ML20217D260
| ML20217D260 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/10/1996 |
| From: | Jerrica Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20217D186 | List:
|
| References | |
| FOIA-97-252 NUDOCS 9710030099 | |
| Download: ML20217D260 (20) | |
Text
{{#Wiki_filter:' e /g># 88ev4' NUCLEAR REGULATORY COMMISSION UNITED STATES y a REGION 11 S 101 MARIETTA STREET, N.W, SUITE 2000 eg 8 ATLANTA, oEORotA 3(IED419e %...../ June 10, 1996 HEMORANDUM TO: St wart D Epneter,RegionalAdministrator Il f/wsr~- ".s. FROM: J .7 son, Deputy Director isiori' f Reactor Projects
SUBJECT:
FINAL MEETING MINUTES OF BROWNS FERRY UNIT 3 RESTART PANEL The Browns Ferry Unit 3 Restart Panel met, via telephone, on May 21, 1996, to discuss completion of post restart issues and lessons learned from the restart process. 1 Donket No. 50-296 License No.-DPR-68
Attachment:
Browns Ferry Unit 3 Restart Panel Meeting Hinutes w/ Appendix cc w/att: L. A. Reyes E. W. Herschoff J. R. Johnson A. F. Gibson C. Casto T. Decker iH. S. Lesser L. D. Wert S. H. Shaeffer R. P. Zimmerman S. A. Varga G. H. Tracy F. J. Hebdon J. F. Williams PUBLIC NRC Docket File 9710030099 970929 ME -252 PDR f' '-
I B.@WNS FERRY UNIT 3 RESTAkT PANEL MEETING MINUTES ~ Meeting Date: May 21, 19CP -Meeting Location: Via Telephone Members Present: J. R. Johnson, Chairman, R!l M. S. Lesser, Ril L. D. Wert, SRI F. J. Hebdon, NRR Summary: The meeting was convened o'n May 21, to discuss the status of post restart items and to develop a lessons learned summary regarding the restart process as implemented in accordance with Manual Chapter 0350. As of the meeting
- date, the four TM1 Action Items, which had been designated as post-restart-
-items to be closed during the power ascension phase, have been closed. 1 Attachment i
P BROWNS FERRY 3 ISSUES CHECKLIST Status as of key 2i, 1996 { LIENSEE STATUS ISStE DLSti!PTIJN URC LEAD IE/SER g CIBEE'BTS STATUS l TNI ACTION ITEMS (TI 2515/065) ...n. ~ 9,:r e
- fnspection perfereed 9/M revleed pregram " ~ L pm6.C~
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ISSE DESCRIPTION WRC IE AD IR/STR LIENTE STATUS ttsstufS $7ATUS I *.F)1.2A l Accident Monito*Ing M [ Jones-SER12/22/84';j m-at x 3 4 v ~ %-n e pweay we+gw p!9 d U "! ? _ ' " l pq.uq - T -- " ' @ h;ifA O.U, cemplete ? " M + N P
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ISSHE DESCRIPit0W stC R E AD tt/SER LICENSFE STATUS trzeerstS stafUS. .e s. s <w n - xsm IEs 93-03. Issues cetsted to Reectoc shyetect' set A/20/94 " ensagete'3/95 ..,..., m p" 5
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{ ressel Water Level' inst. _12 93-201' modifications t 'T ~ ~ N
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- refer ts T125tS/128 e. t 4-
- AC M86834 ftA M303 -
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i e,. t 4, _ % AL '~ of 7. 4 IES 95-02 tJrnprJ.ted Clogging of - s*I .It 95-60 licensee response ,.... g... review esmedete far, mit's restere; 4 sneer:teve t v ' .C :t f "y RHR 9. trainers-the prior tof issue.s cerrtfrusing review
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' C7 ~~ ~ ~7 5' NRC ENERIC 1Ef ff RS .,- ~,.. CL 8293 Inst to fettom course of - audisait- $ER 2/8/90 complete ~,
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os'~ 4 g> x g, -ya g% 'pg .,%~ ^ f~' x V C; Accident: R$ 1.97 ' IR90-32 93-M' TAC M51G75; MPA A31T 201; 95-37 s r 4 s .GL E3-25 Sates Arus; Ti 2500/020 Musser
- refer to TI,. 2500/020
+ . ~., x Gt,83 36 - IrJaEG 073T IS NtR 94.-33; Ts' 'ecsplete- ' 1. 14 ,X ^ s C chhnge "" L', +i U ~ 6/21/?G en l e s pagg -
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y~ -,;. GL 88 01 1GSCC in Buit Aust 53 Coley -; $tt 12/3/93;: complete r J* C+ [ x Pipir s it 95-44 m s e s. ~4r. N) C J T ~ 4 i TAC M55296 "i ~ [ e
- ~
e .nn y,z, g ; g~ 77.,~.,4 4 ;- xxy mediation Ewbrittlement? man. SER 6/29/99 73 assuondments'190,1 _.sDES 1435; nas decernened lese is'etened :., ' ci, 88 11 1 .CL 7 of aesetor vestet; t".' ~ 205162 ef 1/8/93
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% 1; + 1-l , M. ; J o s 1.99' .setisfied CLt. 3: - il. ~ *' N TAC MT1/.69; #PA A023 - t' ' ~ 'dR m.. ~ m, m,,G7
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.m p i -m GL 88-14 ; instrument Air Af fecting - Morgen SER 5/9/87; ctuuntete C
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.I. %.C;, se systeen la 95-38 95 ' 1 ^ t$' TAC MT1633; MFA 8107-56 1 'Or
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t i." zsc i ^ G1,86-20; IPE nest. - y-w can.. 4.n , e n r., n. +.. -. ~,..e n c. 'seisade tweLuntlem tepart asse to tBC 3/19/96; closed j C; _ T F/1/93 edimitted - IPE for etI wilts; f 9for" restart purposes
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'"- ~_ Espended Pe4. #..to ? ., ? "W w - d. t ",p[g ( y' s n ;m" "* x.r m 2 74 ~. m - i ..k' SystM Wll i..' > h_f.f ^ N ^ &**2 N A M ]d}q # 4 l yl W e
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- ItsegerA. <5EB 2/5/92/ L-util; e C ctM C SPDS i *..'
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A- - C8 N l n TAC 73636-MPA pet 2W WWE 1 "M"f 4 9 W @ dMWE-Zm w wp, me :, mm~v .Etnoorpe- -em/se: se - ^ =- t,?!.? "py/ 5FQF.--Q7 ~ - n m w' ' e n,. e m!lL
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y 3 le pG GL'89 08{ Erosfan corrosion ; SEE J ie progree in piece 4 n 4 Mr ae C A L wy".?gb$ :~* *t rM i'*' c y~? N t 3 h 7 a-oonitorine pre,res n TAC eT3459; p?A L998 95-41:' ll+ - 4 5 l r h
a Isser tTSCRIPTitus set itmo ta/sta tinustt STATU5 traseruTS status. _g p. 3-y + - w we gwEg g w p w9w!nT ay r.~ GL 8,9-10~... seov Testing Aruf G, S.r' lattner - ++1 .'4a i-., >m 2,515/199 >$2' w4. e * - 5s $; r.,,
- te. f. er to. it..
-* :9 ; ' 1 >a r u." Survelliance a-: m A.s. S 4 , ~a !4 .4- ~xM W;- 'I O C. J W~r TAC M7563tf1984 tilt 'is f* n aM Md' GU 86*h*3 ; service Water Systeenl [etlogg h .aUL +,, .+ v wy --.i 7 . ~ g+,.
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- Befer. toJT Ng Rg'.2 y? j 3pm7W.*10 m f.
fr a + H, . wet ett. vent nre p* g e t et 4 q, 1&- q. 7 4 *. p" - r*, +- ' U+ 4e'Y4 Tac wrts6c; Mrs ett2' y; :yq s are +g;,9 + ~ a.~. r, e.
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~. - +- GL 89 19 USI A-47 Safety -~ NM ' $12 6/23/96; ...comptete -., w ; 7 :y' N Pc 'M% i G @, t73: C;A ; r Systers
- $4. -
M 1-f, %fi. 7 igiltation of Coritrol - SE 9/21/r41 ~ ' ' ~' ~ N ' 4j; TAC M71717; Mrs 3113 ..1- .,-v. .4 + GL 92-04i peactor vesset Weter-SRI SER 3/25/93'. ecaplete Tr constetec Further revlee of mods neuter'IEs 95-05 : c1 s * "O Level. t nstrment ' 1t73-16 ~ 9 14C M%ZT1; MPA 8121 ' - U ';- ~ ' ' ~ x ~ TVA 3/22/95 tiet$W cables use' the setas and have been leeredad tot c GL 92 05 ' Thernotag kiseman-SE 3/11/94;ft. configurettors os tested et us; especity/combwtilde i +._A 95 43 95-60 ~.,. anetysis 1:y 12/2tWand abandoned meteriet rumeved ' by 6/20/9e; not respa. red for costert T ' ~ ~ .,-y,. c,
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96-11'821e reviam ectiert 1.b;l C ,1 GL 95-0Z Long Terin sein for tetlogg. 94-11 95-62~ couptete a ~ action 1.s cleoed; IFt Thernet Hydraulic T' ( ection 2 not regefrgd for' restart (leng term mods dse(' l s.' ~ 3#97) W ~ " #' JN1 ~ Instabilities -+ el 94-03 IGSCC of Core Shroud Bt ske 94-16; 95-44' Lleensee i, ~y .. m 4 q. 4.. c1. gy .SE 1/13/95 concluded structurei-Integrity eilt be; ' z lseinteined for.at leest 1' cycle without rised for andf ~c 1AC M90083' .Inspectiere._ 7.,}. f y%, m;g'" "g% J +. 4 ^ performed h and July'1996 TV4-
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. >~ A 9/23/96 concludts + 7~ l tf2 can be operated;. s.'f5 ] cycle Tz y' }j n.[1. 3 for et leest 1 h ^ x1 i INIRESr1VED SAFETY ISSIES
- tefer to Leny form Tore Deteerfty 9recrum.* T1n w w w s:na m e w e cr.,,e %yr
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. ; ;.4 A 73 Stske s '.s y p f "o.e, - yn, g ., -vc 1 - i.: < ~ ~ Merk i Long Ters Program ( ~ D G C-et'"'x 2513/005 closed 85 19'
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- 92 Tac m07931; sqPA 0001~
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ISWE DES 31PTION net ttan ItIsra tICTWSEE STATUS (IseE~NTS STATUS l
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s.gp, y p s..e. ..+y - y 2 l A*48 f 1 Mydrogen Control Meesures" muster 1 C and sum Ef fects : It 95 31 e g tetei 1*,'
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.i? C' ' ~ s, TAC P55955; MPA A419 ~ F t @i b X. E $ M MP J d 4H?
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1e CENERIC SAFETY ISSUES C11 ' 40 - safety Concerns -. Lenahan~ SER 1/7/86; 'cugtete c ~ a w e ~..-4 'w' g rgwp ._ s; . ifc ' "2 / ^ C-s r.,. ~ Associated with Pipe. .IR 95-03;- ~ i 'ai ~ ~ "' 7
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Breakes In t' t Scree syst a 95*$2 J .. MP. C. 7'
- TAC M43736; MPA $365 ^ ^ '
9' i ^MYM ^4 x.- c ,. v, v nn 4 v, a m;".-- C$li 41 j BWR $cres Dischargef Morgen $Elt. 6/24/53; .TV4 4/27/95.to add i [ @* A Cc'g' e"y Df c;~ voltme Systeen. IE 95-56 } scree pilot afri a .i - y- ,u -Tac wS1016; MPA EDS8: Y-press tow scree 1 ~'M'-~ . ~ .w ,m y
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SERTI Pt ANT ACTIfel ITTMS .-s. v.,. .x. +-;. y xnm.- . n., my y ,,ayyy97 *y ps.*4.v:A004 : .Arpendix ~J Cont Leri * ;F Wh.l ten.er r SER 10/24/84;,i,.ce 9 ete9 W,* y- .' - f .,p, L'kgy72, y y'yz s . ;gy g
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>b lesPEtten Fettsame* STstfee F < ai4. M.J5 _. M lei M M '3 r '_Q ? s __a ^;_A _C "; IFT M 32-02; brus Levet ^ %_Morgen it 95;31 95H d 'J 2N__ _m- . + M W O'Itiasd ' s,W eumC
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'? s "m+m - s> n -, a 4 ny" ing gu , nn .w - IFt 86-41 06i tetocation of NPC1 Emerg . SRI-.. 94-27;'95-43 " A * >,.n.6 r 2 4 4 4' 4 c' 4 - 6 A ' *d W ' M -#X 0-32.- Controt Somes " " ' " ^ ~ i G +f s +,.,.. ...., -, +,, m n m g,y w,.. m,, 9' g.,,. nm. m m. m M_ i -.,: 77, ",,!:%,, S f4 26 C ET... N. 4 f.: Mt ."7T 'R. 1,FI 85-09-02 '
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's E A % C 79 02' R' A S<d ^ ' - Ptar.t operetten for IEEE s N' O ?M tU Ah "LiNbT ' Id :M N ' % I id
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yh (( 7fF c,. T M LER. @ 20 i e m ms. m :; &;' ,,,,, n.,,,r. a,', w wo 32 r w.n .3 e ma a aws a-2 ++ ~ 4 m.w r ? . - :: ~~y n-c c em MM.&;rief%q@ p ;l df,y n,.mp op r jqm:gg 1. m yg a <e y~Q:p>.qsr LEE 85-32' Reevoluetion of Destysi 4 seyelect; ' 9b0415-21 ':.. 't V e M ! .h .f A t& 'J+ g a u> ;-- XX % 4tWtiz 41 ,e n. 9 %- e ~ > < m-+> criterse'for esas s.6.'Z.1 ~ ~ ', M, Mn. m.;;y v v mM 3 9 9%s. e Cn'W 5sW ~'*222 pe n m. > mm 7 y s r,.p:n mm.yg. LER 8_5 33 J.s l monstandard 4* pipe:, .we., -;r~ sal'. f< 95.M L T. A M. %n. ' <. c y-A4 Js e @A i v %, Axyg d3 y@p ++w&O p$ q q: m gm - 9 p
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IS$1E DESCRIPTION IFec TEA 3 ft/Srt t!UN*EE STAftf5 (DetWTS STATIS y x ne IFJ 86-40-03 ? IRM ewer st,pty and ' sa! 9U32; .~ n* yl Q ! g*nf, *,*g.-Mg M*f '., m,q p .x,4 rg ,8 ~ Wp C + precedJre c! anges'per stL J_,p.. I * *,, e n,>- ,4, 4 %
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a ,y g '( 4. 5 - N. 950 Ad', ; "1 a N A / .a $# ' 4mr;'^- .g 3
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'(. 4 v m. g, $ %,r ,- p M-a" O ed - JR E .c
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idantlCed comection of. unquallfled piping to ' M (( M, y; 1 * - y, f - i b,. e+M ~[}~$;M [N.,~, h: ]IM] @E.[*s wf,[ , 2 - y+4{ . v. { fi m iI W k ',,* . - +
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. e. ' ], w 4 w' 4 g contal vsmt sensing tinev t Ic a 3 sen e.4, ~, s, LEs 86-16 f tund leekese problee ' " st ette -. ,+. n:e .,-e o. ~. - , *. ~ 7 ; s n.., * -.,,, n, -,. 4.pe n g p.y. y 4 w 3 7-: q. m s 32 y with tarte bore snkbert 95-26: 7< -pI M ' D
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l 11 $ !, ";; ' y: t' gj+ 7&+& -43 d. $. c;M 4 i n e i,., for forus dm restraint ' J-6 + 1~ k a% '%,~ ? 3 <m4 y
- t.En 86-13' seutron monitor surv test.
SRI 94-36' ~ F4 'c.~ defieleneles ~ m tst! 87-02-02 Limitorme seer ratio whitener 95g9 : c- + o c-URI 87-26-03 RMS put suction and. tenshan 95-321 l' M <q,i ' C 1 nortte load alt w snees
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,4 .1e_ possibly exceeded ~ ~ e y: s y ,r IFi 57-33-02 tellure cf drywett: sa l' 95 16~3 .9 ,.e+4 I C,<
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CJ control air isol velves, 5 p t-s to fait closed on air loss . a a- -'3 [#'*~ i! + et 1 F1 67-37-03 Acactor Water Levet sa! 95 16
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forms large ntst=r ? -i. g^ f 1, *, n., 4. c. a i Outstanding ) ~
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D ? " " W, m s 't +'M' ~Y' VIO 88*04 Failure to Corrtetty sa l' '95 31'. i, ,, ~,.. +r, x .-i a-c .,~,c.7 + 't' $ 1 3.,1 C.. e e 3 ;P 1 translate desig.. requ -w 4.
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~. O 'Q*,J S ?41.W"# into drawings 1,'--~ ~ t R88-12) Bettery'felture: Ph tIlort 95-60i_ m ... s ^ mp - ,h.7.u. ,, ~. Q Qti',7 - Eg il > J.i ,,y m, [;U g( :). Q 4th,. + ; d>MS >
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p, p G 6 ' n9 't n '- ' 3M ~, prevent ewo start ' - %* ?
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r r r3_ s w y ~ ~c;me w n q,.p qm m + p. r v :w ev9m LER 86-14 (Jrplanned genual: stort of SRl: .95-264 ' (.. (, c jcyryQd1j Q 4;(;IQ [YT C++7 - r i mb a b e ~ 7 '*M' 7, V' d 4 - s - ' ^ n s --s r m due to p.e. error --t C
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((R h.25 ' CR cperstor dose may, IS4 t;' ,94-24 \\ b.. .. h[k N$ .. 7,. o .3 ; . m.< r m e w.p'g uys w ce f $m ...pg j f f'- h hI .4M 4 NJ, %,p [NM?4 P D' d';e 88 e r exceed desiso tintts> t.. E. yhM
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a>e to desion controls ~ - 9
Issue DESCRIPTION Mac LEAD 1R/*;Et titIRSTE STAftJS CIBOENTS STAf[t LER 86'*3' 7 ; Inadequete design controO
- Lenahan~
95 52. ?< ~' r,. w g ;.y -; - m m3mg]f X y.l .C) x,. 7 g p, v. ~
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,g s 7 c:.:- t. + process discrep frj IfvAc. q. L 31:7 d% ! !! Tf' ?g ' '0 duct work' + a -
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t OF4 #J ' 4 + LER 88. Inadequate deslytt, Fit tion c 95-606 0' ,n _, n, p.
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'fdp i ' N. + . 41 J @.y, *,- beckte control system not ; 3!. [.;[. w y, NQ, JM i .) si feeettne design req x c- +- t4- +n-es 4. -? w w - +~w-; . +- ' !T1'89-11-03 Deteriorated CE cables Stl '95-22< ..(~- ,y s a w.vg .s m. ' V.3 - .~ ; ; g y s - M
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'C ki 5 Mh ^ i lc. _. IFt 89 17-05 rotto.aJp on Atus sods' tas 95-22 a .n .s IFI 89-20 02 CRD.selenic analysis 81de 95-03 "~ C URt 89-56-02' use of closed menuet sa t ' 96-17 ~ j. ..L c-4 vetves in ECW tlne to' 4 control bey chitter L m. LER 69 Design of suppressian_ tal 95-22 ' ~ 5 s:' 1.y f c peet vacutse retlef system : 3[ c 't, 4 hot provide single, "Ii 4P,,. felture proof - s LER 69 Design error in EEcv anti $21. 95-22 - c si syphon check valves Jb ~ -,m r ,C' LER 89-07'. Cable deterioration. Sal - 95-22, P J" causes ineperable neutron l anonitoring ' ~ ~ ~ ?, < - 3 fI ~C. LER 89-25 besign errors in 250v0C. Fittien 95-60 ~ results'In tassnalytod. Li" l,. f 4 y 1 URII90-3306' RP /Att diversity-sa! 95-22 [' "p-{1 M (,.. .c. i y ' u, ,3 ~- rz - f ~ s.- .5 IFt 90-f.0-01 Deficiencies identified SEI - 95 10 .g y, s ?,t 4 Q 4 [~v O 4,* q f.Q Eg ff CfYd' ~ " no integrated E8f 17 CEV 91-41 01 control 'of Contruction, 341 -- 95 ' 7 t +qt n % t. d" o::t ; a 7pM .3 9 %gON W e.+eg + 4 3 t0W-ot *e 4 5,. a :;t
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1 + N J:e 4 0 =, 'mg p 3 Mi 1.ER 91-01: Felture of Two trains of
- shyntock, 95-10l.
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v wen 7 V - E > n p h,.;1 q.t>aqp m,,,q u .%o.. c :? J -i, g ei. -c" . 9:la{ Star @ power system'to. ~ ~ ~ m, S f t y L+4.?s yy_ M. _ { n 4-9 t fyd IdW 17 W pu' y 1 f ~ + " " - M _..v e a u h., aa M e e 6t: i o.d,_. sm m c, -. n g , m.r o .. me-y 7 LLER:9 *15 .nPct did net fulf}Lt x A' inst: a r95;10 7 c~ ',' ou p@y'p @,14 i fg safety:fis=tlenfreetoutj q$nqg p'g; g y y p p %cq w:. -ne c 1 gsymWw we myy m gamm w.ww, n . m .4 k g, .4 y h. I g m-L' ; g q' i g y' p g]' ptl A ^ ( 4 p URI 92-07-01 Large bore hetkdows irso ' Blake': 93 29 9$-03 g' -(!S?. Q;%-*;g.C:yg g 4 d a ecco checurso proet r o 2 10
Issue Dest 2tPTION NRC (EA3 IR/Stt titDr3TE STAm5 CIBGEENTS STATUS r.. em y.ppng~4 ymhy 3'N 3 m.;qpg , 4 Ifl.,.9240 Circuit Breeker s - sa gt ' 94 18 e - ^ - E's';E i,3
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coordination' ' ~ 4 & &' X A 1: r .r. .g + n, -73, ., - t o m :g q .e. l
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94-15 I. m ., f 7 r. ^, stm erts' 3E 5-+ 11 4 " i H4f'E 144a - ~. 4 ,r- ~s, ,3 g. w~ -- : a '3-7p e y; yq
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v10 92-37 01 ratture to verifyr . sat- -3 94-06 94 32: b *q pf 3 a t.s. JW wi W k Y + MMi 3. N;CG ;; y ' y %.,.m.f secondary ceritsfrummt L k 'iT pp , i 0. ?. _ ; m3 3g M-t.nhgy ,[.(} F 4 W Mt F J n k -? t
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.,~ r-4 a 7-x y, %j gg% w-n:7.. .,z ,v,- LIR 92 F.5F actuation frrn retey SRI. 9b20 K'4 + ; 'J' A a -p C + no.' + -,s L" failure-1 T o I <J7 M et $'. i' C.. LER 92-03 ratture of Reacter rene sal' 9G-32 i, W 7.Y tf lAZ.
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+ .. e to be released thru pcv t ' M i' - p s >m y. URI 93 11-01 wetd Differerences Coley ; 95!44; Qf. A ' 7 ;g' ' 24 C-between the welds asstaned t- +. +t in stwort1 w-4 ,3-e6 .i ~+ 4 -- 4 > y yt m.wm.
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~ IFI M-06 02 Verify Method used to-stake - 95-15' . :' ? '-4 <A^ L + - Gb 4 - ' ' " ~ im tall medge anchort .l i
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[Q*O !Cl E ((!;96 07-03. Verification of.530., setgoda 95t16; 95*34 functional tequirewnts - ~ ^- J5^ ~ - 5 + s c1 r as < m - y s IFt 9,4-07-04 3rstem operationel Wittiams 95-51. .5 'o - ql c- ' b h { {7. ~$,. a s y - bomdary test ~ .7 9 (9j idantification 44' N4C J i-
- 4 IFl 94 11-02 Respome to CL94 02 ret toog.
95-62~ vn, m: y,3, 2 a Q '!i: C, r . ~, 4 .e .. ~~ . !Fli94-12 01 Rosemone transmitter. .Shymtock' ?$-29 7,. -7.r 4 3 a. 9 ,<p3, d-dn B W@Q d j,.., A p yA: a b *(.c ] "~ ' d7 t "1 Drift Problems' ^' e
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w - Review of conen concrete : t @' @w m m1 # # .C -L i ijl Mla J s 3 a c fs - mc e,yc,,y s ~ ~ ,,.a m .,.trt'94-27 02 - Design Methods ' for Anchor - LenehanL 95-41 L - .^ WI. ".. m..n nn y ~ ' y 4 i ? M C F X H 2 ; U N' dy 'C'yd; i E# t # +" d* iFi-S^ 8 o*e% Watlan Tolerance' M' W W-Y& E E 'I ~ ". g 5 + mpyw m:, m ; m.. .,p m f w,7 yfeegy&g*n g ; *ggu;g g s.. p g p.- t URJi96-29-D4. ,N t If fcetf ort f actors lfor,2 Blake ' Jg,a vy wen .,vio.u.n e m m 'W,O 395;1$eghy j dWWjh3 Nk Ws ~ W f wn ga L 6 m 3 a&w ,Mp '.%,. -,f e f +.. ; _ f..- ? -g }.9 }'p +. qsq f e Jy gg-*g.,9 9 p '+ #41 9 ~ ift 9R j' f y ' Q. - j't q9 9 -f L f Q.:- y
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1 LC4 ~ t ,.jO't! 9'5'+10<01 '" Inadegnete second" f,9 party : j _ - Q ~ + ) g, f d rj. S" - Q' & 1 g- ! ; ;.'. %'- y .,.,h.._* D " M@bTpW4 * ? bMdlt y'. / tudisall' 94 35; 95-14; '4 q Q: ~ 4 ~ M >- ' ; >. !. x,' W' a ,Cj I 'tw ' check ty foreaeqM r *(sets ; ' < 95 202+95 51. A cr i 9 s 3?*M*4d., % 3 4 41 * *' 4 6 ~c-. . y M: TW" t- '.*! f a s + e* dh' l i vio 95-15aG1 . Failure to tamlete Mod ~ tenshan 95. , _., ;, mo -..g . e m- .,, ~., s_ t correcttwe actions ~werified fee res ' FS lreen ![:-H [C ; t-( 4 i 'IfN work plan and ' posins open for tenser tens revlear f; tU' 3 @ b^ _, ' ( i ores.Ings -+ r ?
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s Drawings to Reflect As-butIt conditions tJRI 95-16-01 Work Perforned on 1RI 95-31' .~ incorrect equip- ^ .C~ x 4 P IFt 95-19-02. valve motors stator: Whitener-95-53 C. t u a through bolts mods t i IFI 95-23-01 Service stater self rettoge 95-62' ~.-1i c I assessment findings disp L
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UNITED STATLS NUCLEAR REGULATORY COMMISSION S 6 AT TA. O %,...../ No mbe 15 1 96 MEMORANDUM T0: File FROM: J s P. Ja do. Duoty Director i Di ision o Reactor' Safety 1
SUBJECT:
MINUTES OF CRYSTAL RIVER RESTART PANEL FIRST MEETING. NOVEMBER 13, 1996 In accordance with Memorandum from Stewart D. Ebneter, dated November 1. 1996.
Subject:
CRYSTAL RIVER UNIT 3 RESTART PANEL AND ACTION PLAN (Attachment A), a Restart Panel was assigned for the restart of Crystal River. The Crystal River Restart Panel met at the Region II office on November 13, 1996. The i )urpose of the meeting was to: (1) develop a Restart Plan (2) develop a lestart Task Checklist. (3) develop a Restart Issues Checklist, and (4) to - schedule future meetings. The following personnel attended the meeting: T Panel Members - Johns P. Jaudon Region 11. Chairman Frederick J. Hebdon. NRR Vice Chairman Charles Casto. Region II DRS = Kerry D. Landis. Region II. DRP Lakshminaras Raghaven. NRR Others Todd Cooper Resident Inspector
- Billy R. Crowley, DRS Larry S. Mellen. DRS Robert P. Schin. DRS Glen M. Tracy. ED0
- Todd Cooper. Resident Inspector. participated by phone as a substitute for the Senior Resident Inspector.
l_ The following summarizes the actions taken by the Panel: 1. The draft of a proposed NRC Restart Plan was presented by the Chairman and discussed in detail. After discussion and modifications the following Restart Plan was adopted: a. Develop a checklist (i.e. matrix) of all open issues at CR3: this matrix will have non-docketed supplements that show all open allegations and OI investigations. b. Identify the tie points in the matrix (e.g., a LER that is also an unresolved item, which is also an Allegation). o
a 4 c. Group the items by issue (e.g., examples of lack of knowledge of j the design basis). d. Have the licensee develop a package for each issue from the basic j - matrix of which the licensee has knowledge (e.g. LERs. Violations, etc.). f e. For each issue grouping developed in c.-above, assign an inspector to review all the items in the group and to verify by insoection of a samole from the group that the licensee is closing the issues appropriately. If.the sample verification indicates that the licensee has addressed the issues inspected, close the group.- If there are problems with the verification expand the sample. Repeat as necessary until the group is all verified or can be closed based on the expanded sample. c i f, Inerc are several enforcement items concerning engineering performance in process, There items should be combined and processed rapidly rather than waiting for additional examples to be identified-If there are additional examples found later. -these should be dispositioned in accordance with the Enforcement Policy. l g. For allegations. inspect and resolve the technical issues. For late filed allegations, use the late filed process (i.e., assume that the allegation is substantiated and determine if it would c therefore affect the restart recommendation). Have the EICS staff brief the panel on the status of allegations and investigations. i l 2. In accordance with 1.c, above the panel developed the following Basic Groups for the issues: (1) Knowledge of design & licensing bases and adequacy of design margin (2) Regulatory knowledge and perspective (3! Operator performance & knowledge (4) Marginally effective Engineering Organizat. ion (5) Management Oversight including QA and self assessment l (6) Corrective actions (7) Other 3. A dr' aft issues matrix was provided to the panel. The issues matrix was subsequently characterized by areas above and will be reviewed by panel members prior to the next panel meeting to identify which items need to be closed before restart. -The issues matrix is Attachment B. 4 4 y . --..m. ,v.
j 3 4. NRC Inspection Manual Chapter 0350 was reviewed and Case Specific Checklists prepared using Appendix A of MC 0350 as-guidance. The checklists are included as Attachments C and D to the Restart Plan. 5. The list of all open allegations and 01 investigations was reviewed and discussed. 6. The following future meeting dates were agreed upon: December 3. 1996 (7:30AM) - Site December 18. 1996 - Region II January 8. 1997 - Site January 22. 1997 - Region II Docket No.-50-302 Attachments: A. Restart Panel Assignment Memorandum B. Specific Issues Matrix C. Crystal River Restart Task Checklist D. Crystal River Restart Issues Checklist Distributiort Docket File w/atts L. Mellen. DRP/RII w/atts S. Ebneter RA/RII w/atts S. Cahill. DRP/RII w/atts C. Casto. DRS/RII w/atts B. Crowley, DRS/RII w/atts K. Landis. DRP/RII w/atts R. Schin. DRS/RII w/atts J. Johnson. DRP/RII w/atts M. Thomas. DRS/RII w/atts F. Hebdon NRR w/atts L. Raghaven. NRR w/atts G. Tracy. EDO w/atts R.-Zimmerman. NRR S. Varga. NRR
- FOR PREVIOUS CONCERENCE SEE ATTACHED COPY Orrier O'? Doe ett Doe 31GNATURE RAME B0rowley*
JJaudon* DATE 11 / / 96 11 / /% 11 / / 96 11 / / 96 11 / / 96 11 / / 96 COPY 7 YES NO YES NO YE5 NO YE! NO YE5 NO YES NO vrrisiAL ntwnd wri UULUMthi h/f7 r; wntori.Miu
I e... 4 3 4 4 NRC Inspection Manual Chapter 0350 was reviewed and Case Specific Checklists prepared using Appendix A of MC 0350 as guidance. The checklists are included as Attachments C and D to the Restart Plan. 5. The list of all open allegations and 01 investigations was reviewed and ] discussed. 6. The following future meeting dates were agreed upon: December 3. 1996 (7:30AM) Site i December 18. 1996 Region II January 8. 1997 Site January 22, 1997 Region II I Docket No.-50-302 Attachments: 1. Restart Panel Assignment Memorandum 2. Specific Issues Matrix 3. Crystal River Restart Task Checklist 4. Crystal River Restart Issues Checklist Distribution: i Docket File w/atts L. Mellen. DRP/RII w/atts S, Ebneter RA/RII w/atts S. Cahill. DRP/RII w/atts i C. Casto, DRS/RII w/atts B. Crowley DRS/RII /atts i K. Landis DRP/RII w/atts R. Schin. DRS/RII w/atts J. Johnson. DRP/RII w/atts M. Thomas. DRS/RII w/atts i F. Hebdon, NRR w/atts L. Raghaven. NRR w/atts G. Tracy. E00 w/atts R. Zimmerman. NRR S. Varga NRR i / arrier pit ret otvI l l 110 MATURE .( h WE BCrowlei Naudati / R /96l b/% BATE 11 /_ / C / % 11 L 11 / / 96 11 / / 96 11 / /% 11 / copn Tv?5/ NO (YEs) NO VES NO YES NO YES NO YES NO ll vrriciA TcLunu Luri uutuMthe Mt r. \\truor i, Miu i d
CRYSTAL RIVER RESTART TASK GHECKLIST i st.tm es e I TASK MC 0350
- RESP, REFERENCE STATUS REF APP A tI'ssueLoreliminary notiificat'ioni BI2T RII!:
'C4 f Congressional Notification B.2 g.
- Estab11sh5REstartlPanell
-Bi3 !ah -;RIIENRRi 11/1/9 s 'C f ~ 4,. ~ -SOEnitrl l Assess available information B.3 b. 1-Brief Regional Administrator B.3 d. RII Brief NRR Executive Team B.3 e. 3 f. Develop 5C$seSpedifielCheck11sti iBI3if( RIliNRRi l i 913/9s ' D> 1 l Develop Restart Action Plan B.3 g. RII. NRR 4 Regional Administrator Approves B.3 h. RII Restart Action-Plan NRR Associate Director Approves B.3 1. NRR. Restart Action Plan Implement Restart Action Plan B.3 j. Evaluate' findings of IPAP B.4.1 a. Inspection Licensee performs root cause B.4.1 b. Licensee analysis and develops corrective action plan NRC evaluates licensee's root B.4.1 c. cause-determination and corrective action p;an Review licensee generated B.4.3 a. Panel restart issues -Independent NRC identification B.4.3 b. Panel of restart items-(consider external sources) NRC/ Licensee agreement on B.4.3 c. Panel restart issues Evaluate Licensee's restart-' B.4.3 d. issues implementation process 4 lB P Attachment C
1 TASK MC 0350 RESP. REFER.ENCE STATUS REF APP A Evaluate Licensee's B.4.3 e. implementation of verification process Evaluate Licensee's restart B.4.5 a. RII readiness self-assessment NRC evaluation of applicable B.4.5 b. items from ISSUES section below complete Restart issues closed B.4.5 c. Conduct NRC restart readiness B.4.5 d. RIl team inspection Issue augmented restart coverage B.4.5 e. inspection plan Comments from other parties B.4.5 f. considered Re-review of Generic Restart B.4.5 h. Chicklist comolete Prepare restart authorization B.5 a. document and basis for restart NRC Restart Panel approves B.5 b. Restart Authorization No restart objections from other B.5 c applicable H0 offices No restart objections from B.5 d acolicable Federal Acencies Regional Administrator concurs B.5 e. RII in Restart Authorization NRR Associate Director concurs B.5 f. NRR in Restart Authorization EDO concurs in Restart B.5 g. NRR Authorization when required Conduct ACRS briefing when B.5 h. NRR requested Conduct Commission briefing when B.5 i. NRR reouested ATTACHMENT C ]
._._._._..._...-._._...___._.__m.____.m----__-_- o. i i p 1 [ - TASK MC 0350 RESP. REFER,ENCE-STATUS-REF APP A i i Comission concurs in Restart B.5 j. Authorization when reouired l Regional Administrator B.5 k. RIl j authorizes' restart Notify Comission of restart B.6 a. NRR authorization (if Comission did not concur _in Restart Authorization) l Notify E00 of restart B 6 b. NRR 1 authorization (if E00 did not concur in Restart Authorization) Notify Congressional Affairs of B.6 c. NRR ] restart authorization Notify ACRS of restart B.6 d. NRR authorization (a briefing may be substituted) i Notify Applicable Federal B.6 e. agencies of-restart-l authorization i Notify Public Affairs of restart B.6 f. RII authorization 4 Notify State _and Local officials B.6 g. RII i of restart authorization s Notify citizens or groups that B 6 h. RII i expressed interest during the ? restart ~ approval process ATTACHMENT C
4 CRYSTAL RIVER RESTART ISSUES CHECKLIST st.tus u e ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A i ASSESSMENT OF ROOT CAUSE IDENTIFICATION AND CORRECTION Conditions requiring shutdown C.1.1 a. 4 are clearly understood Root causes of the conditions C.1.1 b. recuiring shutdown clearly uncerstood Root causes of other significant C.1.1 c. problems clearly understood Effectiveness of root cause C.1.1 d. analysis o.rogram Thoroughness of corrective C.1.3 a. action plan Completeness of corrective C.1.3 b. action plan Controi of corrective action C.1.3 c. item tracking Effective corrective actions for C.1.3 d. t the condition requiring shutdown imolemented effective corrective actions for C.1.3 e. Other significant problems implemented Plan Control of long-term corrective C.1.3 f. actions Effectiveness of corrective C.1.3 9 action verification process Effectiveness of 0A Proaram C.1.4 a. Effectiveness of industry C.1.4 b. experience review program Effectiveness of Licensee's C.1.4 c. independent review groups Effectiveness of deficiency C.1.4 d. recorting system ATTACHMENT D Attachment D
i ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A Staff willingness to raise C.1.4 e. concerns Effectiveness of PRA usage C.1.4 f. Effectiveness of commitment C.1.4 9 tracking program External Audit (i.e. INPO) C.1.4 h. capability Quality of 10 CFR 50.72 and C.1.4 i. 50.73 reports Operability ASSESSMENT OF LICENSEE MANAGEMENT EFFECTIVENESS Goals / expectations communicated C.2.1 a. to staff Demonstrated expectation of C.2.1 b. adherence to procedures Management involvement in self-C.2.1 c. assessment and independent self-assessment capability Effectiveness of management C.2.1 d. review committees Management's demonstrated C.2.1 e. awareness of day-to-day operational concerns Management's i.Dility to identify. C.2.1 f. and prioritica significar.t issues Management's abil_ity to C.2.1 g. Coordinate resolution cf significant issues Management's ability to C.2.1 h. implement effective corrective actions Impact of ani Management C.2.2 a. reorganizat'.on Effectiven<!ss and timely C.2.2 b. resolution of employee concerns ATTACHMENT D
.., y i ISSUE MC 03S0 RESP. REFERENCE STATUS {_ REF APP A Adequate engineering support as C.2.2 c. 1 demonstrated by timely j resolution of issues I Adequate plant administrative C.2.2 d. l-procedures Effective information exchange C.2.2 e. 5 with other utilities l_ Participation in industry groups C.2.2 f. l Effectiveness of emergency C.2.2 g. t response organization Coordination with off-site C.2.2 h. .1-emergency planning officials j ASSESSMENT OF PLANT AND CORPORATE STAFF EFFECTIVENESS l Demonstrated commitment to C 3.1 a. achieving improved performance i Demonstrated safety C 3.1 b. consciousness [ Understanding of management's C.3.1 c. [ expectations and goals [ Understanding of plant issues C 3.1 d. j and corrective actions [ Qualifications and training-of C.3.1 e. j staff Staff's fitness for duty C.3.1 f.- Attentiveness to duty C.3.1 9 Level of attention to detail C.3.1 h. Off-hour-plant staffing C.3.1 1. Staff overtime usage C.3.1 j. Procedure usage / adherence C.3.1 k. Awareness of plant -security C.3.1 1. Licensed operator staffing meets C.3.3 a. reouirements and licensee goals Level of formality in control C.3.3 b. room ATTACHMENT D
2 l; j-ISSUE MC 0350 RESP. REFERENCE STATUS j; REF APP-A Effectiveness of control room C.3.3 c. i simulator training Control room / plant operator C.3.3 d. awareness of eauipment status 2 i Adequacy of plant operating C.3.3 e. I procedures Procedure usage / adherence C.3.3 f. Log keeping practices C.3.3 c. l ASSESSMENT OF PHYSICAL READINESS OF PLANT Operability of technical C.4 a. i specification systems Operability of required C.4 b. secondary and suoport systems Results.of pre-startup testing C.4 c. f. Adecuacy of system lineuos C.4 d. I Adequacy of Surveillance C.4 e. i tests / test program 4 l Significant hardware issues C.4 f. r resolved (i.e. damaged i-equipment, equipment ageing. i modifications) j Effectiveness of the plant C.4 h. maintenance program l Maintenance backlog managed and C.4 1. impact on operation assessed I Adequacy of plant housekeeping C.4 j. i-and eouipment storage r ASSESSMENT OF COMPLIANCE WITH REGULATORY REQUIREMENTS i ' Applicable license amendments C.5 a. l have been issued-Applicable exemptions have 3een C.5 b. p granted-I Applicaole reliefs have been C.5 c. granted l ATTACHMENT D i
o. ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A Significant enforceinent issues C.5 f. have been resolved Allegations have been C.5 g. appropriately addressed 10 CFR 2.206 petitions have been C.5 h _approoriately addressed , COORDINATION WITH INTERESTED AGENCIES AND PARTIES Federal emergency Management C.6 a. Agency Appropriate Sate and local C.6 e, officials Appropriate public interest C.6 f. groups local news media C.6 g. i s ATTACHMENT D
i. N, C *pn msg UNITED STATES NUCLEAR REGULATORY COMMISSION p RssoN H - ) TA,' "^ ^ AT O .o December 10, 1996 l MEMORANDUM T0: F FROM: o ns P. Je do. Deputy Director [DivisionofReactorSafety
SUBJECT:
MINUTES OF THE CRYSTAL RIVER RESTART PANEL SECOND MEETING DECEMBER 3, 1996 The Crystal River Restart Panel met at the Crystal River site December 3. 1996. The following personnel attended the meeting: Panel Members Johns P. Jaudon, Region II Chairman Frederick J. Hebdon, NRR, Vice Chairman Charles Casto, Region II 4 Kerry D. Landis. Region II Stephen J. Cahill, Region II Lakshminaris Raghaven, NRR Others Todd Cooper. Resident Inspector Billy Crowley, Region II Robert Schin, Region II The Panel reviewed the restart Issues Matrix and characterized each item as either " RESTART" or "NON-RESTART." The panel also updated the cross reference of issue items which appeared on the matrix as multiple entries (e.g., a single item that ap3 eared as both a Violation and as a Licensee Event Report). The panel decided tlat only one item for each specific case should be retained and characterized as " RESTART" where there were multiple entries for a single issue. The Panel clso determined to re-word the line items related to the IPAP major issues so that they more clearly expressed what inspections were required. The Panel also added the following items to the matrix: e A review of open Appendix R issues to assure that there were no restart and/or operability issues imbedded in them. o A review of operator work-arounds to assure that there were no restart ' or operability issues contained in them, A_ RESTART item "Either to conduct an ILRT or to request a license o amendment to use Option B of Appendix J to 10 CFR Part 50." e A RESTART item for review and issuance of Licensee Amendments for Unresolved Safety Questions (US0s). This item was characterized by the board as a tickler for specific amendment requests that are expected to resolve individual US0s. gf6?\\ooth
d.d4udtd t 2 7 e' . A RESTART item to review the licensees response to the 50.54f letter concerning design bases sent to all licensees. This response'is due in . February. 3 A RESTART item to review implementation of the license' conditions, e i-j A copy of the revised Issues Matrix is Attachment A. The Panel also reviewed and u) dated the checklists for Tasks and Issues i -(marked as Attachments C and ) to the minutes of the initial Panel meeting.) These revised checklists are included herein as Attachments B and C. During the afternoon. the Panel met with Florida Power representatives at a public meting. This meeting which will be documented by separate correspondence, was for the purpose of having licensee representatives present their restart matrix. This licensee matrix will be discussed at the next Panel meeting. The tentative schedule for future Panel meetings was established as follows: Dit.g Time Location December 18. 1996 10:00 am Region II January 10, 1997 7:30 am CR3 Site January 22. 1997 10:00 am Region II Docket No. 50-302 Attachments: A. Issues Matrix. B. Crystal River Restart Task Checklist C. Crystal River Restart Issues Checklist cc w/atts: S. D. Ebneter RII L. A. Reyes RII E. W. Merschoff. RII F. J. Miraglia NRR S. A. Varga. NRR G. M. Tracy._0EDO R. P. Zimmerman. NRR J. A. Zwolinski.:NRR I i
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ISSUE D MCRIPTI0ss aam ' N 23/ m Em m M 1m STNFWS SW BA 95-126,- Design controle failed to ens:re adequate safety margin for 6, 1 IIOW 3.D.1 HP1 pumps for certain LOCA scenarios (SLIIII. twas ERI 94-22-04) EA 95-126, Swapover of ECCS pumps
- suction from BetST tat five feet t to 6, 1 te0V 1.D.2 reactor building sump was inadequate (SLI!!I (was EEI 95-22-08)
EA 95-126.. EOPs allowed single LP1 pump' to supply two HPI pumps, with 6, 1 NOV II.A' twas insufficient NPSH for LP1 pump (Stil!) EEI 95-22-04) EA 95-126, Failure to take adequate corrective actions for tank 6, 5 NOV II.B twas volumes / level / suction point ISLIV) EE! 95-22-03) EA 95-126, Failure to ensure fire water storage tank contained adequate 6, 1 te0V II.C (was volume of water (SLIV) EEI 95 22-03) V10 93-16 07 Inadequate EOP and AP procedares 6, 3 See IR 96-04, IR 96-08i VIO 94-25-01 Failure to properly control the Cbntrol Complex Habitability 6, 7 See tRI 95-02-02 Envelope (door blocked ooen for maintenance work) VIO 94-27-02 Failure to make two 10 CFR 50.73 reports to the NRC within 6, 2 See IR 95-02, IR 95-08 t he required t ime VIO 94-27-03 Failure to make one required 10 CFR 50.72 report to the NRC 6, 2 See IR 95-08 within the revilred time g i VIO 95-16-03 Inadequate procedure for operation of the makeup pump 1A 6, 1 l cooling water j i VIO 95-21 03 Failure to isolate the class 1E from the non-class 1E 6, 1 electrical circuitry for the RB purge and mini-purge valves 4 VIO 96-01-01 Inadequate corrective action for HP1 flow indication problem 6, 5 VIO 96-01-05 Two examples of failure to update FSAR as required by 10 CFR 6, 4 50.71(el VIO 96-01-06 Failure to correctly translete design basis of SW system into 6, 1 procedures, drawings,' and instructions VIO 96-02-01 Failure to maintain 0.2 footcandles in the protected area 6, 7 See IR 96-07 V10 96-02-04 Failure to maintain secondary alarm station rmerehte and 6, 2 inadequate m+;.matory measures VIO 96-03-11 Failure to follow radiation work pasent r equi reau-nt s 6 7 VIO 96-03-12 Failure to report the transport of a radioactively 6, 2 contaminated individual of f site VIO 96-03-13 Unescorted visitor personnel within the protected area 6, 7 .7
.m. m _m ~ ISSUE DESCRIPTZW Anak w 1R/sm 3,2Cm rummsesyg m LEND status STATUS VIO 96-04-02 Failure to take prompt. corrective action 6, 5 VIO 96-05-01 Failure to create a FR and OCR 6, 5 VIO 96-05-04 Licensee approved eddy current accer ance criteria different 6, 2 from TS requirements VIO 96-05-05 Failure to follow procedures for updating design basis 6, 4 documents t v!O 96-05-07 Inadequate receiving inspections for batMry chargers ivendor 6, 4 testel VIO 96-05-08 Failure to follow purchasing procedures for inverters 6, 4 l VIO 96-06-02 No procedure for deelneralized water flush performed by 6, 3 operators on borie acid addition lines VIO 96-06-04 No evaluation on non-FSAR vital battery charger configuration 6, 4 VIO 96-06-06 Failure to timely notify the NRC of a condition outside the 6, 2 i M endix R Licensing design basis VIO 96-06-07 FR not initiated to resolve CREVS test failure 6, 5 VIO 96-07-01 Failure to protect safeguards information 6, 7 VIO 96-07-02 Failure to complete screening elements for Fitness for Duty 6, 7 Personnel VIO 96-08-01 Corrective action not taken on make-up system audit findings 6, 5 si excessive vibration on spent fuel pool pump cooling fan mot or VIO 96-09-01 Failure to follow a maintenance procedure resulting in the 6, 7 inadvertent initiation of the control room emergency i ventilation system VIO 96-09-02 Unescorted visitor personnel within the protected area 6, 7 VIO 96-09-03 Failure to perfore a 10 CFR 50.59 safety evaluation for 6, 3 changes to procedures described in the FSAR for controlling dissolved hydrogen concentration in the RCS VIO 96-09-04 Failure to update operating curves to reflect 1981 power 6, 4 aprate VIO 96-09-05 Failure to incorporate design change of MtN-64 into 6, 4 operations procedures VIO 96-09-06 Three examples of design control errors (erroneous 6, 4 calculation inputs and 151 boundaryl VIO 96-09-07 Untimely corrective actions for the EFIC system concerns and 6, 5 problems VIO 96-11-01 Inadequate work instructions to prevent the inadvertent start 6, 7 of the A EDG 8 I
f Issam sesenIPttes maast senc Ia/sma LIcemens commanums une ' tamp STRTUB WEPTW VIO 96-11-03 Personnel performing work on the roector building susy 6, 1 without logging onto a clearance, as required by approved est i VIO 96-11-04 Reactor building susp not constructed in accordance with 6 1 approved construction drawings - i l l 1 IFI 94-18-09 Review periodic verification plans - MOV IGL 89-10 iteel 2 See IR 95-11 IR 95-21s $*e CL 89-10 IFI 95-02 05 Resonance noise in vicin ty of MUV-25 7 l IFI 95-08-03 Emergency Operating Procedure update program 3 See IR 95-16 I IFI 95-11-01 SCBA requirements for personnel during a toxic gas release 2 I IFI 95-15-01 Design requirewnts for nitrogen overpressure tservice water) 1 See IR 95-21 IF1 95-15-02 Design requirements for dynamic LOCA ef fects 1 See IR 95-21 and TIA 96-013 IFI 95-15-03 Design requirements for reactor coolant pump cooler failure 1 See IR 95-21 and TIA 95-014 I IFI 95-15-04 Code requirement for thermal relief valves on decay heat 1 See IR 95-21 and TIA 96-I 014 I removal heat exchangers { See IR 95-21 and TIA 96-l IFI 95-15-05 Relief valves removed from heat exchangers 1 014 IFI 95-21-02 Modification to the standby feedwater pump recirculation line 1 l IFI 96-03-15 Evaluate the licensee's revised TS Bases and related 10 CFR 2 50.59 analysis i' IFI 96-03-16 Review of W.R 95-02-09 01, HPI flow indicators, installation 1 package and functional testing results IFI 96-04-03 Effect of setpoint calculatione on EOP revisions 1 IFI 96-05-06 Large break loss of coolant analysis generic concerns 1 IFI 96-06-09 Deficiencies in Mecaties fire barrier program procedures and 4 d h...tation IFI 96-08-b2 Reactor building cavity cooling piping thermal relief 1 prot ect ion Identified in IPAP IFI 96-201-11 Design basis for decay heat / core flood / reactor coolant piping 1 report as IF-96-201-01 temperature IFI 96-201-12 Conduit sizing criteria - jamsing ratio not considered 1 Identified in IPAP report as IF-96-201-02 IFI 96-201-13 Cable aapacities - several cables exceed Tating, including 1 Identified in IPAP report as IP-96-201-03 DHP-1 4 9
A ISSUE DescR!pT1cer mana M Za/sm LIC M Cm M N STATUS Sta5W IF1 96-201-14 E14 protective trips not bypassed during eneroency mode of 1 Identified in IPAF. operation report as IF-96-201-04' 'I'! 96-201-15 W t. fication of motor starting data 1 Identified in IPfbP' report as IF-96-291-05 ) IFI 96-201-16 Cooruination of Second level undervo.tage relay (SLUR) 1 Identified in IPAP' set ting vs. Inverter operation report as tr-96-201-06 1F1 96-201-17. Coordination of $1MR and fuse protection 1 Identified in IIAF report as fr-96-201-07 l MtFLTI-PLhtrf ACT10095 MPA #B105: Seismic qualification of eqsipment. Licensee's criteria and 2 Empeeted completion December. GL 87-02 procedures approved. Some issues are pe-nding and wuuld be resolved thru audit (scheduled for Mar 971. Licensee's field walkdown results are currently in staf f review., MPA $B111 IPE and IPEEE - These are in staff review. Mot a rest ar t 2 (IPE); item. MPA89118 (IPEEE) MPA SL507: Pressure locking and thermal binding of safety.related gate 2 GL 95-07 valves. Currently in staff review. An RAI is outstanding. ,[ Expected comptetion7 L MPA #L601; Testing os safety-related logic circuits - 2 11/94 - the licensee has 'b CL 96-01 Licensee response in staff review. More details are identified testing f deficiencies that estest required. This issue requires attention. be fixed prior t.o [ restart t [ MPA *'602; Movement of heavy loads over spent fuel pool 2 NRCB -02 - Licensee response in staff review. This would not be a restart issue. MFA GL200; Thermolag - Licenst-clans to use Mecatiss ' 2 See IR 96-01s IR 96-06 GL 92-00s BU fan alternate materie* some reanalysis of APPENDIN R. and j 92-01 some exemption. FA U t.orrier tests of Mecatiss including Ampacity tests are in staf f review. This also may not be restart issue. L MPA SL503: Circumferential cracking of SG tube flaws, 2 CL95-03 Licensee response in e-aff review. MPAS L201: Reactor vessel structural integrity. RAI to licensee on 2 r GL 92-01 Rev 7/22/96. Only a data base issue, not a restart item. 1, Supp 1 MPA SL604: Boraflex degradation. Licensee response is just in. Staff 2 i CL 96-04 review to commence. This may have to be addressed prior to restart because of sensit ivity to spent fuel pool issues. MPA _ s MOV testing 6 surveillance. This item is closed wit h the 2 See IFT 94-1s-09 [ GL 8 9-10 exception of IFI 94-10-09 on periodic verification, which is to be fo!! owed up af ter a new generic consnunication is { issued. i 1 10 t l. I i I B
m ._m--_ .._..m ..- ~ ~ -m.__ .m. ISSUE DESCRIPTICII AREh EWC IR/SER LICEEBm COBEErtS EBC LEhD STATUS f STATT!D __ LICEISS asmenerf/ RELIEF RSOURSTS CCHE Control cosplex habitability envelope - including TIA 95-01 2 need to be addressed. Licensee submittal does not provide adequate TS action. May be denied. R.G. 1.97 RG 1.97 instrumentation - Subcool monitors ete - category 2 Instruments change. Not a big issue. License amendment may be arproved by December. Security ~ Biceetric exception to a!!ow taking security badges of f sate - 2 Biometrics & Staff review is expected to be complete soon. Not a restart issue. I Core Flood Relief request RE: Core flood nozzle - Staff needs more info. 2 Nozzle IW will keep Rif informed. OTSG Tubes OTSG tube testing - Licensee proposed a revised OTSG tube 2 See VIo 96-05-04 acceptance criteria - _THER YLstfE3 O Pressurizer During Refuel 9 a sub-surface flaw was discovered. The 2 Nozzle Flaw licensee performed better inspection during R10 and found the flaw to be acceptable. The new inspection results in redused 1 flaw size and consequently acceptance criteria twhich is based on ratio of flaw to thicknessl changes. May require inspect ion. Staff review in progress. BC Icop In a survey inspection, the staf f noted that certain branch 2 -[ Piping pipes of f the primary coolant loop were not analyzed as Code 6 Analyses Class 1 pipe (i.e., no fatigue analysis) as required by the code. Need technical branch's opinion on this. This is not ewpected to be restart issue. Criticality The licensee did not carry a previously approved exception 2 Monitor from part 70 (70.247) requirements to Part 50 license. Need [ legal interpretation of the status of the exemption. LTOP Charrent TS does not addrass LTOP prevention or sitigation. 2 On the basis of GL 88-11, the licensee submitted information 4 to demonstrate that LTOP in B&W plants have less than 1 in [ 100 reactor years probability of occurrence and as a result l per GL 88-11 non-appendix G methodology can be used f or PT curves. Such a PT curve would provide for higher LTOP enable [ pressure and teeperature and would provida operatinnal flexibility. Staff denied the request in 1995 and requested i a revised response. The licensee expects to respond late [ 1997. This issue should be resolved prior to restart. t Sources for issues include: IFS, LIMS, NUREG 1435 (Status of Safety Issues at Licensed Power f Plants), Resident's OIL, PM's OIL NOTE:.Open allegations, OI investigations, and emerging / draft issues are listed separately. 3 [ i 5 11 i l
i i t t e ' ~ CRYSTAL RIVER RESTART TASK CHECKLIST status u e TASK MC 0350 RESP. REFERENCE STATUS REF APP A b !1ssue preliminary notification" B'i2 i RII CP4 Congressional Notification B.2 g. ?- isinliskRestart P$nel? i In3? aim 'RIIENRRs 51/N964 ' lCi* ^ i i~ * "W ia' ~ iSOEeltni' iz l Assess available information B.3 b. [ Brief Regional Administrator B.3 d. RII Brief NRR Executive Team B.3 e. IDevelop CaseiS6ecific'CNdlists $ 3 ff'. RIIFNRRC fii/13/963 LCIM' i D^veloo Restart Action Plan B.3 c. RII. NRR i Regional Administrator Approves B.3 h. RII i, . estart Action Plan NRR Associate Director Approves B.3 1. NRR 2 Restart Action Plan l Imolement Restart Action Plan B.3 j. I Evaluate findings of IPAP B.4.1 a. l-Insoection i Licensee performs root :ause B.4.1 b. Licensee analysis and develops corrective action olan NRC evaluates licensee's root B.4.1 c. cause determination and corrective action olan I Review licensee generated B.4.3 a. Panel restart issues Independent NRC identification B.4.3 b. Panel 1 of restart items (consider external sources) i L NRC/ Licensee agreement on B.4.3 c. Panel i restart issues Evaluate Licensee's restart B.4.3 d. l issues imolementation orocess i 1 4 i Attachment C
.. _. _ - _.. _ _ _ _. = _ _ _ _.. _.. _ _.. _ _ _..__._ _ _ _. _.. _.__.___. -I J '~ TASK MC 0350 RESP. REFERENCE _ STATUS REF APP A 4-Evaluate Licensee's B.4.3 e. implementation of verification process Evaluate Licensee's restart B.4.5 a. RII l readiness self-assessment j NRC evaluation of applicable B.4.5 b. items from ISSUES section below complete f Restart issues closed B.4.5 c. Conduct NRC restart readiness B.4.5 d. RII e i team inspection l Issue augmented restart coverage B.4.5 e. inspection plan j Comments from other parties B.4.5 f. j considered i-Re-review of Generic Restart B.4.5 h. 1 Chicklist complete Prepare restart authorization B.5 a. document and basis for restart i NRC Restart Panel approves B.5 b. j Restart Authorization No restart objections from other B.5 c applicable H0 offices c I No restart objections from B.5 d aoolicable Federal Aaencies Regional Administrator concurs B.5 e. RII in Restart Authorization NRR Associate Director concurs B.5 f. NRR in Restart Authorization E00 concurs in Restart B.5 g. NRR f Authorization when recuired Conduct ACRS briefing when B.5 h. NRR reauested Conduct Comission briefing when B. 5 1. NRR reauested 4 ATTACHMENT C
. _ _ _ _ _ ~ _. _. _. _. _ _ _. _. _ _. _ _ _ _ -. _ _ _. 1 1 i-i ? P TASK-MC 0350 RESP. REFERENCE STATUS REF APP A Comission concurs in Restart B.5 j. Authorization when reauired i Regional Administrator B 5 k. RII I authorizes restart-Notify Comission of restart B.6 a. WRR authorization (if Comission did not concur in Restart 1 Authorization) Notify EDO of restart B.6 b. NRR authorization (if E00 did not concur in Restart Authorization) Notify Congressional Affairs of B,6 c, NRR restart authorization Notify ACRS of restart B.6 d. NRR authorization (a briefing may be j substituted) Notify Applicable Federal' B.6 e. agencies of restart authorization i Notify Public Affairs of restart B.6 f. RII authorization 8 i Notify _ State and Local officials B.6 g. RII or restart authorization Notify citizens or groups that B,6 h. RII expressed interest during the restart approval orocess i ATTACHMENT C
CRYSTAL RIVER RESTART ISSUES CHECKLIST se.un., e ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A _ ASSESSMENT OF i'00T CAUSE IDENTIFICATION AND CORRECTION Conditions requiring shutdown C.1.1 a. are clearly understood Root causes of the conditions C.1.1 b. requiring shutdown clearly understood Root causes of other significant C.1.1 c. problems clearly understood Effectiveness of root cause C.1.1 d. analysis program Thoroughness of corrective C.1.3 a. action plan Completeness of corrective C.1.3 b. action plan Control of corrective action C.1.3 c. item tracking Effective corrective actions for C.1.3 d. the condition requiring shutdown imolemented effective corrective actions for C.1.3 e. Other significant probl. ems imolemented Plan Control of long-term corrective C.1.3 f. actions Effectiveness of corrective C.1.3 g. action verification process Effectiveness of 0A Program C.1.4 a. Effectiveness of industry C.1.4 b. exoerience review program Effectiveness of Licensee's C.1.4 c. indeoendent review groups Effectiveness of deficiency C.1.4 d. reoorting system ATTACHMENT D Attachment D
3 l ISSUE MC 0350 RESP. REFERENCE STATUS l REF APP A Staff willingness to raise C.1.4 e. concerns l Effectiveness of PRA usage C.1.4 f. L Effectiveness of commitment C.1.4 g. tracking proaram r External' Audit (i.e. INPO) C.1.4 h. T, capability [ Quality of 10 CFR 50.72 and C.1.4 1. j 50.73 reports-Operability j ASSESSMENT OF LICENSEE MANAGEMENT EFFECTIVENESS }- Goals / expectations communicated C.2.1 a. f. to staff Demonstrated expectation of-C.2.1 b. adherence to procedures Management involvement in self-C.2.1 c. ~ assessment and independent self-j assessment capability Effectiveness of management C.2.1 d. l-review committees 4 Management's demonstrated C.2.1 e. awareness of day-to-day operational concerns Management's ability to identify' C.2.1 f. and prioritize significant-1ssues Management's ability to C.2.1 9 coordinate resolution of j significant issues Management's ability to C.2.1 h. implement efective corrective actions 4 l Impact of any Management C.2.2 a. reorganization g Effectiveness and timely C.2.2 b. l resolution of employee concerns )i ATTACHMENT D i-
l 4 e i ISSUE MC 0350 RESP. REFERENCE STATUS REF APP-A Adequate engineering support as C.2.2 c. demonstrated by-timely 4 resolution of issues t Adequate plant administrative C.2.2 d. procedures i Effective information exchange C.2.2 e. 4 with other utilities Participation in industry grouos C.2.2 f. 1 Effectiveness of emergency C.2.2 g. response organization 4 Coordination with off-site C.2.2 h. j emergency pianning officials-ASSESSMENT OF PLANT AND CORPORATE STAFF EFFECTIVENESS Demonstrated commitment to C.3.1 a. achieving improved performance Demonstrated safety C.3.1 b, consciousness Understanding of management's C.3.1 c. expectations and goals Understanding of plant issues C.3.1 d. and corrective actions Qualifications and training of C.3.1 e. staff Staff's fitness for duty C.3.1 f. Attentiveness to duty C.3.1 g. Level of attention to detail C.3.1 h. Off-hour plant staffing C.3.1 1. Staff overtime usage C.3.1 j. Procedure usage / adherence C.3.1 k. Aware _ ness of plant security C.3.1 1. Licensed operator staffing meets C.3.3 a. reauirements and licensee goals Ilevelofformalityincontrol C.3.3 b. room ATTACHMENT D
A R i r ISSUE MC 0350 RESP. REFERENCE STATUS-REF APP A Effectiveness of control room C,3.3 c. simulator training Control room / plant operator C.3.3 d. j y areness of eouipment status Adequacy of plant operating C.3.3 e. j procedures [ Procedurn usage / adherence C.3.3 f. [ loa keeping practices C.3.3 g. 1 ASSESSMENT OF PHYSICAL READINESS OF PLANT Operability of technical C.4 a. specification systems Operability of required C.4 b, secondary and support systems Results of pre-startuo testing C.4 c. t Adeauacy of system lineuos-C.4 d. Adequacy of Surveillance C.4 e. tests / test program significant. hardware issues C,4 f. resolved (i.e. damaged equipment, equipment ageing, modifications) Effectiveness of the plant C.4 h. maintenance orogram Maintenance backlog managed and C.4 i. impact on operation assessed Adequacy of plant housekeeping C.4 j. and eauipment storage ASSESSMENT OF' COMPLIANCE WITH REGULATORY REQUIREMENTS Applicable licerssa amendments C.5 a. have been issued Applicable exemptions have been C 5 b. granted Applicable reliefs have been C.5 c. granted ATTACHMENT D
i ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A 1 Significant enforcement issues C.5 f. i have been resolved i. Allegations have been C.5 g. appropriately addressed i 10 CFR 2.206 petitions have been C.5 h j: appropriately addressed l COORDINATION WITH INTERESTED AGENCIES AND PARTIES j Federal emergency Management C.6 a. -Aaency Appropriate Sate and local C.6 e. officials Appropriate public interest C.6 f. grouer 1.ocal news media C.6 a. t ) i ? 4 i i t i 1 ATTACHMENT D E , -... ~ -
l 1 3 l 4. NRC Inspection Manual Chapter 0350 was reviewed and Case Specific Checklists prepared using Appendix A of MC 0350 as guidance. The checklists are included as Attachments C and D to the Restart Plan. j 5. The list of all open allegations and 01 investigations was reviewed and discussed. 1 6. The following future meeting dates were agreed upon: t i December 3. 1996 (7:30AM) Site l 1 December 18. 1996 - Region 11 l January 8. 1997 Site January 22, 1997 - Region 11 f l Docket No. 50 302 l l Attachments: A. Restart Panel Assignment Memorandum i i-B. Specific issues Matrix C. Crystal River Restart Task Checklist j D. Crystal River Restart Issues Checklist )htrib;t < on: L bcket :1'e w/atts L. Mellen. DRP/R11 w/atts S. Ebneter. RA/Rll w/atts S. Cahill, DRP/Rll w/atts i C. Casto. DRS/Ril w/atts B. Crowley. DRS/Rll w/atts I K. Landis. DRP/Rll w/atts R. Schin. DRS/Rll w/atts J. Johnson. DRP/Rll w/atts H. Thomas. DRS/Ril w/atts F. Hebdon. NRR w/atts I L. Raghaven. NRR w/atts G. Tracy. EDO w/atts R. Zimmerman. NRR S. Varga. NRR
- FOR PREVIOUS CONCERENCE SEE ATTACHED COPY orrter p!f Mt M t ut
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l l ? 3 l 4, NRC Inspection Manual Chapter 0350 was reviewed and Case $pecific i Checklists prepared using Ap;>endix A of MC 0350 as guidance. The checklists are included as Attachments C and 0 to the Restart Plan. 5. The list of all open allegations and 01 investigations was reviewed and discussed, 6. The fo'ilowing future meeting dites were agreed upon: December 3. 1996 (7:30AM) - Site December 18, 1996 Region 11 January 8, 1997 Site January 22, 1997' Region 11 Docket No. 50 302 Attachments: 1. Restart Panel Assignment Memorandum 2. Specific issues Matrix 3. Crystal River Restart Task Checklist 4. Crystal River Restart Issues Checklist )ist rib Jtion- )ocket :11e w/atts L. Hellen, DRP/R!l w/atts S. Ebneter. RA/Ril w/atts S. Cahill. DRP/Ril w/atts i C. Casto, DRS/Ril w/atts B. Crowley, DRS/Rll w/atts i K. Landis, DRP/Ri! w/atts R. Schin, DRS/Rll w/atts t J. Johnson, DRP/Rll w/att : M. Thomas, DRS/Ril w/atts F. Hebdon, NRR w/atts L. Raghaven NRR w/atts G. Tracy. EDO w/atts R. Zimmerman, NRR S. Varga, NRR I ? I r i et t4 errier at t im si u tuar ,g (E a wa, .u. a / i l DAtt 11 s / C / % 11_1 b / 96 11 / /M 11 / / 96 11 / / 96 11 / / 96 I l corn 7?ib/ e (its) no vis no vis e vts e vis e { vtiiLIA LUN) LVFY. [Ah,UMt.NI MM. f ; %M# 4.M u j-j .._...,-_.__-~...,.._.,.,..a....,___,.____,._,.
/ga 8800glg UNITED STATES NUCLEAR REGULATORY COMMISSION l, f W,?! "" "'LTT*,' EMU '"' T 't, N mbe 15 96 HEMORANDUM T0: File FROM: J 1s P. Jaido. Dupty Director Di ision o Re ctor Safety S'JBJECT: MINUTES OF CRYSTAL RIVER RESTART PANEL FIRST MEETING, NOVEMBER 13, 1996 4 In accordance with Memorandum from Stewart D. Ebneter, dated November 1, 1996,
Subject:
CRYSTAL RIVER UNIT 3 RESTART PANEL AND ACTION PLAN, (Attachment A), a Restart Panel was assigned for the restart of Crystal River. The Crystal j River Restart Panel met at the Region 11 office on November 13, 1996. The i j purpose of the meeting was to: (1) develop a Restart Plan, (2) develop a Restart Task Checklist, (3) develop a Restart Issues Checklist, and (4) to schedule future meetings, I The following personnel attended the meeting: Panel Members - Johns P. Jaudon, Region 11. Chairman Frederick J. Hebdon, NRR, Vice Chairman Charles Casto, Region !!, DRS Kerry D. Landis, Region 11. DRP Lassirainaras Raghaven NRR Others Todd Cooper, Resident inspector
- Billy R. Crowley, DRS Larry S. Mellen. DRS i
Robert P. Schin. DRS i Glen M. Tracy EDO J 1
- Todd Cooper, Resident inspector, participated by phone as a substitute for the Senior Resident i
Inspector. 4 i The following summarizes the actions taken by the Panel: 1 1. The draft of a proposed NRC Restart Plan was presented by the Chairman and discussed in detail. After discussion and modifications the following Restart Plan was adopted: a a. Develop a checklist (i.e. matrix) of all open issues at CR3: this matrix will have non-docketed supplements that show all open t allegations and 0! investigations. i b. Identify the tie points in the matrix (e.g., a LER that is also an unresolved item, which is also an Allegation). i 4QO311 r%$
2 I c. Group the items by issue (e.g., examples of lack of knowledge of the design basis). l t d. Have the licensee develop a package for each issue from the basic j! matrix of which the licensee has knowledge (e.g.. LERs. Violations, etc.). e. For each issue grouping developed in c. above, assign an inspector to review al' the items in the group and to verify by ins 3ection of a samole 1 rom the group that the licensee is closing t1e issues appropriately,ddressed the issues inspected, close the grouif the samp licensee has a If -there are problems with the verification expand the sample.p. Repeat as necessary until the group is all verified or can be closed based on the expanded sample, f. There are several enforcement items concerning engineering performance in process. There items should be combined and )rocessed rapidly rather than waiting for additional examples to >e identified. If there are additional examples found later, - these should be dispositioned in accordance with the Enforcement Policy. g. For allegations, inspect and resolve the technical issues. For late filed allegations, use the late filed process (i.e., assume that the allegation is substantiated and determine if it would therefore affect the restart recomendation). Have the EICS staff brief the panel on the status of allegations and investigations. 2. In accordance with 1.c. above, the panel developed the following Basic Groups for the issues: (1) Knowledge of design & licensing bases and adequacy of design - margin (2) Regulatory knowledge and perspective (3) Operator performance & knowledge (4)- Marginally effective Engineering Organization (5) Hanagement Oversight including-0A and'self assessment (6) ' Corrective actions (7) Other 3, A draft issues matrix was provided to the panel. The issues matrix was subsequently characterized by areas above and will be reviewed by panel members prior to the next panel meeting to identify which items need to be closed before restart, The issues matrix is Attachment B.
p 'g NUCLEAR RE LT COMMISSION ATNTA,o Ni Novunber 1,1996 i MEMORANDUM TO: Johns P. Jaudon. Deputy Director Division of Reactor Safety Frederick J. Hebdon. Director Project Directorate !!-3 Office of Nuclear Reactor Regulation Jon R. Johnson. Deputy Director Division of Reactor Projects Lakshminaras Raghavan. Project Manager Office of Nuclear Reactor Regulation Kerry D. La~ tis Chief Reactor Projects. Branch 3 Division of Reactor Projects Charles A. Casto. Chief Engineering Branch Division of Reactor Safety Steven J. Cahill. Senior Resident Inspector Division of Reactor Projects FROM: Stewart D. Ebneter Regional Administrator vs
SUBJECT:
CRYSTAL RIVER UNIT 3 RESTART PANEL AND ACTION PLAN I am pleased to inform you that you have been designated as a member of the Crystal River Unit 3 Restart Panel. Johns Jaudon is hereby appointed as the Chairperson and Frederick Hebdon as the Vice Chairperson. Jon Johnson is designated as an alternate. Panel. members will be responsible for )roviding the necessafy oversight of the Crystal River restart project and mate recommendations to the Region II Administrator and Director of NRR. In accordance with Manual Chapter 0350. Staff Guidelines for Restart Approval, the responsibilities of the Panel include the following and will be further detailed in the Crystal River Restart Action Plan (and MC 0350 Checklist). 1, Review available information related to the current plant shutdown. 2. Establish and maintain the Restart Action Plan including a plant specific Task Checklist and a plant specific Issue Check List. The plant specific Issue Check List shall be coordinated with the licensee. 3. Review the licensee's corrective action or improvement program and. ensure that the scope is sufficient, and addresses identified problems and weaknesses. CONTACT: Kerry U. Landis DRP. Branch 3 (404) 331-5509 .._ ___. _.A%%0chsGng A _ _ _
J. Jaudon, et al 2 4. Maintain an ongoing overview of licensee performance throughout the corrective action process to include periodic meetings (at least biweekly) among members of the panel. 5. Conduct periodic meetings (at least monthly) with the licensee to discuss progress toward satisfactory completion of the prograr,. Meetings with the licensee will typically be open to the publ.c. 6. Provide oversight of the NRC's followup activities. Review NRC inspection and /5essment plans and findings, and licensee performance. Identify areas eM4 OC inspection and technical review are needed. 7. Periodically provide obsessment of licensee performance and corrective actions to NRC management with appropriate documentation (at least monthly). 8. Based on the satisfactory com)letion of the licensee's restart program provide a recommendation to tie Regional Administrator and Director. NRR for approval to restart. Docket No. 50 302
Attachment:
Crystal River Restart Action Plan cc: L. A. Reyes. RI! F. Miraglia. NRR S. A. Varga. NRR G. H. Tracy. OEDO R. P. Zimmerman. NRR J. A. Zwolinski NRR E. W. Merschoff. Ril
- e
l CRYSTAL RIVER RESTART ACTION PLAN l The Crystal River Restart Panel Johns P. Jaudon Region 11. Chairman Frederick J. Hebdon. NRR. Vice Chairman Lakstainaras Raghaven. NRR l Kerry 1. Landis. RIl Charles A. Casto. RIl Stephen J, Cahill. RII i D e i
CRYSTAL RIVER RESTART ACTION PLAN 1. Puroose To provide a plan in accordance with NRC Manual Chapter 0350. Staff Guiclelines for Restart Approval, and assign responsibility for NRC activities related to restart of the Crystal River Nuclear Power Plant. 2. Backaround i On September 2. 1996. FPC shutdown CR3 for re) airing a pipe leak in the turbine lube oil system. While in this condit< on. FPC discovered several potential unr6 viewed safety questions involving the emergency diesel generator (EDG) loadings and design adequacy of the emergency feedwater (EFW) system. FPC plan for addressing these and other issues are currently in development. Since 1994, the staff has observed significant performance concerns at CR3 (e.g., unauthorized makeup tank test, nonconservative trip setpoints.. missed surveillances and failure to follow procedures). Poor operator performance was highlighted by the September 1994 unauthorized test of the Makeup Tank (MUT). The staff also performed a root cause analysis of these adverse trends and determined the probable root cause, i.e. lack of Corrective Action Program (MCAP)ponse, the FPC initiated a Management management commitment. In res FPC's MCAP has not been effecMve in reversing the declinina performance t trend. Since its implementation, the staff observed continued notable deficiencies in personnel performance in general, and more specifically in the area of engineering. The engineering issues include, among others. the inaccurate design basis curve for the MUT. service water system
- design, and persistent control room and Technical Support Center ventilation system issues poor quality of engineering relating to the Steam Generator tube plugging criteria, inadequate assumptions in the l
emergency operating procedures, inadequate safety evaluations, and implementation of modifications which compromised design basis limits. In i April 1996, the staff identified five areas of concern: (1) inadequate management oversight and involvement. (2) configuration management and design basis issues. (3) lack of sensitivity to comply with regulations. (4) a marginally effective engineering organization and (5) poor operator l performance. In July 1996, an IPAP and SSFI also confirmed the staff's
- concerns, i
3. Resoonsibilities i 3.1 The Crystal River Restart Panel will coordinate staff activities. monitor licensee activ1tles, and keep the Regional Administrator informed regarding restart of the unit. The Panel will conduct periodic meetings with the licensee to discuss progress toward ~ satisfactory completion of the corrective action program. The Panel ~..
i 2 Will provide oversight of NRC inspection activities and provide assessment of licensee performance and corrective actions to NRC management. The Panel Chairman will provide periodic briefings to the Regional Administrator. Based on the satisfactory completion of the licensee's restart program the Panel will provide a recommendation to the Regional Administrator and Director of NRR for restart approval. 3.2 The Reaional Administrator will coordinate with the De Executive Director for Nuclear Reactor Regulation. Regional erations and Research, and with the Director of Nuclear Reactor R lation (NRR) in im)lementing the Restart Action Plan. The Regional Administrator will (eep the Director of NRR informed of staff and licensee restart actions. 3.3 The Associate Directc'r for Proiects. NRR will assure that the 4 Commission 1s kept informed of staff and licensee restart actions through Comission paaers. EDO highlights or communications with the E00. Based on t1ese interactions between the staff and the Commission. the need for Comission briefings will be determined by the circumstances-and the Commission's wishes. 4. Action Plan Contents The Task Checklist for the restart process will be prepared for Crystal River from the generic MC 0350 checklist. The issues Checklist will i identify all issues which need to be resolved prior to unit restart. The checklists will be maintained current and revised as appropriate by the Restart Panel. Sumaries of the licensee programs and issues being i upgraded and the scope of planned major inspections shall also be maintained by the Restart Panel, t 5. Records All documents relating to the restart 3rocess will be included in the docket file and, to the extent permittec by 10 CFR 2.790. made public in accordance with NRC policy. Such records include: a) Minutes of Restart Panel meetings l b) Minutes of meetings with licensee i c) Other government actions comunicated to the NRC i d) Comission papers e) Documents approving restart f) Inspection reports g) Lafety evaluations e 1 m.,r._ ,y. ,...mmm,,-.,. ,..-g .,,o, n_._,g...,.,-.,.,...,,%,,.%,,, y, e-r .,mv, .rmm ,,,,w .m
._,..m._ l Attachment B CRYSTAL RIVER 3 ISSUES CHECKLIST status me et nece=eer 1s. 1996 i The Crystal River Restart Panel met on November 13, 1996, and developed seven general areas under which the restart issues will be grouped. Those seven areas are: 1. Knowledge of design and licensing bases and adequacy of design margin l 2. Regulatory knowledge and perspective 3. Operator performance and knowledge 4. Marginally effective engineering organization l S. Management oversight; including quality assurance, self assessment, and corrective action t 6. Corrective actions for NRC violations [ 7. Other t zSSos DescarFrzon mRam see rR/ Sam s.rCasas ccamorrs s-i 1.anD Srmros t i [ 1.IC M EE*S RESTART LIST OF DESIGN-RELkrED ISSUBS (D.I.s)fper 10/20/96 Itr frem FFC) CR3 D.I. 1 NFI pump recirculation to the makeup tank 1 See CRI 96-01-C2 i CR3 D.I. 2 HPI system modifications to improve SBIDCA margins 1 S M CRI 96-01-02 F CR3 D.I. 3 1.P1 pump mission time ' 1 See 121 96-201-01 l t { CR3 D.I. 4 Reactor teilding spray pump la WPSM 1 See CRI 96-201-02 CR3 D.I. 5 Emergency feedwater system upgrades and diesel generator load 1 See URI 96-12-01: EEI 94-12-c2 impact CR) D.E. 6 Emergency diesel generator loading 1 See EEI 96-12-02 j l CR3 D.I. 7 railure modes and ef fects of loss of DC power 1 see CRI 96-12 01 g CR3 D.I. 8 Generic letter 96-06 (Thermal overpressure protection for 1 Cent airewnt piping, penatrations, and coolers 1 I Attactment B
- x. =
=.c=1PTra. -a oc r./== i.re-.= -c 12hD STATtFS STRTWS LI N 'S OT W RSSTART IT M OTSG 7 tabes Adequacy of OTSG tube stress-relieved rolled joints is 7 See licenser Preciarsor questioned. Be*31 analysis of a Davis-Beese pulled CTSG tube. Card PC 96-5077 of current test data, and limited field experience conflict with 11/6/96. test data from 1972 which *gualified* a stress-relieved j rolled joint. GL 96-01 ft.e licensee has identified testing deficiencies in saf ety-2 See MPA 81401 (GL 96-01) t est ing related logie circuits PIvg assas or cowTIntrigo compenaN WITE IPAP - - '.e ZW5PSCTION AND RIT 7 - - uib ACOTTIONS ".= r ~ ;.; - Increased inspection of Problem Identifications focusing on 5 Oversight - OA audits and the eroblem reportim evstee. - Increased IPAP anspection of Problem Analysts and Evaluations focusing on R _. ;." J root coure evaluat ions. Inspection - Normal inspectaan of Problem pesolutions focusing of dat a-t t r, aM mer -im of rar** l' ive *v aa* s. Management - Inspect / Assess licensee's trendim indicaters. 5 Oversight - - Inspect IPAP raccamended areas, ancludang processas fer CA RII Additions audit s. car f ormance assess===et s. end r mt causa evaluatters. Include lacensee's root cause evaluet ten of IF AP f indsms. - Inspect Problem Resolutaons focusang on the Prot' lam perert system Process, including t rSekim of assi'3ned act 3 cn St W. t amely complet ion of act ions, and a-curacy of rm status snf or= net zen. Marginally - Increased inspection of Engineering Problem Identification 4 Effective and Resolutions with emphasis on license
- evaluatiens fer Engineering s terni ficant issues and work backlocas.
Organization - Increased anspection of Qualaty of Engineeringt with - IPAP emphasis on IO CT1t 50.59 screenim and saf ety evaluatier s. Sh-.M securaw of the FSAR, and mana<aamen* cre r s t et. Inspection - Normal anspectaan of Engineerang Procedures and Programs: focusing on root cause trainim and corrective actions e rw-*rn i m + ba i n - se rv t <-* rr~zr m. Marginally - Inspect / Assess licensee's trendim indicators. 4 Effective - Inspect IPAP recowended areas, ancludang the licensee *s Engineering FSAP review crole-t. Organization -Inspect process f or emineerim calculat ions. - RII Additions tack of - Inereased inspection of Engineering Safety Focus; fceusing 1 Adequate on prever identification of discrerancies with the clant's Knowledge of deston t asis an the correct 2ve act1on system. the Design - Increased inspectain of Enganeerang Problem Identiffastion Basis - IPAP and Resolution; focusing on progra's for identifyim 4 siv 9_-. M basis issues and caeturim them an t he car rect ive a-t ten Inspection program. - Increased inspection of Quality of Enginee. ing focusing on sensit ivity/understandim tv the emineeriers/11eansim s'af f of f he til ane ' e des t *1ft basie. 2
~- issue EssCRIPTICEE ARBA EutC 2R/SEE LICENSEE N NBC I.EnD status sTmTus E Iack of - Inspect / Assess license?'s trendim indicators. 1 Adequate - Inspect IPAP ihv. -,0*d a r ea s. Knowle+1e of the Des;9n Basis - RII Additions Lack of - Increased inspection of Engineering Safety Focus; with 2 Sensitivit y emphasis 1 interoretat ion of NPC rules and requ!at i ns, for the Need - Increased anspection of Quality of Engsneerangs focusing on sensit ivity/ understand 1m t v the emin** rim /11cansim etaf f to Comply. of NkC rew lassons. Nith Regulations - IPAP Rm-.M Inspect ion Iack of - Inspect / Assess licensee's gendim indicators. 2 Sensitivity - Inspect IFAP re W ad areass including 50.59 for the Need evaluations. LEPs, and rewronses to NPC violatsons, to Comply Nith Regulations - RII Additions Operator - Increasec inspection of Safm, Fccuss focusing on refuelim 3 Perforinance - act ivit ies, etwmminication within operatiens. con =*micat zon IPAP w2 t h ot h*r sit e groues and overt a= Rew-.M - Noresi inspect 2on of Problem identification and Reso; at ion; Inspection I.xusing on observation of refuelim ed ivit ies, j ic1*=ent at ion et menac-=ent ext e.ats m. and problem resoautton - Nor1mai anspection of Quality of Operations; with emphasis on jwelement at ion of mar.aqawt erpactat ions. sensitivity to conalt ions t hat could votent2 ally d-trade ewloment reliability, and erw=m2nscat sons and cocrdinat ion betwaan or-r at zens and ot her site d*rart=*rst s. i - Normal anspect non of Programs and Procedures Operator - Inspect / Assess licensee's trendim indicators. 3 Performance - - Inspect IPAP reWad areas. RII Additions - Inspect process f or op*rability
- valuations.
INSPSCTOR Pm 807 SYSTEBt (JRI 95-02-02 Cont ro) room habitability envelope leakage. Eacessive 1 See TIA 95003; FPC TS leakage paths through doors. daspers, and drains due to Change Request No. 200 design errors and lack of surveillances/ preventive of S/29/96 1 ens 96-04, 94-10 95-01. 95-04-01, maintenance 95-094 IBs 95-02 95-09, 95-11, 95-16 95-21: FPC ltre. of 5/24/95 and 10/29/ss URI 95-021-94 Escessive cooldown rate 3 tJRI 96-01-02 Discrepancies in the high prs 'ere injection design basis 1 See CK) D.I. is Cit 3 D.I. 2 analysis 3
IBEUR DESCRIPTION AstEE SEC 1R/SEE LIC M BE N WRC LEAD STATUS STATUS URI 96-03-04 Measuring of percent throur,h-wall indications with an 7 See IR 96-06 NRR to unqualifted procedure resolve generic issue Ine TtAl i URI 96-03-05 Eddy current saepte expansion based on degraded tube 7 See IR 96-06 percent agee URI 96-04-01 Discrepmies in the EDBD and the FSAR regarding the 1 prever of post-IDCA beron precipit at ion URI 96-05-02 Design concerns with main steam line hangars used in seismic 1 and ot her dynamie load applicat ions URI 96-06-03 pon-safety related transf er switch used in ES status 1 indicating light circuitry URI 96-06-10 Justification for removal of hermo-Lag protection from the 1 source rarne ins + rument at ion URI 96-07-03 Incorrect information provided by contractors 7 l URI 96-12-01 Emergency Teedwater low WPSN to both puwys due to postulated 1 See CR.3 D 1. Si single failure CRB D f. 7 URI 96-201-01 Kong tern plant cooldewn following a small break LOCA 1 See CR3 D.F 3: Sea IR assuming a single failure in ene decay heat drop line 96-11. Nap taking responsibility for this it em URI 96-201-02 EPSM for building spray pump has very little margin, and sw e 1 See CR) D.I. 4 calculat ion f actors were none one-rvat ive i f URI 96 201-03 Operating curves 16, 17, and le in DP-103B are not validated 4 by 1icesee URI 96-2C1-04 Nonsaf ety-related positioners on safety-related valves 1 See IR 94-08 i URI 96-201-05 Service water system heat loads did not consider maximute 1 input heat (OP-1018. Curve 15) URI 96-201-06 Preferred offsite electrical power source with plant shst 1 down 4500 kw switchyard) is not gali fied UPI 96-201-07 EDG not protected against water spray f rom failure of fire 1 p.ot ect ion deluoe system in Etw rocaw URI 96-201-09 Testing to qualify relays beyond manuf acturers' ratings was 1 inadeTat e I LER 93-02-02 Switchyard cable f ailure caused degraded voltage of Class IE 7 122 99-02-01 cloe*d in IER 93-02-03 elect rical t= wes aM act uat ion of EDG In 95-09 LER 94-06-01 Deficiency in und+rstanding of technical requirements leads 2 LER 94-06-00 closed in LER 94-06-03, to nonconservativa RPS setroint and potential violation of TS 19 95-16. See also VIO 95-02-04 LER 94-06-04, LER 94-06-05 LER 95-09-00 Minimal release during sulfur dioaide delivery causes 7 See IR 95-11 actuation of toxic gas monitor resulting in control room eneroency vent ilar ion act uat ion 4 i
ISSUR DESCRIFT20gg amma umC 1R/SER LICMaggs rysmumyS umC LEAD STRTUS STRPJS IER 95-10-01 Inadequate procedure causes low cooling water flow to make=w/ 1 LER 95-10-00 closed is pump resulting in operation outside the design basis IR 95-16. See also URI 95-11-02, VIO 95-16-01 LER 95-13-01 Design deficiency may cause makeup tank wortening resulting 1 1ER 95-13-00 closed in in f ailure to m**t A W im R requirement s IR 96-c6 LER 95-17-00 Su flow to control room coolers controlled by air operated 1 See In 95-16. VIO 96 valves which could fall open 04 IER 95-18-90, Inadequate TS note allowed delayed entry into TS 140 2 See WCV 95-18-05 LER 95-19-01, IIR 95-18-02 LER 95-19-00 teak instrumentation fer Su flow to RSCUs incapable of 1 See IR 95-18 measurirwy 90 ope L81t 95-23-01,
- isistent design assunptions cause butiding spray flow 1
LER 95-23-00 closed in _ _,st 95-23-02 to te out side design basis is 94-04 LEP 95-25-00, In*4aate isolation of safety /non-safety related circuit s 1 See VIO 95-21-03 LER 95-25-s! LER 95-2s 00, Bwst vacuum breaker has inadequate relief capacity 1 See IR 95-21 IER 95-28-01 LER 96-01-01 EFIC control circuits misrouted; Appendia R concern 1 LER 96-01-00 closed in IR 96-04; See also NCY 96-01-01 LER 96-02-00 Minipurge valve has safety /non-safety related circuit s 1 See VIO 95-21-03 wit hout isolat icus LER 96-03-00, RCS cooldown rate exceeded during cooldows 3 See URI 95-21-04 LER 96-03-01 LER 96-04-00 CCHE control dampers fcund damaged 6 leaking 1 See ORI 95-02-02. IR 95-21 1ER 96-05-01 Su flow to RBCUs could enc *ed design 1 1ER 96-05-00 closed in 1R 94-04 See also VIO
- 6-01-01 IER 96-06-00, HPI instrument error could result in HPI pump runout 1
See IR 95-20, IR 96-04 LER 96-06-01 LER 96-07-00. HPI line SB14CA/100P/ loss of de bus could have inad*quate RPI 1 See IR 96-01 IER 96-07-01 flew inst rumentat ion LER 96-08-00 Ambiguous TS note results in not performing RCS leak 2 surveillance prior to Mm3a 2 LER 96-09-00 Failure to reattach instrument tubing to seismic supports 1 See CRI 96-03-06, IR 94-aft er undif icat ion leads to operat ion out side deign basis 05 LER 94-10-00 low flow in SW system cooled wwMs causes operatiert 1 out s ide design basis LER 96-11-00 Personnel error causes testing deficiency resultirty in condit ion prohibited t'y improved TS (CL 96-01 issues) LER 96-12-00 Operation outside design basis caused by battery chargers 4 See tNtt 94-03-08 IR 96-IER 96-12-01, having inadequate test resulte accepted in error 05 IER 96-12-02 5
1955E ___ - - -xim mama M 13/3m LIC m N M tm sTaNS SW LER 94-13-00 Operator error resulted in the inadvertent actuation of DCP-3 See WCW 94-03-42 1A LER 96-15-00 Personnel errors cause cable separation / isolation concerns 1 See IR 96-04 resulting in operation cutside the design basis (tomic gas sumitorst 12R 96-16-00 CREYS filter testing did at meet TS specs 2 1ER 96-19-90 Failure to verify RB penetrations closed per TS 1 LER 96-19-00 Mon-safety related switch used in safety related wiring for 1 S*e URI 96-04-03 ES status lights LER 94-20-00 Unreviewed sarety questions concerning EDG overloading caused 4 See EE1 96-12-02 , ginterpretation of regulatory reqtst rements ( Four emant es of f ailure to follow refueling procedure FP-203 3 l EEI 96-10-01 EEI 96-10-02 Failure to assure root cause analysis and corrective actions 5 taken to preclude repetition were adequate af ter refuel incident (no PR issued) EE1 96-12-02 CDG loading USQs due to inadequate is CFR 59.59 evaluationes 4 Enforcement conference three examples tone modification & two procedure changest to be scheduled. See CB3 D.1. 5: CR) D.T. 6 EEI 96-12-03 Inst
- equate corrective actions for 10 CFR 50,59 evaluation 5
Enforcement conference errors: two emagles to be sebeduled EE1 94-12-04 Use of unverified calculations to support modifications 4 Enforcement conference to be sebeested EA 95-16 Use of non-conservative tril, setpoints for safety-related 6, 1 See IR 95-16, In 95-21 tuas EEI 95-equipment ISL111). Additional examples iden.tif aed in IR 95-02 04) 26. EA 95-126, Nine instances where operators violated procedures for SCT 6, 3 See IR 96-04 NOV I.A twas pressure / level (SLIII). EEI 95-22-01) EA 95-126 Conduct of unauthortred tests cf MUT without 10 CFR 50.59 6 3 See In 96-04 ' pori.B tes evaluation (SLI!!). Additional emaaples (four tests) EEI 95-22-02) identified in 1/18/96 letter titled EA 95-126 and EA 96-105). (See URI 96-04-08) EA 95-126 Fallere to take adequate corrective actions for operator 6, 5 HOV 1.C.1 concerns regarding OP-1038, Curve 8 for MUT pressure /lewel (was EE1 95-limits (SLIII) 22-01) EA 95-126, Corrective actions for an inadequate Curve S (two STI's ami a 6, 5 NOV 1.C.2 revised Chrve SA & SB) were also incorrect (SLIII) twas EEE 95-22-019 6 m m
ISSUE DESCRIFTION asma mEC II/SEE LICEESSE N NEC Land STAT"JS STATUS EA 95-126 Design controle failed to ensure adegaate safety margin for 6, 1 NOV I.D.1 NPI pumps for certain IOCA scenarios (SLIII) Iwas EEI 95-22-04) EA 95-126 Swapower of ECCS pumps
- suction from BwST tat five feet) to 4 1 WQV I.D.2 reactor building sury was inadequate (St.IIII (was EEI 95-22-04)
EA 95-126.. ECPs allowed single LPI puep to supply two NFI pumps, wath 4 1 N07 II.A twas insuf ficient WPSM for LPI pump (SLIIII EEI 95-22-049 EA 95-126, Failure to take adequate corrective actions for tank 6 5 NOV II.B (was volumes / level / suction poirrt (SLIV) Er1 95-22-031 EA 95-126 Failure to ensure fire water storage tank contained adegaate 6, 1 Nov II.C twas volume of water (SLIV) EEI 95-22-03) VIO 93-16-07 Inadeouate EOF and AP procedures 6 3 See IR 96-04 IR 96-CS VIO 94-25-01 Failure to preperly control the Control Comples Habitability 6 7 See URI 95-02-02 Envelcy. (dccr blocked op**i for maintenance werkt VIO 94-27-02 Failure to make two 10 C71 $0.73 reports to the NRC wathin 4, 2 See IM *S-C2, IR 95-04 the required t ima VIO 94-27-03 Failure to make one required 10 CFR 50.72 report to the NRC 6 2 See IR 95-04 within t he retsired t i=* VIO 95-16-03 Inadequate procedure for operation of *he makeup pwep 1A 6 I coolim water VIO 95-21-03 Failure to isolate the class 1E from the non-class IE 6 1 electrical circuitry f or the RR purce and etni-pur*** valves VIC 96-01-01 Inadequate corrective action for HPI flow indication problem 6 5 VIO 96-01-05 Two emanples of failure to update FSAP as reg 2 ired by 10 CTR 6, 4 $0.71te) VIO 96-01-06 Failure to correctly translate design basis of SW system into 6 1 procedur*e. drawi me, and inst ruet torw VIO 96-02-01 Failure to maintain 0 2 footcandles in the protected area 6, 7 See IR 94-07 VIO 94 02-04 Failure to 1 maintain secondary alarm stat ion operable and 4 2 inadaquat e canpensat ory meme sres VIO 96-03-11 Failure to follow radiation work permit regairements 6 7 VIO 96-03-12 Failure to report the transport of a radiose-tively 4, 2 contaminated individual of f eite VIO 96-03-13 Unescorted visitor per _anel within the protected area
- 6. 7 7
..... --.-.. ~. 4 ISSUE DescRIPTZcer ammk mc IR/Sm LZCussWE N mc tano sta7es svares VIO 96-04-02 Failure to take prompt cor-xtive action
- 6. 5 VIO 96-05-01 Failure to create a PR and OCR 6, 5 VIO 96-05-04 Licensee approved eddy current accepcance criteria different
- 6. 2 f rom TS requirenuanto VIO 96-05-05 Failure to follow procedures for updating design basis 6 4 doewneet a VIO 96-05-07 Inadequate receiving inspections for battery o gers tverm$or 6 4 t est al I
VIO 964-08 Fa11erre to follow purchasing procedures for inverters
- 6. 4 VIO 94-06-02 h3 procedure for demineralized water flush performed by 6 3 cparators on borie acid addition lines VIO 96-06-04 Ito evaluation on non-FSAR vital battery charger configuration 6 4 VIO 96-04-06 Failure to timely notify the latC of a condition outside the 6 2 l
Appendis a Licensing design basis
- l VIO 96-06-07 PR not initiated to resolve CREh5 test failure
- 5. 5 VIO 96-07-01 Failure to protect safeguards informotion 6 7 VIO 96-07-02 Failure to couplete screening elements for Fitness for Duty
- 6. 7 Personnel VIO 96-08-01 Corrective action not ta<en on make-up system audit findings
- 6. 5
& excessive vibration en spent fuel pool pupp cooling fan mot or VIO 96-09-01 Failure to follow a maintenance procedure resulting in tte 67 inadvertent initiation of the control room emergency ventilat ion system I VIO 96-09-02 Unescorted visitor personnel within the protected area
- 6. 7 VIO 96-09-03 Failure to perfore a 10 CF1150.59 safety evaluation for 6 3 changes to procedures described in the FSAA for controlling dissolved hydrooen concem ration in the RCS VIO 96-01-04 Failure to update operating curves to reflect 1981 power 6 4 uprate VIO 96-09-05 Failure to incorporate design change of MUV-64 into 6, 4 cperatfone proredtsres vio 96-09-06 Three examples of design control errors terroneous
- 6. 4 calculation inputs and IST thryl VIO 96-09-07 Untimely corrective actions for the EFIC system concerns and
- 6. 5 problems VIO 96-11-01 Inadequate work instructions to prev =nt the inadvertent start
- 6. 7 of the A EDG 8
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.... ~.. ~_- . -... ~ ~. -. -... - ~ - t 1 i ISSUE DeSot1PTICIE AAAk Inc 1R/SEE LICMSM N WC 4 a.ame staves status t YIO 96-11-03 Personnel performing work on the reactor building sump 6, 7 wit hout logging onto a clearance. as required ty approved WR f j VIO 96-11-04 Reactor building sump not constriseted in accordance with 6 1 approve $ constreetion drawings I l IFI 94-18-09 Review periodic verification plans - Pov iGL 39-10 iteen 2 See IR 95-11 IR 95-21: See CL es-to IFI 95-02-05 Resonance noise in vicinity of %"#-25 7 4 IFI 95-08-03 Emergency Operating *rocedure update program 3 See IR 95-14 IFI 95-11-01 SCBA requirements for personnel during a tonic gas release 2 IFI 95-15-01 Design requirements for nitrogen overpressure iservice watert 1 See IR 95-21 i IFI 95-15-02 Design requirements for dynamic IACA effects 1 See IR 95-21 and TIA 96-011 IF1 95-15-03 Design requirements for reactor coolant pump cooler f ailure 1 See IR 95-21 and TIA 95-014 IFI 95-15-04 Code requirement for thermal relief valves om decay heat 1 See IR 95-21 and TIA 96-removal heat exchangers 014 ] IFI 95-15-05 Relief valves removed from heat exchangers 1 See IR 95-21 and TIA 96-014 I' IFI 95-21-02 Modification to the standby feedwater pump recirculation line 1 IFI 96-03-15 Evaluate the licensee's revised TS Bases and related 10 CFR 2 50.59 analysis 1 IF1 96-03-16 Review of MAR 96-02-09-01, 8tPI flow isdicators, installation 1 package and f unct ional test irag result s IFI 96-04-03 Effect of setpoint calenlations on EOP revisions 1 3 j IFI 96-05-06 Large break Ioss of coolant analysis generic concerns 1 i j IFI 96-06-09 D=ficiencies in Mecatise fire barrier progrew procedures and 4 ^ hm=mt at ion IFI 96-08-02 Reactor building cavity cooling piping thermal relief 1 prot ect ion IFI 96-201-11 Design basis for decay heat / core flood / reactor ctolant piping 1 Identified in IFAF tewperature report as IF-96-201-01 Ir3 96-201-12 Conduit sizing criteria - ja=uning ratio not considered 1 Identified in IPAP 4 report as IF-96-201 -02 1 IF1 96-201-13 Cable aspacities - several cables exceed rating. including 1 Identified in IFAP DHP-1 r w as TF-se-201-01 9 1
.mm._._..- -=- - - - -mm.m. ~-u- -.-.a___ l t n -sm., -e 2./.- ue-.- -e i lamp stavus suurus i f 1 Identified in IPAP l IF1 96-201-14 EDG protective trips not bypassed during emergency sede of operation report as IF-96-201-04 p IF1 96-201-15 Verification of motor starting data 1' Identified in IPAP 1 report as IF-96-201-05 ]. IF1 96-201-16 Cbordination of Seccad level undervoltage relay (SIJJR3 1 Identified in IPAF set t ing vs. Sewerter operat ion report se IF-96-201-06 i IF1 96-201-17 Cbordination of SLI:R and fuse protection 1 Edentified in IPAP [ repcet me IF-96-201-e7 l I L asutTz-Plasrr AcT10ms k } MPA 99105s S2ismic qualification of equipment. Licensee's criteria and 2 Espected completion [ GL 07-02 procedures approved. Some issues are pending and would be December. j resolved thau audit (scheduled for Mar 97). Licensee *s field l walkoown results are currently in staf f review. 5 j MPA $8111 IPE and IPEEE - These are in staf f review. Not a restart 2 (IPE):
- item, MPA98119 i
j fIPEEED h l MPA SL507s Pressure locking and thermal binding of safety-related gate 2 { GL 95-07 valves. Charrently in staff review. An RAI is outstanding. i Erp=cted compietion? [ 1 MPA 81401 Testing of safety-related logie circuits - 2 11/96 - the licensee has GL 96-01 Licensee response in staff review. More details are identified testing I 6 deficiencies that smast y required. 'This issue requires attention. be fiaed prior to r } r= start [ h MPA 93602: Movement of heavy loads over spent fuel pool 2 9.tCB 96-02 - Licensee response in staff review. This would not be a rest art issue. MPA SL208s Thermolag - Licensee plans to use Mecatiss 2 See IR 94-014 1R 96-06 GL 92-08s 80 (an alternate material), some reenalysis of APPENDER R. and 92-01 some esemption. Fire barrier tests of Mecaties including ? Ampacity tests are in statf review. This also may not be rest art issue. MPA SL503: Circumferential cracking of SG tube flaws. 2 GL95-03 Licensee responsa in staf f review. j MPAS L201: Reactor vessel structural integrity. RAI to licensee en 2 CL 92-01 Rev 7/22/96. Only a data base issue. not a restart item. 1, supp 1 MPA SL6044 poraflex degradation. Licensee response is just in. Staff 2 GL 96-04 review to commence. This may have to be addressed prior to n 1 rest art because of sensitivity to spent fuel pool issues. MPA s WJW testing & surveillance. This item is closed with the 2 See IF1 94-19-09 CL SI~IS exception of IF1 54-10-09 on periodic werification. which is 1 to be followed up after a new generic = ication is issued. I l a 1(5 1 i s ,e, e a -r m., n n- ,n. n-.,-..
18555 DESCRIPT2 cur amm ante ta/sm LICusse en - =fs smut Im StaTips STa m LIC m a m /RELI W Egg 5ESTS CCME control complex habitability envelope - Including TIA 95-01 2 need to be eddressed. Licensee subsittal does not provide adequate TS action. May be denied. R.G. 1.97 RG 1.97 instrumentation - Subcool monitors ete - category 2 Instruments change. Elet a big issue. License -..._.a may te approved by Lec=mber. Biomet rics -4 Biometric exception to allow taking security badges of f site - 2 Security Sraf f review is expected to be complete soon. Isot a restart
- fasue, Core Flood Relief request RE: Core flood nozzle - Staff needs more 1.nfo.
2 mrrie EM will keep Ett info med. OTSG Tubes CTSG tube testing - Licensee prrposed a revised CTSG tute 2 See YIO 96-05-04 acceptance criteria OTW ISM Pressurizer Diaring Eefuel 9 a sub-sur race flaw was discovered. The 2 Isozzle Flaw licensee performad better inspection during R10 and found the flaw to be acceptable. h e new inspection results in reduced flaw size and canaequently acceptance criteria (which is based on ratio of flaw to thicitnessa changes May require inepect ion. Staff review in prooress. RC toop in a survey inspection. the staf f noted that certain brancts 2 Piping pipes off the primary coolant loop were not analyzed as Code Analyses Class 1 pipe (i.e., no fatigue analysist as required by the code. Iseed technical branch's opinion on this. This is not errected to be restart issue. Criticality The licensee did -mot carry a previously approved eaception 2 Monitor from part 70 170.2473 requirements to Part 50 license. Iseed legal.nterpretat ion of the s*atus of the cuemption. LTOP Current TS does act address L1TiP prevention or estigation. 2 On the basis of GL 88-11. the licensee subettted information to demonstrate that LTOP in B4W plants have less than 1 in 100 reactor years probability et occurrence and as a result per GL 88-11 non-appendix G sethodology car be used for FT curves. Such a PT curve would provide for higher LTOP enable pressure and temperature and would provide operational flexibility. Staff denied the request in 1995 and requested a revised response. The licensae expects, to respond late 1997 This issue should be resolved prisr to restart. Sources for issues include: IFS, SIMS, NUREG 1435 (Status of Safety Issues at Licensed Power Plants), Resident's OIL, PM's OIL NOTE: Opec. allegations, OI investigations, and emerging / draft issues are listed separately. 11 -}}