT) 0.50 s nouTns fgj/6 10/ 5 10/ 5 '#/5 '0/5 /0/5 '#/5 #/5 '#/S Y 5 j
9 PARTICIPAT!048 AT OPERATING PIANT 0.75 12 MOMTNS
?
I j 13. OTHER NUCLEAR FIAffT EXPERIENCE
- 11. C00sDUCTING LICEIISE TRAINING G.25 S.25 12 MONTHS
/A/3 / /5 Ter b3 #
- N s NOWTES .
?
I 12. DECREE (ENGINEERING. APPLIED SCIEleCE OR C3UIVALENTI
! 12 P90IffMS (SACutLORS DECREE) (12 MONTMS) j t%SSOCIATES CECDIEl (6 MOMTMS1 i ToTai. wUCtEAR PtANr ExPERIEwCE:
35.s5 al Y SK 4.03 1s.3 % 32 15 35 3i.75 25 33a5 nor PARTICIPATICIO EXPERIEIBCE i
T!!E
- 20% peset/IPfit (TIES)
) CTANTUF s SNUT00 ens (YES/ iso)
MONTMS Cut SIIIFT seOTE 18 I .
SEE *188STRUCTtoleS FOR USE 'OF NUCLEAR P0tfER FIA88T EXPERIERICE FACTOfts FOR l OPERAT!l8C 58 TIFT POSITIOe8S (OL APPLICANTS
- C18ECE ONE OF TWE POLt430 TINGS seOTE 2: IteCLUDE ALL SWIFT SUPERVISOlts (SS), SNIFT SRO'S, IIEACTOR OPEftATORS (RO) O a- s'.tet t .e b. .. ei.f i AND SN!FT TEC1RetCAL ADVISORS (STA). enyerience* requirements of tne utstify plan.ene .n.e ,.r.ici ,.ti Q b.
Stilft asp.ie.re wi11probably be requires, at least for osmo shifte.
y 5///F7 Ex/ER / CAKE /5 NOJEN/3 ##N O e-
- = === riaa == === =htet **vt = r= =a1=== m. =a for.
sepr. /C, MY stance arisee. etre. -
1 i
l esame sue Ayito M esammemes estre swunsaus erthen r=
maswu Ed s.t. anus f-15-fr*f aam TETss,am rd KTKYnd r>9E9xm*lRWI9atDJT CAOtATOR (RO) smous n Poe opsametas Smary PostTtogs seees it nurse antas TYPs or aspenteuCs letttipttus IEErsese mourus/mourus a metaattas enevos FACTea cuest #1 82 13 I4 M
- 1. S4IS TTPS M AL 380 II II W #' #
1.00 30 LIMIT i
- 2. OrWER rummusMAL SAS
.?S IIO L1tet?
4 1. SAsE TTPE ColesESCIAL 30 1.96 180 LINT?
- 4. OrleER CosettactAL 90 9.75 Is0 LIMt?
- 5. leAVT tutttTART) Is
- iBo 34 MouTRS iOTE.,E . E00.UC, . LEAR P,.Sl
..s.
i . 25 I
- 4. SIMUtATOR (REFEIIENCE PLAstT)
(SIMitARI 5.99 12 MOIITRS (12 MoleTIIS)
M[g *%g g a; (,6 3.99 (9 MowTtest # o, D 7. NUCLEAR PLAlef ,,dPERIEleCE ON SWIFT CNIO PIANT) 5 25 m 5 cr.7 Mas 1
(LESS TNAse 1 1/2 YEAWS PRIO4 TO F.L.) 24 . W S Y 7 y y i 0.75 (12 T*dTitSt flg '
tw mE Tnam 1 1/2 REAPS Patoa To r.L.) o.se
! 5. L C=,sEO CtASSnooM TRArnrac .wo Exm 12 MowTnSi
- //2 +/f ,
i o.so , = TnS l
i IGC4 PLANTI
/0/5 /o/5 /0/6 '#/6 Y6
- 9. PAMICIPAT!ose AT OPERATING PLANT 0.75 12 MONTNS l t
- 10. OTMEA MUCLEAR PLANT EXPERIENCE 0.25 f 11. C0esDUCTIIeG LICENSE **AAINING 12 MouTWS 27hc 1 3 .45 7 0.2$ 9 MouTES ,
\ *
- 12. OtCRES (EleGINEER!ssC. APPLIED SCIEleCE OR C3UlvALDe?) ; ,
t3ACHELOWS DECREE) 12 M00eTNS
(*SSottATES PECREE) (12 Pe0NTNSB h t6 lONTHSD j ToTAI. stCtEA= PIANT ExPERIEwCE: !
J5.75 35.is l'/
4 If 37./5 t
i not PARTICIPA?!ON EXPE9 FENCE
?!IE
- 29% Pesamm tesES)
STARTUP s SaUTODIEW (TES/Isol 1
N00eTNS Cet SIIIFT Is0TE to SEE *1 test 90CTtoesS FOR USE Otr IsUCLEAR POIIER FIANT EXPERIENCE FACT 0a5 FOR . ..
) OPERATIRBG SIBIFT POSITICIUS (OL APPLICAserSl* CissCE Out OF TER POLt4estasG.
3ely!g 2 taCLuos ALL SetPT SurtSVISOAS (SS), SWIFT SRO*S, IIEACTOR OPERATOIIS (nel O .. mitre e,s.or. . m. is e. si.eV en. n = ,.renei,.ti Also SWIFT TROnetCAL AOW1 SORS (STA).
.mp.ti.nc.* r.getr ent. of En. utility pl.n.
M ))( MM MM W pMh b NW, 8 MM M m MW S///FT 84/cg/ENCE /s //0gEc7ED TN#WGN scer. /s, /1TrY O == === **a= ** === =ht e= **'t =*e=
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ATTACHMENT B SHIFT ADVISOR RESUMES' L _
i ...
SHIFT TECHNICAL ADVISOR RESUME
- 1. Previous Nuclear Power Plant Experience, PWR:
Facility Salem Generatino Station License Held (Month / Year)
FROM TO RO May 1977 umu - lo82 SRO - -
Other Positions Held (Non-License)(Month / Year)
FROM TO Equioment Ocerator Rapt _1979 Angnce 1976 BWR:
Facility License Held (Month / Year)
FROM TO RO --- ----
SRO Other Positions Held (Non-License)(Month / Year)
FROM TO
- 2. Simulator Name Westinghouse Location Zion. Illinois Certification (Month / Year)
Jan. 1977
- 3. Military (U.S. Navy-Nuclear)
Indicate number of months that you were qualified in the following positions:
RO --
EWS --
EOOW PPWS __
Other vn==47
- 4. -Education High School:
NO GED Graduate (Circle) (kkk)
Degree:
Major un Engineering __
un Applied Science YES Bachelors (Circle) -
YES N Associates (Circle)
- 5. Operatinq on shift exoerience Indicate number of months / weeks you have spent an shift during the following plant evolutions: 3 yrs. total
>20% power
,=_ mn=+ -r y l4 cense t,ime NO Startup (Circle) NO YES L
Shutdown (Circle) 6 vrs as no at salem I
Months on shift Total Time 8 or 9 yrs.
l-
- 6. Other related experience or education (See Attached)
Signature M Operating Engineer Review I / N_ .
l
-...-..m.,,- - . - -_...,,.c . -. ., ,, _.- ...-.,,_... -...,_ .__ ._.__-,- ,_,.. ,. --..-- -,_.._ _. .__,
- 6..Other'related experience or education
- Simulator Test Director on (Gould Simulator System)
South Texas: Project Melville, New York Arkansas Nuclear Unit 1 Unit 2 Washington Nuclear Public Power Unit 3 Ir.struction in emergency and operation procedures at simulators in Indian Point, Buchanan, New York
.Surry, Surry Virginia SNPSS,'Pittsburgh, Penny. w During the period May 1977 to May 1982 I functioned as a
' Nuclear Control Operator at Salem Generating Station Unit 1 and 2.
Approximately 3 to 3h years of this time either one or both units'at Salem were greater than 20% RTP. This time frame includes operation at 100% RTP and numerous load transients between 20 to 100% RTP.
Also, on both_ Salem 1 and 2 I participated in pre-operational
. . testing of equipment, cold hydro testing of RCS, hot functional testing, initial core loading, low power physic testing, power escalation, commercial operation, refueling and return to power.
4 While at 20% or greater power I was involved in several plant problems which include but are not limited to the following, loss of instrument bus power, loss of station air, failure of various instrumentation and control failures, loss of RCP, loss of charging' pump, loss of boric acid transfer pump, loss of r circulation water pump, loss of feedwater pump, condenser tube leaks, numerous reactor trips for various reasons, and two safety injection actuations due to technican errors.
During this same period I attended simulator training on Westinghouse simulators in Zion, Illinois and Pittsburgh, Penn.'and at Indian Polint simulator in Buchanan, New York
.and Surry simulator in Surry, Virginia.
I believe that with my knowledge and previous operating experience I may be of value to Byron as a shift advisor during the day 5 to day routine operation and abnormal conditions of operation such as those described above.
9
SHIFT TECHNICAL ADVISOR RESUME
- 1. Previous Nuclear Power Plant Experience PWR:
Facility mnrke; unin* p1,n. n,4+e , t a Florida PWR & Light License Held (Month / Year)
FROM TO RO 10 /1/R 1 ? /7 /R d SRO Other Positions Held (Non-License)(Month / Year)
FROM TO In trainina for RO 7/80 10/R1 BWR:
Facility Licanse Held (Month /Yearl FROM 10 RO SRO Other Positions Held (Non-License)(Month / Year)
FROM TO
- 2. Simulator
' Name VEPCO Simulator Location Surrv. Viroinia (Westinghcuse PWR)
Certification (Month / Year)
Start-up Certification RO 9/R1 SRO
..n -
- ,-,, .,-, ,n..- ,,--.,,m --g ,ww--ay.,_-e s, .-.,,.-__.,am-.,gm
6
- 3. Military (U.S. Navy-Nucle"r)
Indicate number of months that you were qualified in the following positions:
n EOOW 5 PPWS n Other _
- 4. Education High School: 12 NO GED Graduate (Circle) (j55)
Degree:
Major Engineering Applied Science 'lES Bachelors (Circle)
YES Associates (Circle)
- 5. Operating on shift experience o.~. shif t Indicate number of months / weeks you have spent .
during the following plant evolutions:
99-10n uke
>204 power NO Startup (Circle) ES NO Shutdown (Circle) 90 mnnes._
l Months on shift 6.
Other related experience or education 1
(See Attached) r Signature e
- II ! ^^l^"
\
l A Operating Engineer ReviaW .- .
6 Other related experience or education During the period 10/81 thru 2/84 I operated Turkey Polint Units 3 & 4 above 20% PWR approximately 95-100 wks. This95-100 wks included both base loaded operation at 100% power as well as numerous load transients between 20-100% power.
I also participated in two hot funcional testing programs and return to 100% power following STM generator replacement on both units 3 & 4. This I believe will be of value in the Shift Advisor Program. While at power 20% I have been involved with several plant problems including, but not limited to. - loss of instrument bus power, loss of feedwater regulating valve control, failure of both pressurizer spray valves in the open position, station blacko.ut, loss of instrument air, failures of various channels of primary plant, secondary plant, and nuclear instrumentati on, failure of an RHR PP, loss of RCP while operating at 100% PWR, steam generator tube leaks, condenser tube leaks, loss of secondary plant components such as FW PP, condensate PP, and heater drain pump.
I believe that with my knowledge, as a previously licensed reactor operator, I may be of value to Byron station in the Shift Advisor capacity both as to routine day to day plant operation and abnormal conditions of operation such as those enumerated above.
Also to be included under operating plant experience is the 5 months spent on shift as an unlicensed observer in the control room while in license training and while awaiting receipt of my license.
While not directly comparable to a commercial power plant my 68 months spent as a reactor operator in the US Navy was good experience for basic reactor response while at power and many lessons learned there can be directly transferrable to commercial operation (i.e. secondary plant operation, importance of procedural compliance, radiation protection training, etc.)
i .
SHIFT TECHNICAL ADVISOR RESUME
- 1. Previous Nuclear Power Plant Experience PWR:
Facility Trocan License Held (Month /7 ear)
FROM TO RO SRO 10/75 10/77 Other Positions Held (Non-License)(Month / Year)
FROM TO Unit Test Group Supervi.sor 1/81 d4a3- Callaway Startup Engineer 2/91 1/a1 Callaway Supervising Test Enc. 2/80 __
9 /n
- Satsop BWR: .
Facility Lacrosse Boilinc Water Reactor Licanse Held (Month / Year)
FRCH TO ,
RO t /sn 1/71 SRO Other Positions Held (Non-License)(Mon h/ Year)
FROM TO Unit Test croup sup_ s /vo _
9 /an WNP-2 Senine Tame Eng- o/77 A /70 WNP-2
- 2. Simulator Name Zion Location Tinn. T11innis certification (Month / Year)
- 3. Military (U.S. Navy-Nuclear)
Indicate number of months that you were qualified in the following positions:
RO EWS EOOW PPWS Other pla"*"4" operator .
- 4. Education High Schools Graduaia(Circle) (jfk) NO GED oegree Major Engineering Applied Science YES NO Bachelors (Circle)- YES NO Associates (Circle) 4
- 5. operating on shift experience
.a shift Indicate number of months / weeks you have spent during the following plant evolutions:
21 manch* (PWR-Trogan)
>204 power NO Startup (Circle) NO
_YES Shutdown (Circle) 23 months (PWR-Trogan)
Months on shift
- 6. Other related exoerience or education See Attached)
SignatureQ) 1 Alm I o,ere u n, .n,ineer evi #31
l
- 6. Other related experience or education Startup experience at WNP-2, Satsop and callaway-Listed under item 61.
During the period 10/75 thru 9/77 I was a Shift Supervisor at the Trogan Nuclear plant, I participated in the hot' functional test program, low ppower physics test and power ascention testing through 100% commercial power run. Have approximately 18-months'of experience in above 204 power level.
I believe that due to my experience from hot functional testing through 1004 power run will be of value in the shift advisors program.
I have been involved in some of the abnormal situations as listed below during my time at Trogan, loss of instrument air, loss of onsite power, drop rods, condenser tube leaks, loss of various primary and secondary plant equipment.
I-believe that with my knowledge as a previous licensed SRO l at a similar type plant in the everyday operation that I am qualified to handle normal and emergency situations and can be of value to the Byron Operating crew.
While not directly comparable to operation of a four loop Westinghouse PWR, have worked as a licensed RO at a BWR for
,approximately 3 years, also worked as a Startup Engineer on various type plants of which two years were spent at Callaway Nuclear Station which is a similar type plant. :
r r
r 4
I I
i e
U SHIFT TECHNICAL ADVISO3 RESUME
- 1. Previous Nuclear Power Plant Experience PWR:
Facility Palisades Nuclear Station License Held (Month / Year)
FROM TO RO ana 77 n,,, o,
~ ' ~~
SRO Other Positions Held (Non-License)(Month / Year)
FROM TO Aux. Operator Juna 74 ang 77 BWR:
Facility License Held (Month / Year)
FROM TO RO SRO Other Positions Held (Non-License)(Month / Year)
FROM TO
- 6. Other related experience or education I held an RO license on the Palisades Nuclear Station from Aug. 1977 to Aug. 1983. During this time period I operated the unit above 20% power for approximately 25 months. In those 25 months I experienced several load transients including reactor trips from 100% power, loss of feedwater controls, loss of condenser vacuum, loss of all AC power from 100%
power, loss of instrument air, RCP seal failures, ets. I have also participated in four refueling outages - two as a licensed opera,, tor.
Some other duties included conducting auxiliary operacor training, NGET, Operations and Maintenance Dept. CRDM Mockup training and Operations Dept. requalification training.
I have also had military training in the Navy Nuclear Power Program. As an Engine room Supervisor I gained experience in steam plant operations as well as casuaity training.
During the last two years I have worked on shift at Byron Station in the Shift Foreman capacity and performed the duties and responsibilities as described in BAP 200-A2-4. I also participated in various flushing and testing activities including integrated hot functional testing here at Byron.
I firmly believe that my knowledge and experience as a previously licensed reactor operator will benefit the Byron Station Shift Advisor Program.
- 3. Military (U.S. Navy-Nucleur)
Indicate number of months that you were qualified in the following positions:
RO EWS EOOW PPWS Other Ens - 94 mas.
- 4. Education High School:
Graduate (Circle) h NO GED Degree:
Major Engineering Applied Science
- YES Sachelors (Circle) YES NO Associates (Circle)
- 5. Operating on shift experience Indicate number of months / weeks you have spent e shift 4
during the following plant evolutions:
25 mos.
>204 power NO Startup (Circle) YES NO Shutdown (Circle) 10 mna.
Months on shift i
- 6. Other related experience or education _
(See attached) i l
l Signature (kmm F . MA u g
XA Operating Engineer Review I
7..
6 Co ATTACliMENT C PROCEDURES CONCERNING SHIFT ADVISORS
. o BAP 300-2 Revision 6 SHIFT MANNING A. STATEMENT OF APPLICABILITY The purpose of this procedure is to describe the Criteria for Shift Staffing.
B. REFERENCES
- 1. Technical Specification Figure 6.2-1
- 3. 10CFR50.54
- 5. CECO. G.S.E.P. Figure 4.2-2
- 6. S.E.R. 13.1.3
- 7. NSD Directive NSDD_A09
- 8. NUREG 0654, Table B-1 C. MAIN BODY
- 1. The Minimum Shift Manning for the Station is shown in the table below:
POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION
- l Both Unit In MODES 1 Unit In Modes 1, 2, 3, or 4 Both Units In 1, 2, 3, or 4 & 1 Unit In Modes 5 or 6 Modes 5 & 6 SE 1 1 1 SF(Licensed) 1 1 None NSO 3 3 1 EA 4 4 1 SCRE 1 1 None Rad-Chem 2 2 2 Personnel NThe Shift Manning may be one less than the minimum requirements of the above table for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shif t Manning to within the minimum requirements of the table. This provision does not permit any shift crew position to be unmanned upon shift change due to oncoming shif t personnel being late or absent.
APP OVED FOR \ -g[Q ON _Y
_1 (0032P) B. O. S. R.
BAP 300-2 Revision 6
- 2. In addition, the following experience levels are required on each shift:
POS POWER PLANT (YRS)i SRO ON-SHIFT AT OPERATING PWR TOTAL NUCLEAR LICENSE >20% POWER S/U & S/D 6 MONTHS SR 4 2 YES 6 Wks X Either 1
SF 3 2 YES 6 Wks N/A SE o_r_ SF If either the SE or SF experience levels are not met, a Shift Advisor
- is also required to be on shift.
This requirement commences at initial criticality.
- A Shift Advisor is defined as a person with one year on shift as a licensed SRO at an operating plant of the same type, p_r_ a person with an R0 license as evaluated by the Mtc on a case-by-case basis.
- 3. A site Fire Brigade of at least 5 members
- shall be maintained onsite at all times. The Fire Brigade will not include the Shift Engineer, the Station control Room Engineer, and 2 other members of the minimum shift i crew necessary for safe shutdown of the Unit or any personnel required i
for other essential functions during a fire emergency.
_N!2LE The SCRE may go into the plant to participate in
!
- shift activities. While the SCRE is out of the *
- control room, an SRO licensed supervisor must *
- relieve him. In addition, during such absence *
!
- from the control room, he must be available m
i
- within 10 minutes.
'g M
- ggg
- The Nuclear Station Operators shall not under any *
- circumstances leave the controls area for any *
- reason without obtaining a qualified relief
- App
- operator. Prior to assuming responsibility, the
- VED j
- Relief operator shall be properly briefed on the i
- plant status. The Relief operator will be
- gig M
- informed of any evolutions in progress that might *
- affect plant operation, any special instructions
- B. O. ~ '
- that are in effect, and the overall status of the *
- plant. The Nuclear Station operator will be *
- briefed by the Relief operator upon his return.
- A
- e...*********** . ******************************** ..
- Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence provided immediate action is taken to fill the required positions.
(0032p)
BAP 300-2 Revision 6
- 4. A supervisor will be on site at all times who is trained as a fire chief. l S. Shift manning assignments during periods of core alterations shall I include a licensed SRO or SRO (Limited) to directly supervise the core alterations.
- 6. Station Management and Technical Support are either present or on call l at all times. The Shift Engineer has the authority to call out all required personnel, regardless of discipline.
- 7. The Shift Technical Advisor position will be filled by a technical l graduate who has successfully completed the required STA training.
Normally, the Station Control Room Engineer who is licensed at the SRO level, a technical graduate, and has completed required STA training, will fill this position.
- 8. Commencing at criticality each shift will be manned with at least one l individual with prior commercial PWR experience for at least one year after initial criticality, including the attainment of 100 pe'r cent power.
l FORMint 0 '"a'n"o B.O.S.R.
(0032P) m
p BAP 300-22 Revision 4 CONDUCT OF OPERATIONS A. STATEMENT OF APPLICA8ILITY:
The purpose of this procedure is to provide operating personnel with specific guidance as to their expected conduct in operations. This procedure addresses additional responsibilities other than those that may be delineated in other sections of the BAP.
- 8. REFERENCES 2 e
- 2. SER 13.1.2.2 Item 1.A.1.1
- 3. 10 CFR 50.54
- 4. Dennis Galle Ltr. Re: Procedure Change Regarding Importance of Finding Root Cause of Scram Prior to Startup Dated 4-13-83.
- 5. Vice President's Instruction No. 1-0-17
- 6. ANSI N.18.7-1976
- 7. NSD Directive NSDD-A09
- 8. OPEX 83-53
- 9. Byron Ltr #83-918 C. MAIN BODY:
General Responsibilities
- 1. The responsibility of the Shift Engineer shall be to maintain a broad perspective of operational conditions affecting the safety of the plant as a matter of highest priority at all times.
- 2. The Shif t Engineer should not become involved in any single operation that distracts him when multiple operations are required in the control room. During plant transients or an emergency he should not become totally involved in any single operation to the extent he loses his overall perspective of plant evolutions.
- 3. During events that require implementation of GSEP, the Shif t Engineer is the Station Director until properly relieved.
- 4. During accident situations the Shif t Engineer is in direct charge of the control room. The Shift Foreman relieves the Station Control Room Engineer so the SCRE can perform STA functions.
- 5. The Shift Engineer has the authcrity to call out all required personnel, regardless of discipline.
APPROVED 20R N 20R VIAiii'HAN .Y L
(3509f) B. O. S. R.
BAP 300-22 Revision 4
- 6. The Shift Engineer is responsible for appraising his assigned personnel for fitness for duty after shift turnover as soon as practicable,
- 7. During the shif t, the Shift Engineer and the Shift Foreman /Shif t Advisor shall be made aware of any significant changes in plant status in a timely manner by the Station Control Room Engineer.
- 8. During the shif t, the Shif t Engineer and Shif t Foreman shall remain abreast of current plant status. In addition, the Shif t Foreman shall return to the control room two or three times per shift, where practicabic, to confer with the Station Control Room Engineer regarding plant status. Where not practicable to return to the control room, the Shif t Foreman shall periodically check with the Station Control Room Engineer for a plant status update. In no case should the Shif t foreman be required to abandon duties important to reactor operation to return to the control room, unless specifically ordered to do so by the Shift Engineer.
- 9. If any surveillance / test or other condition indicates that a system l 1s not operable as required by the Technical Specifie.ations, the Shift Engineer is to immediately begin the action required by the Technical Specifications as stated in the applicable LCOAR procedure, log the condition and notify the Operating Engineer or Assistant Superintendent.
- 10. Licensed operators on duty are responsible for achieving 'and monitoring abnormal plant shutdown and Engineered Safety features System actuation when required.
- 11. Licensed plant personnel are responsible for conducting operations within Technical Specification Safety Limits and Limiting Conditions for operations.
- 12. Operations personnel shall be attentive to the condition of the plant at all times. They must be alert to ensure that the plant is operating safely and take action to prevent any progress toward a condition that might be unsafe.
- 13. All operating personnel must believe and respond conservatively to instrument indications unless the indications are proven to be incorrect.
- 14. An operator nay place a controller in the manual mode from the automatic mode whenever, in the operator's judgement, continued automatie operation is unsafe, or whenever it may cause any unnecessary transients. This should only be done when conditions are
" stable and under control", or when it is apparent that continued operation would aggravate or worsen the plant condition.
- 15. Operations personnel have the authority to depart from approved procedures where necessary to prevent or reduce injury to personnel, including the public or damage to the facility. Any such departure is to be documented and reported to the Assistant Superintendent of operations. APPROVED
.,. 20R IN:0REEMN.Y 05o,e Q IM D D_ -_ ___ _ ____ .
z l
BAP 300-22 Revision 4
- 16. Except for training purposes, only licensed operators are permitted to manipulate controls that affect reactor power or reactivity on the Main Control Board or Remote Shutdown panel. For training purposes a licensed operator must be in attendance and concur prior to any manipulations.
- 17. All Operating personnel must be alert and remain within their immediate areas of responsibility until properly relieved and be responsible for monitoring the instrumentation and controls located within their areas. They are responsible for taking timely and proper actions to ensure safe operation of the plant.
- 18. Any plant evolution outside the control room that may affect reactor power must not be performed without the knowledge and consent of the unit operator (NS0).
- 19. Personnel shall r.ot change any setpoints or control settings, etc.
inside control panels unless authorized using BAP 400-3 or BAP 400-13 as appropriate.
- 20. In-plant operators should report the completion of assigned tasks promptly to the center desk operator.
- 21. The Operators will keep their Shift Supervisor informed of any abnormal equipment operation or major evolutions.
- 22. When replacing fuses cautior should be taken to ensure fuses are replaced like for like.
- 23. Reading of unauthorized, uncontrolleo material by operating personnel is prohibited.
- 24. The Shift Advisor will provide advice and recommendations concerning plant operations to the Shift Engineer. If the Shift Advisor does not feel that his advice has been given Adequate weight by the Shift Engineer, he may confer with the Unit / Duty Operating Engineer. If the problem has not been resolved with the Operating Engineer, ho may contact the Assistant Superintendent for Operating. If the problem still cannot be resolved, the Shift Advisor may contact the Station Superintendent. The decision of the Station Superintendent is final.
Reactor Trio
- 1. When a reactor trip occurs, the Shift Engineer will take the following action:
- a. Ensure that the plant is placed in a safe condition by directing that the necessary operations are performed in accordance with approved procedures.
- b. Notify the Station Control Room Engineer, if necessary.
- c. Determine the subsequent action to be taken and notify the Operating Assistant Superintendent or Station duty person on call and other appropriate personnel and agencies. A P P R O V E D (3509P) 201 N:0RVMfM Y B. Oe Se R
BAP 300-22 Revision 4
- d. Ensure reactor trip documentation is complete (BGP 100-A13).
- 2. The Shift Engineer is responsible for determining the circumstances, analyzing the root cause and determining that operations can proceed safely before the reactor is returned to power after a trip or an unscheduled or unexplained power reduction. Permission must be obtained from the Station Superintendent or his designee prior to startup.
Operations during Abnormal or Emergency Conditions
- 1. The Operator shall believe the instruments until the indications are proven false. When operations are not as expected, return to a known safe condition. If conditions warrant, reduce power level as required until the cause of the condition has been determined and the status of the core is known to be in a safe condition. Operators are to initiate a manual reactor trip or an Engineered Safety Features System actuation if system parameters for a reactor trip or E.S.F.
actuation exceed their actuation setpoint and automatic actuation does not occur or anytime when in their judgement it is necessary.
- 2. If circumstances arise which may require operations outside of the technical specifications, procedures, or operating orders the operator shall notify the Shift Engineer for approval, if there is sufficient time to' contact him, or the licensed Senior Reactor Operator immediately available. Always proceed in a conservative manner.
- 3. When a definite hazard exists or when there is uncertainty as to
! whether an unstable. condition exists, operators shall consider the following mandatory:
- a. The safety of personnel and equipment is a responsibility to be considered primary to system -load, efficiency or other factors.
- b. Interlocks and other safety equipment shall be properly maintained, tested at regular intervals, and kept in service at all timesM.
- c. Equipment shall not be operated in a manner to intentionally avoid the proper functioning of this protective equipment.
- d. Operation of equipment under unstable conditions shall not be continued, when analysis indicates that a trip is the propar Course,
- e. If an immediate trip is necessary the System Power Supply Office should be notified immediately.
- 4. Control Room Division of Responsibility
- a. Normal shift supervisor re%ing will usually consist of 1 Shift Engineer (SE), 1 Shift Foreman (SF) with an SRO, and 1 Station Control Room Engineer (SCRE). See BAP 300-2 for minimum manning.
APPROVED
_,_ FOR N 0BWeTHE0XLY (3509P)
~
B. O. S. R. _ __
BAP 300-22 Revision 4
- c. In the event of a casualty the first available SRO in the.
control room will direct recovery and procedure flow. Note that initially this could be the SCRE. The SCRE will be relieved as soon as possible so that he may assume the role of the Station.
- Some emergency procedures may allow for bypassing some safety functions in order to maintain the plant in a safe condition.
- d. If the SCRE is the SRO in the control room he must be relieved within 10 minutes to act as the STA.
. e. The SF will usually relieve the SCRE of line functions and take over as the SRO.
- f. The SE will have to classify and initiate GSEP as acting Station Director. In addition he could relieve the SCRE of line functions.
- g. The STA function of independent observer will be executed by monitoring of the status trees aither by computer or manually, observing the flow through the procedure, and observation of any other parameter deemed appropriate. If a non-Green path is observed in the BSTs the SCRE will notify the SRO in charge (SE, SF) of the condition. Other non-expected conditions will also be communicated to the SRO in charge.
- h. The RO will perform all immediate actions, and follow the appropriate subsequent steps of the emergency procedures, usually under direction of an SRO.
Switching Orders
- 1. The Shift Engineer shall be informed prior to any switching operation
- . requested by the Load Dispatcher. If the Load Dispatcher states that it is an emergency switching operation, prior approval is not required, but the Shif t Engineer will be notified as soon as possible.
r j 2. A Supervisor qualified in Hi Voltage Switching shall accompany the l operator when live switching operations or transfer trip testing is
- being conducted.
~3. Operations personnel will make regular observation of the 34KV and 345KV transmission lines when weather and operating conditions are favorable for icing. When icing is observed, necessary action will be taken to prevent further ice buildup on the conductors and static wires.
APPROVED 01 FORAETWh0LY B.O.S.R.
(3509P)
BAP 300-22 Revision 4 Generator Load Changes
- 1. Load Changes requested by SPSO - Load changes requested by the System Power Supply Office (SPS0) are directed to the SE or NSO. When the
-NSO receives t.he request, he will notify the SE and receive SE approval for the load change. SPS0 is notified by the NSO when the load change is completed or if the SE disapproves of the request.
- 2. Load Changes requested by Station - Normally load change requests by the station are made to SPS0 by the OE. Notification should be made as early as possible. Communication to the shift is through the daily order book.
- 3. Load Changes while on EGC - When the unit is on EGC the range of Load Changes is set by the NSO and the changes are controlled by the EGC computer.
Housekeeping
- 1. The control room will be maintained in a clean and orderly condition in the interest of safe and efficient operations. All dusting and cleaning of control consoles, instrument panels, and computer consoles will be. performed by NSO's It may at times be advisable not to clean or dust in some areas of the control room during plant power conditions because of risk of bumping or otherwise moving critical controls.
- 2. The Shift Engineer's Office shall also be maintained in a clean and orderly condition. The frequency and areas to be cleaned will be delineated by the Shift Supervisor.
Control Room Conduct
- 1. All personnel shall be alert and capable of performing their assigned duties in a professional manner at all times. Of particular note are operators who_are tied to a duty station (including control room operators); such personnel must be attentive to their panels in order to professionally execute their duties. Examples of actions and performance which will not be tolerated are:
- a. Sleeping
- b. Habitual or chronic lack of attentiveness
- c. Card playing, games, or other distractions from prescribed duties.
- d. Alcohol or drug use.
- e. So-called practical jokes which could reduce the ability of persons or equipment to perform as required.
APPROVED 4,
?oR 20%UU
-s- e. o. s. a.
)
BAP 300-22 Revision 4
- f. Any other acts which could adversely affect the ability of individuals or equipment to perform their intended safety functions.
ANYONE FAILING TO ADHERE TO THESE REQUIREiiENTS WILL BE SUBJECT TO SEVERE DISCIPLINARY ACTION, INCLUDING THE POSSIBILITY OF DISCHARGE FROM THE C0,MPANY.
- 2. The only reading material allowed will be professional, job-related literature approved by the Station Superintendent. Examples of reading material not allowed are newspapers, novels, non-professional magazines and other non-job-related material. The SCRE has the authority to ban any material, as defined above, from the control room.
- 3. No radios or television capable of receiving commercial broadcasts will be permitted in the plant except as authorized by the Station Superintendent.
ANYONE FAILING TO COMPLY WITH ABOVE MENTIONED WILL BE SUBJECT TO DISCIPLINARY MEASURES COMENSURATE WITH THE SEVERITY OF THE VIOLATION, TAKING INTO ACCOUNT THE SIGNIFICANCE OF THE INFRACTION.
DISCIPLINARY ACTION COULD INVOLVE WARNINGS, DISCIPLINARY SUSPENSION, OR DISCHARGE, ANY OF WHICH STEPS COULD BE REPEATED OR BYPASSED.
- 4. The above elements are not all inclusive. They do, however, outline specific performance requirements for certain elements of nuclear plant operations which indicate the seriousness with which the Company views such actions. Our objective is a professional atmosphere - one in which operators and their supervisors continue to l
gain in knowledge of the plant end its operations while performing normal evolutions and routines.
- 5. Access to the control room shall follow the provisions as delineated in BAP 900-10.
- 6. All personnel are to request permission from the appropriate Unit NSO l prior to entrance into the "at the controls" area. No one has special-approval for entrance into this area, however, the NRC, QA and observers have the right of access for control board walkdowns, observations of evolutions, etc. The Shift Engineer, Shift Foreman, Station Control Room Engineer, and the NSO have the authority to i restrict access to or remove personnel from the control room during routine and emergency operation.
l 7. All necessary plant-related technical / administrative control room business must be conducted at the center desk and in such a manner that neither Unit NSO attentiveness nor the professional atmosphere will be compromised.
i
- 8. No unauthorized or uncontrolled notes, pictures, graphs, prints, etc.
will be used as operator aids in the control room or in the plant.
203 T@MA P P R RWGFB _ _ _
m
BAP 300-22 Revision 4
- 9. Paragraph "k" of 10 CFR 50.54 states "An operator or senior operator licensed pursuant to part 55 of this chapter shall be present at the controls at all times during the operation of the facility." In order to comply with this paragraph, an operator will be considered to be at the reactor controls if the operator has visual contact with the unit annunciator panels. An operator is not at the controls when behind the panels or out of the control room. Therefore, before an operator can leave the controls, a licensed operator must assume control of-the unit. One reactor operator cannot assume control of both units simultaneously.
- 10. The control room should not be used as a lunchroom or meeting room except for operators and testing coordination meetings held during plant construction.
1 Shift / Evolution Briefines
- 1. Briefings shall be conducted by the Shift Engineer or his designee for' individuals involved in an evolution that is to be performed.
The detail of the briefing is dependent on the degree of complexity, routineness, logistics, or number of people involved.
- 2. The individual who is 'to perform the activity is responsible to adequately review the procedure, to fully understand what he is doing, and to be cognizant of all the limitations, precautions and requirements.
- 3. Evolutions involving many individuals, especially from two or more departnents or disciplines, may require large formal briefings or preplanning sessions. If'the evolution is complex and involves close coordination, the briefing session shall be coordinated by the operating Engineer or his designee and should include:
- a. a review of the appropriate section of the procedure by key p parties
- b. examination of each individual's specific involvement and
-responsibility l c. discussion of. expected results or performance; review of l
limitations, hold points, emergency action to be taken if contingencies arise,
- d. ensure that everyone understands the interface and communications required.
L
' Communications L
(' 1. The page system should be used to announce emergencies and unexpected events, .and to relay information regarding a change in plant status j
(e.g. - the starting of a large piece of equipment). It is not to be used for horseplay.
A P P R O V E' D 20R Y:0 E M ON_Y J3509g(_ B. O. S. R.
3AP 300-22 ,
Revision 4 !
- 2. Operator communications should be clear and concise. Complex orders or orders involving specific equipment numbers should be repeated 1 back by the operator performing the task.
I Records
- 1. Refer to BAP 300-4.
i l'
l l
(
t l APPROVED 20R N :0MMW40N Y l
( _9_
B.O.S.R.
1 (3509P)
FillAL
(_._ -- _ _ ._ _ _ _ ___
~%
t BAP 200-A2-3 Revision 3 POSITION DESCRIPTION SHIFT ENGINEER REPORTS TO: Assistant Superintendent Operating SUPERVISES: Shift Foreman, Shift Control Room Engineer, Auxiliary Services Foreman, Shift Advisor.
FUNCTIONAL RELATIONSHIPS:
Operating Engineers, Master Mechanic, Master Electrician, Master IM, Storekeeper, Tech Staff Supervisor, Security Administrator, Training Supervisor, Rad / Chem Supervisor, Maintenance Foreman, Stationmen Foreman, Division Load Dispatcher, System Power Supply Office, Fuel Handling Foremen, Radwaste Scheduler / Planner & Outage Coordinator.
BASIC FUNCTIONS:
The Shift Engineer is responsible for operating the plant in compliance with the plant's operatinq license and the plant's operating procedures.
PRIMARY RESPONSIBILITIES:
- 1. The Shift Engineer is in charge of the entire plant operation and is responsible for the plant being operated and fueled in a safe and reliable manner. He has the authority to order the plant shut down, if he deems it necessary for safety.
- 2. Supervise the Shift Foremen, Shift Advisors and Station Control Room Engineer to ensure proper performance of their assigned duties.
- 3. Ensure shift operations are conducted in a safe and professional manner and in accordance with plant procedures and operating license.
- 4. Coordinate the activities of Operations, Chemistry, Health Physics, Maintenance, Instrumentation and Control, and Security groups to accomplish the operating objectives for his shift.
- 5. Notify higher management authority as required by plant reporting and notification requirements.
- 6. Analyze the circumstances, determine the root cause, ascertain whether operations can proceed safely, and obtain approval from the Station Superintendent or his designated alternate before the reactor is returned to criticality after a trip or scram.
- 7. Analyze the circumstanc.es, determine the root cause, ascertain whether operations can proceed safely after a substantial unscheduled or unexplained power excursion.
APPROVED FOR IN OlyffW\ _Y (3506P) EB. C). EE Ft.
l
- . .. l BAP 200-A2-3 Revision 3
- 8. Supervise the on-site Operating Department functions required by the i Generating Stations Emergency Plan (GSEP), Radiation Control Standards, the Security Plan and their respective implementing procedures. l l
- 9. Act as GSEP Station Director during site emergencies and incidents in l accordance with GSEP until properly relieved.
l
- 10. Frequently inspect job sites or areas of responsibilities in the plant to ensure that appropriate and effective radiological procedures and controls are being utilized and that radiological deficiencies are identified and reported to the Rad-Chem Department. .
- 11. Authorize the removal of equipment and systems'from service for maintenance, testing, or operational activities.
- 12. Authorize the return to service of equipment and systems following maintenance, testing or operational activities.
- 13. Ensure proper implementation of the Out-of-Service and Caution Card Procedures, i
I
- 14. Act as custodian of plant keys assigned to the Operating Department. -
I
- 15. Review shift logs for accuracy and completeness. j
- 16. Ensure his shift is properly manned including timekeeping, overtime call-out and meal authorization.
- 17. Initiate deviation reports of reactor trips and abnormal activities and NRC notification of reportable occurrences as required by plant procedures.
- 18. Supervise implementation of radiological waste management program with respect to shift operations.
- 19. Ensure completion and review of all surveillance / shift routines assigned to his shift.
- 20. Authorize temporary alterations.
- 21. Monitor qualification, mental, and physical condition of the operating shift personnel.
- 22. Authorize access to the site during weekends, holidays and off-hour shifts.
- 23. Authorize temporary procedure changes within the bounds established by Station Administrative Procedures.
- 24. Ensure proper shift turnover.
APPROVED i
203 E0ggK.Y B.O.S.R
_ J3506D _
BAP 200-A2-3 Revision 3
+ 25. Ensure proper High Voltage Switchinq Operations at the station for equipment under jurisdiction of the Division Load Dispatcher.
- 26. Conduct evaluation of operator performance.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Assistant Superintendent Operating - daily.
- 2. Operating Engineers - as necessary.
- 3. Master Mechanic - resolve maintenance problems as necessary.
- 4. Master Electrician - resolve maintenance problems as necessary.
- 5. Master IM - resolve maintenance problems as necessary.
- 6. Storekeeper - maintain operating consumable products.
- 7. Tec'h Staff Supervisor - resolve long term or generic operating problems.
- 8. Rad / Chem Supervisor - maintain plant radiological and chemical specs.
- 9. . Operating Foreman - conduct plant operations.
- 10. Shift Advisor - assimilate advice, assiqn duties.
- 11. Maintenance Foreman - authorize maintenance work start.
, 12. IM Foreman - authorize maintenance work start.
- 13. Electrical Foreman - authorize maintenance work start.
- 14. Tech Staff Engineers - resolve long term or generic problems.
- 15. Rad / Chem Foreman - maintain plant radiological and chemical specs.
- 16. Stationmen Foreman - maintain plant cleanliness.
- 17. Division Load Dispatcher - operate High Voltage Equipment as necessary.
- 18. System Load Control - provide necessary generating capacity.
l l
i 19. Training Supervisor - provide necessary training to maintain shift proficiency.
- 20. Shift Operators - accomplish shift objectives.
- 71. Fuel Handling Foremen - Coordination of operators during refuel outages.
- 22. Radweste Scheduler / Planner - Implement operations in Radwaste determined by Scheduler / Planner to be necessary.
70R TO M M ;JE 58 F# Ft () \
RfD W 2h TEkf8k#LJYL
BAP 200-A2-3 Revision 3 MEASUREMENT YARDSTICKS:
' 1 '. Unit availability.
- 2. Unit Derating.
'3. - Feedback from maintenance personnel.
- 4. ' Annual Station Report.
- 5. -License Event Report.
QUALIFICATION-REQUIREMENTS:
ANSI N
18.1 REFERENCES
NSD Directive NSDD-A09.
i L
l KPPROVEO l
20R S 0Mir har_Y B. O. S. R.
L tGC9TD c:rm
BAP 200-A2-7 Revision 3 POSITION DESCRIPTION STATION CONTROL ROOM ENGINEER REPORTS TO: Shift Enqineer SUPERVISES: Nuclear Station Operators, Equipment Attendants, Equipment Operators FUNCTIONAL RELATIONSHIPS:
Shift Foreman, Shift Advisors, Maintenance Foreman, Tech Staff Engineers, Fuel Handling Foreman, Auxiliary Services Foreman BASIC FUNCTIONS:
- Assist the Shift Engineer with his duties and is responsible for all duties assigned to him by the Shift Engineer.
Provide advanced technical assistance to the operating shift complement during all operatinq conditions.
PRIMARY RESPONSIBILITIES:
- 1. Coordinates equipment operations necessary to support the objectives of the shift.
- 2. The Station Control Room Engineer has the authority to order the plant to be shut down, if he deems it necessary for safety.
- 3. Maintains indepth knowledge of plant and equipment status.
- 4. Coordinates unusual or abnormal plant operations from the Control Room.
- 5. Coordinates normal equipment operations and directs plant evolutions from the control room while directly interfacing with the Shift Foreman.
6'. ' Principally maintains direct supervisory contact with the reactor operations and evolutions controlled from the control room.
- 7. Directly verifies that proper shift manning levels are maintained in the control room.
- 8. Reviews requests for equipment Out-of-Service and coordinates necessary pre-maintenance testing and post-maintenance testing.
- 9. Verifies that system operation is in accordance with approved procedures.
- 10. Assists the Shift Engineer in initiatinq deviation reports and NRC notifications as required by plant operations.
APPROVED F0R N 20RWM OLY B.O.S.R, (3504P) .___,, _ _
BAP 200-A2-7 Revision 3
~
- 11. Assists the Shift Engineer in review of applicable temporary procedure changes.
4
- 12. Assists.the Shift Engineer in requests for maintenance of equipment and maintenance of the Work Request 109
- 13. Assists the Shift Engineer with proper implementation of the Out-of-Service, Hold, and Caution Card Procedures.
l14. Verifies that proper shift turnover occurs in the Control Room.
- 15. Conducts shift operator personnel Performance Evaluations.
- 16. Conducts applicable.on-shift operator training as necessary to maintain shift operations' proficiency.
- 17. Assures safe and professional conduct of shift operations.
- 18. Removes himself from normal operating in-line supervisory responsibility and steps back during abnormal operations to assume a role of overview with the specific responsibility of monitoring the maintenance of core cooling and containment integrity.
- 19. Ascertain, during transierits and accidents, whether the plant is responding to the incident as predicted in the Safety Analysis Report. .
- 20. Ascertain during transients that there is adequate core cooling. In the event that critical parameters become unavailable due to instrument failures, perform calculation or through other means determine the approximate values for the parameters in question.
- 21. Investigate the cause(s) of abnormal or unusual events occurring on assigned shift and assess any adverse effects therefrom. Recommend i changes to procedures or equipment as necessary to prevent recurrence.
- i. 22. Evaluate the eff6ctiveness of plant procedures in terms of terminating or L mitigating accidents and make recommendations to the Shift Engineer when l changes are needed.
l
- 23. Make a qualitative assessment of plant parameters during and following an accident in order to ascertain whether core damage has occurred.
l l 24. Assist the operations staff in interpreting and applying the requirements
- of Technical Specifications.
l l 25. Perform an early review of the planned activities for the upcominq shift to ascertain whether special considerations or precautions are warranted l and. make appropriate recommendations to the Shif t Engineer. This review should include scheduled surveillance tests and maior maintenance items.
APPROVED 20R \ 20RMAiIM9E Y
@PZI2h _ _ _______.. .. _._ SMi$1$*_ _ _ _ _ _ _ _ _ . _ _ _ _ _
BAP 200-A2-7 Revision 3 PRINCIPAL WORKING RELATIONSHIPS:
- 1. Operating Foreman - Coordinate plant evolutions.
1
- 2. Maintenance Foreman - Authorize work start.
- 3. Tech Staff Engineers - Resolve generic problems.
- 4. Rad / Chem Foreman - Maintain radiological and chemical specs.
- 5. Shift Operators - Accomplish shift objectives.
- 6. Fuel Handling Foremen - Assure safe core alterations.
-MEASUREMENT YARDSTICKS:
.1. Unit availability.
- 2. Unit derating.
- 3. Annual station reports.
- 4. Feedback from Maintenance personnel.
- 5. Feedback from Shift Engineer and Operating Foreman.
- 6. Feedback from Shif t Operators.
- 7. License Event Reports.
QUALIFICATION REQUIREMENTS:
ANSI N
18.1 REFERENCES
NSD Directive NSDD-A09 APPROVi3
(
503 M0MABS B. O. S. R.
ORY L-_ nrrv;vre
BAP 200-A2-10 Revision 0 POSITION DESCRIPTION SHIFT ADVISOR REPORTS TO: Shift Engineer SUPERVISES: Equipment Attendants, Equipment Operators FUNCTIONAL RELATIONSHIPS:
Shift Control Room Engineer, Auxiliary Service Foreman, Maintenance Foreman, I.M. Foreman, Electrical Foreman, Tech Staff Engineers, Rad Chem Foreman, Stationmen Foreman.
BASIC FUNCTIONS:
Assist the Shift Engineer with his duties and is responsible for all duties assigned to him by the Shift Engineer; provide advice and recommendations on plant operations to the Shift Engineer.
P,R,IMARY RESPONSIBILITIES:
- 1. Maintain in-depth knowledge of plant and equipment status.
- 2. Observe and/or assist in plant evolutions as directed by the Shift Engineer.
- 3. Assist in resolving Tech Spec relateo problems.
- 4. The Shift Advisor does not have the authority to order plant shutdown.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Shift Engineer - provide advice on plant evolutions.
- 2. Shift Control Room Engineer - coordinates plant evolutions.
I L 3. Auxiliary Services Foreman - coordinate primary and secondary plant
[ evolutions.
4.- Maintenance Foreman - authorize maintenance work start.
- 5. Tech Staff Engineers - resolve plant generic operating problems.
- 6. Rad Chem Foreman - maintain radiological and chemical specs.
MEASUREMENT YARDSTICKS:
- 1. Feedback from maintenance personnel.
pp
! 2. Feedback from Shift Engineer.
l
- 3. Feedback from Shift Operators. : 0'R '
F 0,R, W H e 1, l
B. O. S. R.
l L (4410P) g
r BAP 900-10 Revision 2 CONTROL ROOM hCCESS A. STATEMElff 0F APPLICABILITY:
The purpose of this procedure is to outline Control Room access during normal and emergency conditions.
B.
REFERENCES:
- 1. FSAR Appendix E, REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT.
- 2. Frank Palmer letter dated March 3, 1980, " Access to Vital Areas by QA Personnel".
C. MAIN BODY:
- 1. Unlimited access to the Control Room will be allowed to the following l personnel during normal operations. i
- a. Station Superintendent
- b. Assistant Superintendents
- c. Shift overview Superintendent
- d. Operating Engineer
- e. Technical Staff Supervisor
- f. Shift Engineer
- g. Shift Foreman
- h. Senior Resident Inspectors and/or site Resident Inspector (s).
- i. Nuclear Station Operator.
- j. shift Technical Advisor / Shift Control Room Engineer
- k. Station Quality Assurance Engineer
- 1. Station Security Administrator
- m. Equipment Operator
- n. Shift Advisor
~
- 2. Routine access to the Control Room will be allowed to personnel displaying a valid Station Security Badge, only for performance of their required duties.
- 3. Access to the Control Room for other personnel may be granted by Station Management personnel listed above for specific purposes only, during normat operation. APPROVED
_1 201 N ~0yfgg _Y (1763P) _ _ _ _ . _.. _ __ _ _ _ _ __ _ _ _ _ _ . . _. _ _ _ _ _ _ _ _ _ . _ .
BAP 900-10 Revision 2
- a. Personnel with visitor badges must be escorted by persons who have a proper security badge.
- b. The management person who grants access to the control Room for specific purposes (such as training) must notify the Shift Engineer or Shift Foreman or the SRO in the Control Room to inform him that permission has been granted to enter the control Room and the reason for the person's entry.
- c. If the individual requiring access does not have a security badge with proper clearance to allow entry into the control room notify the security shift supervisor.
- 4. In the event of an emergency, the Shift Engineer or his designated alternate shall establish himself in the control Room as directly responsible for the operation of the plant.
- a. Any recommendations toward the plant operation during an emergency shall be made through the Shift Engineer or his designated alternate.
- b. Any personnel entering the Control Room during an emergency shall first gain permission to do so from the Shift Engineer or his designated alternate, except for those personnel listed in ctep C.1 above.
- 5. Under normal or emergency conditions, the Shift Engineer or his
- designated alternate has the authority to exclude or remove non-essential personnel from the Control Room when their presence is hampering the operation of the control Room.
l
- 6. When communications are required between the Control Room and On-Site Technical Support Center or On-Site Operations Support Center, they should be established by means of the telephone or a messenger.
t APPROVED 201 UORM M OLY
- s. o. s. a.
(1763P)
..____,________M
4 #
ATTACHMENT D SHIFT ADVISOR TRAINING PROGRAM
BTP 100-19 Revision 0
'{ SHIFT ADVISOR TRAINING PROGRAM A. S,,_TATEMENT OF APPLICABILITY:
The purpose of this procedure is to outline how the Byron Station Shift Advisor Training Program is to be conducted.
B.
REFERENCES:
l
- 1. Licensed Operator Training Lesson Plans.
- 2. Shif t Advisor Certification Guide, BTP 106-T107.
- 3. Shift Advisor oral Exam Document, BTP 100-T108.
C. MAIN BODY:
- 1. The Byron Station Shift Advisor Training Program shall L9 conducted by the Byron Station Training Department.
- 2. Personnel to receive Shift Advisor training shall be identified by Byron Station Operating Department.
- 3. The Shift Advisor Training Program will consist of two phases and
( will be concluded with the certification of the trainee as a certified Shif t Advisor.
- 4. Phase I of the Shift Advisor Training Program under the direction of the Byron Station Training Department shall consist of:
- a. Classroce instruction covering:
-UK
- is 2). Reactor Coolant Pumps ii,i u 3). Pressurizer System 4).
5).
Nuclear Fuel Excore Nuclear Instrumentation SgKbenV Ol \/
1 6). Reactor Rod Control System 7). Digital Rod Position Indication 8). Reactor Make-up Control System 9). Chemical Volume and Control System 10). So. on Thermal Regeneration System 11). AC/DC Electrical Distribution 12). Main Generator .
13). Emerger.cy Diesel Generators 14). Emergency Core Cooling System 15). Containment Spray System APPROVED 16). Component Cooling Water System 17). Essential Service Water System APR 2 71984 13). Non-Essential Service Water System 19). Circulating Water System B. O. S. R*
( 20). Main Steam System (4158P)
n:.L . . . . a . ... ;
BTP 100-19 Revision 0
- ( 21). Steam Dump System
- - 22). Condensate /Feedwater Systems 23). Auxiliary Feedwater System 24). Turbine Controls and Auxiliary System '
25). MSR Control 26). Reactor Protection System 27). Engineered Safety Features Actuation System 28). Radiation Monitoring Systems 29). Fuel Handling
- 30) Gaseous Radwaste System 31). Liquid Radwasto System 32). Byron General Op. rating Procedures (BGP's) 33). Byrop Abnormal Operating Procedures (BOA's) 34). Generating Station Emergency Plan (GSEP) ~'
- 35) Rediation Standards 36). Reactor Trip Root Cause Determination f Qi li 4 6 V 1\
37). Byron Emergency Procedures (BEP's) 38). Byron Administrative Procedures (BAP's) [ T l -
39). BOS LCOAR _, i 40). Byron Technical Specification
- b. Phase I is to be conducted in two segments, the first being 20 days with a written quiz being conducted following each 5 days, as a maximum, of classroom instruction. The second segment of Phase I shall immediately follow Phase II and shall be 5 days in length and is comprised of a comprehensive written final exam
( j. and an oral exam.
1). The oral exam shall be comprised of two training department personnel, one operating department personnel, and one i
trainee. The minimum length of the exam is two hours and requires all examiners to agree on trainee passing the SHIFT ADVISOR ORAL EXAM.
2). The Shift Advisor Oral Exam Document BTP 100-T108 shall be used to document the trainee's oral exam. BTP 100-T108 is comprised of three sections, a).Section I - is used to document the topics covered during the oral exas. Each topic must be identified as being discussed satisfactorily / unsatisfactorily in the S/U column provided.
b).Section II - is the " Comments" section for the examiners to note any strengths / weaknesses of the trainee. ,
c).Section III - will be used to indicate the results of the oral exam and also provide a location for the signatures of the examiners. The Training Supervisor's signature is required for final approval.
-( KPPROVED APR 2 71924 B. O. 2 :'.
(4158P)
. . . :: a .. :. .:... . . . :.. . ... -- . . . ... .;
BTP 100-19 Revision 0
(' 5. Phase II of the Shift Advisor Training Program under the direction of
' Byron Station Operating Department shall immediately follow the first segment of Phase I. Phase II shall be 10 days in length with the 1
(
trainee being assigned to a shift or shifts as appropriate to complete the Shift Advisor Certification Guide BTP 100-T107.
- 6. Upon successful completion of Phases I and II the trainee shall be recognized by the facility as a certified Shift Advisor.
- a. Successful completion of Phase I is determined by the trainee having:
1). Achieved an overall examination score average of 80% or higher with no one examination score less than 70%.
4 2). Passed Oral Exam.
- b. Successful completion of Phase II is to be determined by both the completion of the Shift Advisor Certification Guide BTP ,
100-T107 and the submission of this guide to the Byron Training l Department.
- 7. Classroom instruction shall be documented using course code Y-SATP, file number 1.6.1001 and keyword SHIFT ADV. WK XX-X. !
- 8. The Shift Advisor comprehensive written final exam shall be l documented using course code Y-SATP, file number 1.6.1001, and
}(
4 keyword SHIFT ADV. FINAL XX-X.
- 9. The Shift Advisor oral exam shall be documented using course code Y-SATP, file number 1.6.1001, and keyword SHIFT ADV. ORAL XX-X. The Shift Advisor Oral Exam Document is also required for proper documentation.
- 10. The completion of Phase II, Shift Advisor Certification Guide, shall be documented using course code Y-SATP, file number 1.6.1001, and keyword SHIFT ADV. CT GD XX-X.
- 11. A certificate of completion shall be issued to each trainee upon certification for successful ebepletion of " Shift Advisor Training Program." This shall be documented using course code Y-SATP, file number 1.6.1001, and keyword SHIFT ADV. CERT XX-X.
4 a XX-X - represents the last two digits of the calendar year followed by the sequential number of the F class llin tOyRear,. ,# 0, OLY ,
( APPROVED APR 2 71984 B. O. S. R. I (4158P) g% int ,
i
. .-.;.....~:.....-. . . . . - . .-
BTP 100-T107 Revision O
( SHIFT ADVISOR CERTIFICATION GUIDE I. Outline of Shift Advisor Certification Guide A. The Shift Advisor Certification Guide is to be utilized by the student to gain practical experience training as a supplement to the in-classroom portion of the program.
- 1. The certification guide is a document listing specific evolutions which the student is to perform, simulate, or observe under the supervision of the Shift Engineer or his designates.
- 2. For each of the specific evolutions listed there is a signature /date blank provided for the Shif t Foreman or SCRE to (
fill in, verifying satisfactory completion by the student. l
- 3. Upon completion of all the evolutions, the Shift Engineer is to review a random sample of the listed evolutions. This review sr/ves as a spot check of the student's retention and affords a specific time frame in which key safety points or procedures relative to the evolutions may be emphasized. There is a signature /date blank provided for the Shift Engineer as well as a comments section in which any items regarding the students knowledge level or performance may be made.
- 8. In all cases each student shall have completed the Shift Advisor Certification Guide and submitted it to the Training Department prior to being certified as Shift Advisor.
FOR IN 0 l
0LY L
l.
9 t ,
APPROVED k APR 2 71984 Page 1 of 14 B. O. S. R.
(4159P,,)
BTP 100-T107 Revision 0
( SHIFT ADVISOR CERTIFICATION CHECK 0FF AUXILIARY FEEDWATER (AF)
Signature /Date
- 1. Explain the function of the Auxiliary Feedwater System and its design features.
SF/SCRE
- 2. Walk through the flowpaths of Auxiliary Feedwater System, both normal and emer-gency, along with expected flow raies.
Draw a one line diagram of the Auxiliary .
Feedwater System.
SF/SCRE
- 3. Discuss system interconnections and support systems; both mechanical and electrical. , ,,... -
SF/SCRE
. $ 1
- 4. Walk through the locationa the components of the Auxiliary F I
!(
h System. W SF/SCRE
- 5. Discuss Auxiliary Feedwater System's b
normal operations and abnormal opera-p tions.
! SF/SCRE
- 6. Discuss the Safety System Actuatina l? Signals.
+ SF/SCRE System Knowledge Satisfactory SE 1
? Date a
. Comments:
APPROVED L.
? k. APR 271984 Page 2 of 14 (4159P) l . _ _ . - _ . _ _ _ _ _ _ _ _
-. a.. . . ... .~ ... . ..- ......:....~.. . . .
Signature /Date
- 1. Explain the purpose of the system.
SF/SCRE
- 2. Discuss the following major components in the plant;
- a. Surge tanks SF/SCRE
- b. Component cooling pumps SF/SCRE
- c. Component cooling heat exchangers SF/SCRE System Knowledge Satisfactory SE Date Comments:
FOR INFO n/y.s.v 6_
3 i
APPROVED APR 271984
> ( B.O.S.R.
! Page 3 of 14 f (4159P) r
- . . . _ _ _ _ _ . _ _ _ _ . _ . . _ . _ . . .- _ _ . _ . . . . . , _ _ . . ~ . _ . _ . _ _ . . _ . _ _ _ . _ _ . _ - . . . . _ _ .._ _. ..___._
. e. .. . ..2 ..'_..s. _r .. - _ ..
BTP 100-T107 Revision 0
- SHIFT ADVISOR CERTIFICATION CHECK 0FF CONTAINMENT SPRAY (CS)
Signature /Date
- 1. Explain the function of Containment SF/SCRE
- 2. Walk through Containment Spray flow path and identify chemical addition and what the chemicals do.
SF/SCRE
- 3. Explain auto and manual operation.
SF/SCRE
- 4. lxplain the method of Containment l Spray sump water removal to Red Waste.
' SF/SCRE
- 5. Explain why the Containee I L II
,( is a part ESF and what ac t. I SF/SCRE N._.y i-System Knowledge Satisfactory SE l Date Coments: .
APPROVED
(
APR 2 71984 (4159P)
-_. ~ . . _ . _ _ - . . _ - - _ . . _ _ _ . _ . . . - _ _ , _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___
BTP 100-T107 Revision 0 1 SHIFT ADVISOR CERTIFICATION CHECK 0FF CHEMICAL AND VOLUME CONTROL SYSTEM (CV)
Signature /Date
- 1. Explain the functions of the CVCS.
SF/SCRE
- 2. Walk down available flowpaths of the CVCS.
SF/SCRE
- 3. Discuss operation, control and interlocks associated with the CVCS, SF/SCRE
- 4. Discuss chemistry control of the Reactor Coolant System.
SF/SCRE
- 5. n;
\
Discussthefunctionsf
.and charging.
SF/SCRE
- 6. Discuss the significance of'the
- C. centrifugal charging pumps.
SF/SCRE
- 7. Discuss the purpose of emergency boration and locate the manual emergency borate valve.
SF/SCRE
- 8. Discuss normal parameters of the CVCS.
SF/SCRE
- 9. Discuss the use of regenerative and non-regenerative heat exchangers.
SF/SCRE
- 10. Discuss " Flow Balance" as it pertains to the CVCS.
SF/SCRE
- 11. Discuss the purpose of the excess letdown.
SF/SCRE
- 12. Discuss the major components of the CVCS.
SF/SCRE l( APPROVED APR 2 71984
, , , ,, 1, (4159E) B. O. S. R.
- , ,. . . ~ - - - - - - - - * - - - ~ ~ ' - ' -
. . .. .a 2 . .:. . . .
l l
BTP 100-T107 '
Revision 0 Signature /Date
- 13. Discuss seal injection flow (start-up j and normal). 1 SF/SCRE I
- 14. Discuss the functions of the letdown l orifices, p
System Knowledge Satisfactory SE Date Comments:
FOR Info ONLY l
APPROVED l(. APR 2 71984 .
i B. O. S. R.
l Page 6 of 14 (4159P)
....<>....=...:..... .
^ ^
~.. ^
- - ~ ^ ^ '
- ^ ^ ..
BTP 100-T107 Revisicn 0
- SHIFT ADVISOR CERTIFICATION CHECK 0FF DIESEL GENERATOR (DG) l Signature /Date
- 1. Explain the function of (DG), loads supplied and under what conditions it is used.
SF/SCRE
- 2. Walk through the flowpath of the diesel j fuel oil systems. Know location of major )
valving and piping. :
SF/SCRE j
- 3. When the alarm sounds in (DG) Room, why should you evacuate the area immediately?
SF/SCRE System Knowledge Satisfactory SE Date Comments: s-'
VO d l
[
APPROVED APR 2 71984 Page 7 of 14 B. O. S. R.
.. .,.w.---- ---....~..
, . -BTP 100-T107 Revision O SHIFT ADVISOR CERTIFICATION CHECK 0FF MAIN FEEDWATER SYSTEM (FW)
Signature /Date
- 1. Walk through the flowpath of the Main Feedwater System.
SF/SCRE
- 2. Discuss when the Turbine Driven Feed Pumps are placed on the turning gear and its interlocks.
SF/SCRE
- a. Discuss how to manually engage the turning gear.
- b. Discuss why the Turbine is placed on the turning gea,r after stopping -
the feed pump.
- SF/SCRE
- 3. Basically describe the flow path of EH .
fluid from the EH pumps to the stop ik' C valves and governor valves, loc
'r\
\ '
the HP accumulators and interf .
- 4. Describe the steam flow into the F6edwater Turbines at various power levels.
SF/SCRE System Knowledge Satisfactory SE Date Comments:
( APPROVED ,
APR 2 71984 (4159P) B. O. S. R. l
........a....., . - . . - . - - -
BTP 100-T107 Revision O SHIFT ADVISOR CERTIFICATION CHECK 0FF MAIN STEAM SYSTEM (MS)
Signature /Date
- 1. Explain the function of the Main Steam System.
SF/SCRE
- 2. Explain the functions of the Steam Dump Control System.
- 3. Walk through the flow path of the Main Steam System to the Main Turbine. Know locations of all major components.
SF/SCRE
- 4. Explain the basic construction of the Steam Generator and how steam is produced.
SF/SCRE
- 5. Explain shrink and swell of the
( Steam Generator during a Turbine load increase and decrease. On 1%.
0 SF/SCRE
- 6. Explain the operation of the Steam Oh Dump Control System in the TAVG and U STEAM PRESSURE modes and know the locations of the controls on the Main Control Board.
SF/SCRE
- 7. Explain the operation of the cooldown mode of operation with only three steam dump valves armed.
SF/SCRE
- 8. Explain the Steam Generate,r Water Level Control System and where its parameter can be read on the Main Control Board. '
SF/SCRE
- 9. Explain the Reactor trips (and their significance) associated with the Steam Generator. Also, explain main steam inputs for safeguards actuations.
SF/SCRE
( KPPRoVED Page 9 of 14 APR 2 71984 (4159P) ~
B. O. S. R.
BTP 100-T107 Revision O
(- Signature /Date
}. 10. Explain the importance of the Main Steam safety valves, atmospheric reliefs and Main Steam isolation
- valves and the safety valve setpoints.
SF/SCRE
- 11. Explain the chemistry control of the Main Steam System, the safety precautions involved and locations of the components involved.
SF/SCRE
- 12. Explain the function and location of the steam traps in the Main Steam System.
SF/SCRE System Knowledge Satisfac) -- SE h oate Comments: ONLN Ik APPROVED
- ( ,
APR 271984 Page 10 of 14 . ., 3 (4159P)
. . . . . . - . . . . . . . . . . . . . - ~ . . - . . . . . .
e e BTP 100-T107 Revision O SHIFT ADVISOR CERTIFICATION CHECK 0FF REACTOR COOLANT SYSTEM (RC)
Signature /Date
- 1. Explain the functions of the Reactor Coolant System.
SF/SCRE
- 2. Walk through tha flowpath of the Reactor Coolant System for any of ,
the loops.
SF/SCRE
- 3. Explain the penetrations into the Reactor Coolant loops and their functions.
SF/SCRE Explain the baisc construction d
-4.
Reactor Coolant loops and thei
]
lI If l
functions.
SF/SCRE
!(
- 5. Explain the chemistry control in the primary plant, the safety precautions involved and locations of the components involved to add chemicals.
SF/SCRE l 6. Explain the functions of the Pressurizer System.
SF/SCRE
- 7. Walk through the flow paths into and out of the pressurizer and the significance of the following:
- a. Spray valves
- b. Spray bypass valves
- c. Power operated relief valve
- d. Safety valve
- e. Pressurizer relief tank operation SF/SCRE .
System Knowledge Satisfactory SE Date d Comments:
Page 11 of 14 I B.O.S.R.
' BTP 100-T107 Rsvis.ien O
( SHIFT ADVISOR CERTIFICATION CHECKOFF RESIDUAL HEAT REMOVAL (RH)
Signature /Date
- 1. What is the purpose of the Residual Heat Removal System, ooth normal and emergency.
SF/SCRE
- 2. What are the sources of suction for the RHR Pumps? ,
SF/SCRE
- 3. What are the different flow paths for the RHR System?
SF/SCRE
- 4. Where are the major components located?
SF/SCRE
- 5. What systems does the RHR System interconnect to and why? q 4
1{1 Ill SF/SCRE
( 6. What are the power supplies to t RHR Pumps? .*-
SF/SCRE
- 7. Where are the local indications for system flow and temperature.
SF/SCRE ,
System Knowledge Satisfactory SE one.
Comments:
APPROVED
( !
. APR 271984 Page 12 of 14 B. O. S. ri (4159P_)
.- . BTP 100-T107 Rsvision O
{ SHIFT ADVISOR CERTIFICATION CHECXOFF SAFETY INJECTION SYSTEM (SI)
Signature /Date
- 1. Explain the purpose of the Safety Injection System.
SF/SCRE
- 2. Discuss and locate the following major system components:
SF/SCRE
- a. RWST SF/SCRE
- b. Centrifugal charging pumps SF/SCRE
- c. Safety injection pumps SF/SCRE
- d. Accumulators SF/SCRE
- e. Containment recirculati i SF/SCRE l' Discuss the flow paths associated dh l 3. i -
l the injection and recirculation.
- 4. Name tne sources of borated water and what are their boron concentrations.
SF/SCRE i 5. Why is boric acid used?
SF/SCRE System Knowledge Satisfactory SE
[
Date Comments: .
l l
KPPRoVED I( APR 2 71984
- s. o. s. a.
Page 13 of 14 l (4159P)
, .. -- - . - - - _ _ , _ - , . . _ _ , , . _ _ . - _ _ _ _ _ . ~ . . ..----.- - _ _ _- - -_ _ ... _
,....e......-+ . . . :. . . . . .n ... . . . . . .
BTP 100-T107 Revision O SHIFT ADVISOR CERTIFICATION CHECXOFF
- '(
ESSENTIAL SERVICE WATER 'YSTEM (SX)
Signature /Date
- 1. Explain the purpose of the Essential Service Water System and name loads the System feeds.
SF/SCRE
- 2. Name sources of normal, emergency, and backup makeup water to the Essential Service Water cooling towers.
. SF/SCRE
- 3. Explain local control of the Essential Service Water cooling tower fans and the interlocks with their respective riser valves.
SF/SCRE System Knowledge Satisfactory SE
(
oat.
Comments:
l t
FOR 6 oW L
l l
l l
l l
l l
APPROVED k APR 2 71984 i B.O.S.R l
Page 14 of 14 l (4159P,,)
> FINE l.
7_-
o
- ATTACHMENT E SHIFT ADVISOR WRITTEN EXAM E-.
Fi '. . . ,
BYRON STATION
-OPERATIONS TRAINING EXAM GROUP Shift Advisor MODULE WEEK FINAL
. NAME
.DATE 6/26/84 TOTAL POINTS 15.7 TOTAL MISSED FINAL SCORE
'O
?
INSTRUCTIONS TO TRAINEE
- 1. Answer " multiple choice" questions by circling the most correct answer.
- 2. Answer " Fill in the Blank" and " Matching" questions on the space provided on the exas sheet.
- 3. Answer "Short Answer" ar.J " List" questions on a separate sheet of paper.
One answer per page, sad write on one side of the paper only.
- 4. Use BLACT. INK for taking exam.
- 5. You must do your own work, and without the aid of any texts or notes.
Time Limit: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
- 6. I have done my own work without the assistance of text book or notes. .
Signature
' ?..
l
- 1. Sta.te the Reactor Coolant System Pressure Safety Limit, (0.75) include LCO and Action statement (s).
- 2. State the Pressurizer Pressure / Temperature Limitations (0.6) as specified in Tech Specs.
- 3. Complete the following table with respect to Ex-core N.I. (0.75)
SOURCE RANGE INTERMEDIATE RANGE POWER RANGE Type Detectors Total No. Detectors Level Meter Scale Compensation Method Level Trips
- 4. How would rod motion be affected for an " Urgent Failure" (0.3)
Alarm in the:
- a. Logic Cabinet
- b. Power Cabinet
- 5. Label all the attached Unit 1 drawing. Identify all (0.95) transformers, buses, breakers, and power sources.
- 6. On the output of the Main Generator two potential transformers (0.5) exist per phase. Explain the affect on Main Generator power operatien if:
- a. 1 Regulating PT is,inadvertantly racked out. (0.25)
- b. 1 Metering PT is inadvertantly racked out. (0.25)
- 7. What automatic actions occur when the E.O. inadvertantly (0.5) racks out Bus 142 P.T., when the SAT is supplying the bus?
- 8. Describe the difference on the Main Feedwater System on (0.5) a Safety Injection and a Reactor Trip with Low Tave.
- 9. a. How is minimum flow to the S/G's ensured during an (0.3)
Aux. Feed Line Break, and what is this flow (gpm)?
- b. List the signals that automatically start the Aux. (0.6)
Feed pumps.
- 10. a. State the Tech Spec requirement for Boron concen- (0.3) tration during refueling.
- b. What operator action is required if one of these (0.1) limits is not met.
- 12. Give 4 indications in the control room if all three (0.4) orifice isolation valves for the letdown system were inadvertantly open. Consider only CVCS indications.
(Assume no operator actions.)
- 13. What signal (s) causes the CC surge tank vent valves to (0.3) auto close, and where is/are the signal (s) generated?
- 14. a. What are the " arming" signals for the steam dumps? (0.4)
- b. Explain how steam dump operation would be affected (0.2) if all Circ Water pumps tripped.
- 15. List all signals which will initiate a safety injection, (1.0) including setpoints and coincidence.
- 16. Other than Radiation Monitors. List four symptoms (1.0) of excessive primary plant leakage, per BOA PRI-1.
- 17. What conditions require initiation of BOA-ENV 1, (0.5)
Operation During Tornado or Sustained Wind conditions?
- 18. BGP precautions state that all but one charging pump (0.5) must be placed OOS when RCS temperature is less than 350*F. Explain why?
- 19. The RCP seal leakoff valves must not be opened unless the (1.0)
RCS is at least 100 psig. Why does this precaution exist, and what undesirable effects could this result in?
- 20. List the 18 immediate actions for BEP-0. (0.9)
- 21. During recovery from a Steam Generator Tube Rupture in (1.5)
BEP-3, the operator is instructed to isolate AF flow to the ruptured S/G once it's level is in the narrow range.
Why must AF flow be maintained to the ruptured, S/G until the U-tubes are covered.
- 22. a. Define weekly whole body dose, and what is the ad- (0.5) ministrative limit at Byron Station?
- b. Define daily whole body dose, and what is the ad- (0.5) ministrative limit at Byron Station?
- 23. Per BAP 300-18, Removing and Returning Equipment (0.5)
Out of Service, where may the master out-of-service cards be placed?
G
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- 1. The Reactor Coolant System pressure shall not exceed (0.2) 2735 psig.
- a. Modes 1 and 2 - whenever the RCS pressure has exceeded 2735 psig, be in Hot Standby with the RCS pressure within its limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and comply with the requirements of Spec. 6.5.1 (0.3)
- b. Modes 3, 4 and 5 - whenever the RCS pressure has exceeded 2735 psig, reduce the RCS pressure to within its limits within 5 minutes, and comply with Spec. 6.5.1. (0.25)
- 2. The pressurizer temperature shall be limited to: l
- a. A maximum Heatup of 100*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, (0.2) l
- b. A maximum Cooldown of 200*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, and (0.2) ,
- c. A maximum spray water temperature differential of 320*F (0.2)
I,
- 3. SOURCE RANGE INTERMEDIATE RANGE POWER RANGE Type Detectors BFt CIC UIC Total No. Detectors 2 2 8 Level Meter Scale 100_106 cps 10-31-10-3 amps 0-120% pwr Compensation Method discrimination reverse current NONE 25% power Level trips 105 cps amps @25% pwr 109% power
- 4. a. All rod motion would be inhibited except for an " Urgent Failure" in the shutdown banks C, D, and E which would inhibit motion on Shutdown Banks C, D, and E. (0.2)
- b. All rods in the affected Power Cabinet rod motion (0.1) would be inhibited.
- 5. All labeling, see attached drawing. (.025 ea)
I
- 6. a. If the Regulating PT is opened the feedback signal to (0.2) the voltage regulator will be lost and voltage control
- will be switched to manual.
- b. If the Metering PT is opened on one phase the relays (0.3) which are supplied the metering PT will sense a generator fault due to a loss of phase and trip the generator.
- 7. 1) D/G starts (0.2)
- 2) SAT feeder break opens (0.1)
- 3) Load Strip (0.1)
- 4) D/G closes on to Bus (0.1)
- 5) Loads do not sequence due to UV condition (0.1) still existing.
- 8. On a Safety Injection the Main Feed pumps are tripped (0.5) automatically along with a Feedwater Isolation. A Reactor Trip with Low Tave the Main Feed pumps are not tripped (go on recirc) but a Feedwater Isolation also occurs.
- 9. a. Flow restricting orifices are in the Aux. Feed lines (0.1) which prevents a total loss of aux. feed.160 gpm.
- b. 1. Safety Injection (0.1)
- 3. Lo-Lo S/G level 2/4 Instruments 1/4 S/G's (0.2)
- 10. a. 2000 ppm boron or a Keft < .95 whichever is more restrictive (0.3)
- b. Emergency Borate (0.1)
- 11. 1) FWOO9's (FW Isolation Valve)
- 2) FWO34's .
.3) .FWO35's -----------CLOSE (0.05 each)
- 4) Feed Reg Valve
- 5) Bypass Feed Reg Valves
- 6) FWO39's
- 7) FWO43's i
r
- 12. 1) Letdown flowrate increased (0.1 each)
- 2) Charging flow increased (to maintain Pzr Level)
- 3) VCT Level increases
- 4) LCV ll2A would open to HUT's
- 5) Higher temperature in letdown line would cause TCV 130 to go full open, and TCV129 would divert around the Mixed Bed Demineralizers.
- 6) PCV131 would open to maintain proper back pressure
- 7) Charging Return Temp (downstream of Regen HX) would increase.
Only 4 required for full credit.
- 13. A high radiation signal from a radiation monitor in one (0.3) of the outlet headers of the CC HX's will automatically close both CC surge tank vent valves.
- 14. a. 1. C-7, Load Rejection, or (0.1)
- 2. C-8, Turbine Trip, or (0.1)
(0.1) 1
- 3. Steam Dumps in Steam Pressure Mode, and
- 4. C-9, Condenser Available (0.1)
- b. With all cire water pumps tripped C-9 will not be satisfied and steam dump operation is inhibited. (0.2)
- 15. 1) Manual (0.15), 1/2 switches (0.1)
- 2) Pzr Low Pressure (0.1), 2/4(0.075), 1830 psig (0.075)
- 3) Low Steamline Pressure (0.1), 2/3(0.075), 640 psig (0.075)
- 4) Containment High I (0.1), 2/3 (0.075), 5 psig (0.075)
- 16. 1) Increase sump / cavity pump run times
- 2) Abnormal PRT conditions
- 3) Reactor Vessel flange leakoff high temperature
- 4) Abnormal CNMT parameters ,
- 5) Increased Charging Flow during Normal Operation
- 6) Increased VCT makeup frequency only 4 required (0.25 pts each) i
F .
- 17. 1) Suotcined wind sp;cd of grantor than 60 mph, or (0.25)
- 2) Tornado Warning in effect. (0.25)
- 18. This provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.- (0.5) 19 . . -To prevent blowing stagnant unfiltered water into (0.5) the RCP seal area.
-This could result in seal damage when the RCP is (0.5) started.
- 20. 1) Verify Reactor Trip (0.05 each)
- 2) Verify Turbine Trip
- 3) Verify ESF Buses Energized
- 4) Check if SI is actuated
- 5) Verify FW Isolation
- 6) Verify Phase A and CNMT Vent. Isolation
~7 ) Verify AF Pumps Running
- 8) Verify AF Valve Alignment
- 9) Verify ECCS Fumps Running
- 10) Verify ECCS Valve Alignment
- 11) Verify CC Pumps Running
- 12) Verify SX Pumps Running
- 13) Verify Diesel Generator Running
- 14) Verify RCFC's Running
- 15) Verify ECCS flow
- 16) Verify AF Flow
- 17) Verify RCS Heat Removal s
- 18) Check CNMT Pressure
- 21. -If the tubes are exposed to the steam space in the (0.5)
S/G, it will condense the steam.
. -This will result in a decrease in S/G pressure. (0.5)
-The resulting effect is that break flow into (0.5) ,
the S/G will increase.
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- 22. a. That whole body does squivnisnt recaivsd during the (0.5) seven day period commencing at 0001 Monday and terminating at 2400 Sunday. 300mR
- b. That whole body dose equivalent received in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (0.5) period commencing with the start of the workers shift.
50mR
- 23. -an OOS peg board (0.25)
--on file with the master equipment outage form (0.25)
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ATTACIIMENT F SilIFT ADVISOR ORAL EXAM t
9
f A F , .i O V E O BTP ico-T108 Revision 0 APR 2 71984
( B. O. S. R. SHIFT ADVISCR ORAL EXAM DOCUMENT NAME3ger Anderson COMPANY PLD DATE GIVEN 6/28/84 I. TOPICS COVERED TOPICS
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F BTP 100-T108 Revision O II. CCmENTS:
III. ORAL EXAM RESULTS Roger Anderson A. An oral exam was conducted on trainee _
f The recommendation (s) of the examiners are
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Approved - , -
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Tral Supervisor APPROVED APR 2 7!994 2
l B. O. S. R.
A P < .- O V E D BTP too-Tios APR 271984 I B. O. S. R. SHIFT ADVISOR ORAL EXAM DOCUMENT NAMg Jim Hassinger COMPANY LOC DATE GIVEN 6/28/84 I. TOPICS COVERED TOPICS
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BTP 100-T108 Revision 0 f- II. ComENTS:
III. ORAL EXAM RESULTS Jim Hassinger
( A. An oral exam was conducted on trainee of the examiners are The 9A6. recommendation Am'm - .e /~4 (s) / 4A dhar n . .e 4 ff. 4 v #. _ A4.s n e ,// h~/e/,e A~Z / 11 e, s
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- 8. Examiners signatures
'd TrattlingWpartment (1)
( C _ _ _ _ _
Trai ing Q pa tment (2)
! ,M -
rating Department Approve _ Mo -
'T ~ng Supervisor APPROVED APR 2 7 '984 B. O. S. R.
(t155P) .
( , .. . - . ..
l APrnOVED BTP 100-T108 Revision O APR 271984 SHIFT ADVISOR B. O. S. R. ORAL EXAM DOCUMENT l
NAME Nick Malato COMPANY H. DATE GIVEN 6/29/84 1
I I. TOPICS COVERED i
TOPICS S U
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- BTP 100-T108 Revisicn 0 II. ComENTS:
i III. ORAL EXM RESULTS An oral exam was conducted on trainee @ph +4@l 4 t4 f A. _
ij 4 wmedAC 56Vris alf i}L M,H-L.
of the examiners are i GI
' The recormyndation(s)d M /1644 a44f k.w. Nu nA4. '
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- 8. Examiners Signatur s __ m Tra(ptfWffepartment (1) i ---~~..._
Tr ining ment (2) erating Department
~ .A 3 '
! Approved ,
,. 7-Trainigupervisor APPROVED APR 2 7!994 2
(tIste)
- 8. O. S. R.
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r . . A P P ., O V E D BTP 100-T108 R0 vision 0 APR 271984
( g, f* g g SHIFT ADVISOR ORAL EXAM DOCUMENT NAME Wil l i am M i n o ,. 4 ,-h COMPANY PLD DATE GIVEN 6/29/84
- 1. TOPICS COVERED
' TOPICS
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BTP 100-T108 Revision 0
[ II. CorethTS:
III. ORAL EXAM RESULTS
- A. An oral exam was conducted on trainee .
The recommendation (s) of the examiners are JA . Meersch . , he,,a 4/,_. ,, , jyjp Ma , . A n Ao /g.f4 4 L m U .r,47A Ar,,.
B. Examiners Signatu e
- epartment (1)
[ raif I
Training D W tw nt (2)
'. /W-0, ating Department i I
Approved _ /-
de,, - = ,
Train upervisor APPROVED 1 APR 271984 l
B. O. S. R. (
(4155P) . . . .
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ATTACHMENT G SIIIFT CREW TRAINING PROGRAM l
I
t The training program presented to the operating shift crews regarding the role of the shift advisor will be accomplished by procedure revision training. The licensed requalification
. training program includes training on revised procedures, and also the non-licensed operators will be trained on these revised procedures. The specific procedures that deal with the shift advisors are:
BAP 300-22 Conduct of Operations BAP 300-2 Shift Manning BAP 200-A2-7 Position Description-SCRE BAP 200-A2-3 Position Description -SE BAP.200-A2-10 Position Description -S/A BAP 900-10 Control Room Access.
All operating shift crews will receive this training by August 3, 1984. Any new personnel added to the shift crews will receive training on these procedures during their initial training program.
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F ATTACHMENT H MEDICAL QUALIFICATIONS
All Shift Advisors have been previously licensed and therefore have passed the NRC medical qualification for a reactor operators license.
General good health is adequate for the shift advisors to perform their present duties.
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ATTACHMENTI SHIFT ADVISORS EVALUATION PROCEDURES
-v ,--
BAP 299-Ravision 0 SHIFT ADVISOR PROGRESS REVIEW A. STATEMENT OF APPLICABILITY:
This procedure describes the implementation of the Shift Advisor Progress Review.
B.
REFERENCES:
- 1. BAP 299-T1 Byron Station Management Progress Review Form C. MAIN BODY:
MMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMM M NOTE M M Completed evaluations contain material of a sensitive nature. As M M outlined in this procedure, every effort should be made to ensure
- M proper routing (band carried) and avoid unauthorized disclosure of
- M information.
- MMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMAMMMMMMMMMMMMM
- 1. All Shift Advisors will be reviewed every February, June and October, on the 3rd Monday of the month.
- 2. The observing supervisor shall complete the progress review form with the employee, update the responsibilities and measurement standards for the next approval period and then hand carry the completed forms to the Department Head by the appralsal due date. The employee is encouraged to add any comments as a result of the review prior to signing the review form.
MMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMX i M NOTE M M Only the following sections of BAP 299-T1 apply to Shift Advisor
- M progress review: Paris I, II.B, and V. M MMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMM
- 3. The Department Head shall review the completed portion (s) of the Progress Review Form and initiate feedback as necessary to the cognizant Supervisor to resolve employee or supervisor comments.
l
- 4. Upon completion of the review, the Department Head will sign and hand carry the Progress Review Form to the cognizant Assistant l
Superintendent. The Assistant Superintendent will review the l appraisal, sign, and submit to the Personnel Administrator who will have the Progress Review Form filed in the individual's personnel file.
^0'11F0 W A ON ON _Y
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BAP 299-Revision 0
- 5. Protection of Completed Forms
.a. Completed forms shall be marked CONFIDENTIAL at the top of each page.
- b. Completed forms shall be kept in a locked file when not in use.
- c. Access to completed forms will be granted to a person's department head, the Assistant Superintendent, and Station Superintendent. The Station Superintendent may release the forms to personnel considering an employee for promotion or transfer.
- 6. Progress review for Shift Advisors will include, but is not limited to, the following areas:
- a. Communication.
- b. Attitude.
- c. Ability to mesh with the shift crew.
, d. Ability to provide useful technical information and recommendations to the Shift Engineer.
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- Revision 0 II. IEEquIllEIENIS/00ALIFICATICII FOR PRESENT POSITION .
A. List requirements that the individual must meet for the position which is currently held, i.e., 5110, N45.2.6 qualifications, ANSI 18.1, All5 3.2 Requirements Status I
1
- 8. List requirements for future position individual is being trained for (All5I 18.1, Alt 5 3.2, N45.2.6, Position Description.
Requirements Status i
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IV. CAREER GOALS A W PLAII (List Short fem (51) and Long Tem (LT) chronologically) 3 A. telAT netEE ISIEN nefY l
f the Supervisor ausst discuss these career plans to ensure understanding of the individual's reason for consideration of career paths. Further guidance should be obtained for the Dept. Head or Asst. Superintendent.
B. CAPACITY FOR ADWAllCEMNT ADVAIICIENT P0TENilAL AT THIS IIK:
A. PROM 01ABLE TO POSITI0li O "**' D "
- 8. ALSO, PROM 01ABLE TO
]HOW? ]letEN?
C. Basis for promotion consideratien:
OTHER SUGGEST10lIS:
APPROVED FOR INF0WilfTj_q e. o. 037 (0940P) A s
SAP 299-il
- Revision 0.
IV. (Continued) > -
C. C_AREER TRAINING NE DEVELOPfENI PROGRAM DATE RESULIS CONENTS
- 1. Work Emperience (Change in) e i
j 2. Plant visits (Off site) l
. 3. Task Force /Comitee
- 4. Ceco Training
- a. Technical
- b. Sup for Results
- d. Coaching (KT Perf. Stds.) g g APPROVED l
l
- c~c I FO.q[ypDriVOyy B.O.S.R.
- 5. School or Univ. Courses i
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- 6. Lectures, Workshops
- 7. Reading Assign / Heme Study
- 8. Other i
1
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I (0940P) g
BAP 299-il ,a Revision 0 -
~V. SIGIIAluRES 5 A). Appraisal Prepared by:
HAK IIILE DAIE 8). Appraisal Review Held On:
DATE EW LOYEE'S SIGNAIURE C). Engloyee's Consnents:
D). Department Head Review:
. Sipature/Date i E). Asst. Supt. Review:
Sipature/Date F). Sta. Supt. Review:
Sipature/Date C). Additional Conments:
i l Sipature/Date i
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