ML20151X793
| ML20151X793 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/12/1988 |
| From: | Nagai Y GENERAL PUBLIC UTILITIES CORP. |
| To: | Dromerick A NRC |
| References | |
| TASK-03-04.A, TASK-3-4.A, TASK-RR NUDOCS 8808260105 | |
| Download: ML20151X793 (7) | |
Text
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GPU Nuclear Corporation UC 88r One Upper Pond Road Parsippany, New Jersey 07054 201 316 7000 TELEX 136 482 Writer's Direct Dial Number:
h 6c k't h N
b O - 7. I }
O August 12, 1988 Alexander W. Dronerick U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, f1D 20852
Dear fir. Dronerick:
During our conference call on fiay 26, 1988 you requested additional information concerning SEP Topic III-4A (IPSAR Section 4.6.4), Tornado Missile (see attached telphone communication note).
Our responses to all five questions received are provided in the enclosure.
We believe that the information being submitted is sufficient to resolve the issues relating to the IPSAR Section 4.6.4.
Very truly yours, f'
S
/Yosh Nagai Senior Licensing Engineer
/jbw Attachment cc:
M.W. Laggart w/o enclosure T. Denpsey N. Shah Angela T. Chu - NRC (NRR) f0k j
L l'D&
. p g er'fitf~
O!
8808260105 880812 1
PDR ADOCK 05000219 P
PNU l
1 i
7226f GPU Nuclear Corporat>on is a subs.dary of General Publ,c UtJ.t-es Corporat on
Page 1
of 1
.O.helephone Callin
. UCear o
Date/ Time b Telephone Calbout Communication Notes
>!a y 96' 1988 Interview Person Contacted Location Phone A.
Dromerick,
- 3.. Chu, J.
Kudrick 301--492-1301 Est
- Compan, NRR/"Rc - Rackville,
>! d.
T. Dempsey, N. Shah and Y. Nanai talked to the NRC Staff listed above.
The purpose nr
- Ln +ninns en rnnvorc,, inn..:. <
.n dierocc RFo Tct,fr ITT-4A. Tnrn,dn N!uulloc.
n GPl:N Int t ar dnscribed t hn nothodoloov, fallowinn tornndo missiles, t o maintain the the plant in a hot shutdewn condition hv utilizine the e<istine pipinq vhich takes suction from the torus and sunnlies the isolation condenser.
During tho telephono convnrsation, the staff requested GPl!N provide the following informntion:
1.
Discuss how lono tho i nt us wa t o r woul.! hn nveilahin.
2.
Accnssibility of t he lorn'lv one: nt ed manual valvas (4 valves) 3.
Explain why NPSil is not an issue for the' core sprav pump.
4 linw snnn enn CPUN i sson onnrnnrint" (dinonnstic & rost nrat ion) r, r n r o d u r n s or revi so thn nrnrodurns?
5 Pvninin knw n dinn_nnctir 8 rostorntinn nrnradurn ic invnknd, r.s r.
.-,1 T
no-.
e c h.st, yf,4n,
.,mm,s
, p n s.n m,
c...,
r, cnc.
.n
,im
-r, cuestions.
The staf f requested writt en resnouses es sonn as possible.
T. Domnsev nnd N. Gh,h vill n r n v i ria tho i1fnrr,tinn in \\f. I q"co re 1
I Signa ture i j
~ '
cc:
T. Dampsny Ft. Lno,qart
^0000*
N. Shah
.. MNucloor caicuiation sneat
- $wb.Ct (4tC NO Aev No i
lInda%ienGndenur Makeup OueingTornado Eveni C.15o2 2115450.o40 0
! SFget Aek')
o,.r,o, n '.
a......a e,
- e. r.
P.s.S mith 2 August,1988
- 1. Torus Water Availability I.. _ST' ATE ME NT OF P ROBL El Durinc3 o, icrnodo event at Oyster Creek., deco.y heat from the reath2r will be. remcNed b3 khe T.scloWon condensers (I.c.). Mc6ke up br the boiloff frem M
We It wili be provided from We focus vio, o connechen on one of t-he cote sproij main pumps. This colcutokbn computes rbe amount of Hme of fer r eac.br shutdown Er which the decay heat can be removed by odding 10,000 Ft of makeup 8
unkr to the LC she4 frorn the terus.
II.. SOMt1ARY OF R ESUt TS h adding 10,000 fi5 op wgher from tbe brus b Se shellside of We 1Cs thiS 3 stem 1
is enpable of ferncn[ing decay heat fre,m the fearlor core be opproxirnatelg l15 hours eactadnc3 ne amount of m6er in%htig in the 7.C shetts. If Fhe. iniKol s helisde N
henkry is coresideted, +hs ICs are capable. of terecNing deca 3.cd rer obcoA h
13 bours.
H.REFE2. ENTER
- l. 0 ster Creek Opero hans Plant netnual, module 13,'I.soloism Conderms', Revisitrn 0, 3
March 1987.
- 2. ' REruM o:L - A Pregram (3r Transient Nemat Herautic Arctasis ef Compnea Fluid Fbio Syste ms ', EPRI repor t. W P-185o cc.tta,Matume 1, Stevision 2.,se ekdn V, Nevernber 1984.
- 5. A5HE 5teano Tables, 5:our% Edib*on, LS19.
H, ASSOMPTioNs LBete ourA
- 1. En%1N of eteum at 5 peig (,1C shetts.de operah'ng pressure) hg = lisbalu/lbe GaF 3:
- 2. Enthalpy eF brue wahr cut O psic3, (10'F ho = 58 BTV/lbm (Re i O
- 3. Denoih3 of torus wo)er at. O psis,90'F f = fo21 lbm/ft3 leef 3)
- 4. Decog heel data based on Re fuence 7-.
- 3. CAL.wt. ATtoQ In order to determine the kmt of kr teatter sbuhben Er wh'ch coe s deca 3 but can be rernoged by acidirq 10,000f4 3 ok shelt ide makup unkt Frcm the 4 crus, the foltount'rg procedute uns followed i N70016106-86)
l i
E Nu21ccr Celculatisn Shoot l
Le.ci c.ic No w., so i ss..i n
,Tubb Gndefoer itWp_QuitrgloIDoch Event C-@l.AlUidM C
l3 o' jo,.c.,or o...
- s.....o e,
o...
P.S.Smi W 2 August t918 i
- 7. _C ALC.0LATio@ (conVnuedl I. Ausum a Mme afkr shu%wn (t).
- 2. Coltulate 'inte<3mh d de cat 3 hen 4 usinc3 %e preg tum I'n A ptrdi A ( Q (AD.
P
- 3. Compuk We mass of unter regu'ued b remex Het ctmount of entec 3y ( m )
Q(O m = h - ho 3
- 4. Compute t-ke volu.me of unkt eguiWent b tbt mass of unke ( V)
V= E f
- 5. Re peat s+,ps 1.-4 u.nHL volurn e = to,cco M.
The seluhon uns ebhnned in 3 ilerabbn.s.
T. Fero Wen 1.
I. ossume b = B hrs 2.
Q = S.3 EB BTU 3.
rn, S.3 EB BTU 4B 2, te ib l b m c
(1154 -5 B) BTV/tdr.
4.
Ve 487.,(o% tbm 7.77 3 R2 62.1lbml M i
T.+ era ken 2.
i
). assu.m e t.* 12 hts
- 2. Q= 7.oSTEB BTU 642,7t4lbm 3
m= 1.0ST EG BTO.
=
(lIS b-58) BW/lbe
- 4. 9 - (s4 2.,714 lbm l'S. 6 5 0 f t8 b2.1 lbrn / ff 3 N70016 (06-86)
. E Nu tcr ccicuiation si,00t s oi.ci
~
cre No 1., so is.. so TsenaHon condenser nakeup Queir4. Tornado Evenn C 001 111 5450.o40
__o l J o4.
o,. e.,o, c..
- 8.... - e,
o...
P. S. Smi kh 2 Acqus1: 1o)B8 1 C Attut.ATtokks (.conHoueO I.4e eo.hh 3 I. A m u m e b* l).S his
- 2. Q = G.BSS EB BTO S. m : b.BSSEB BTQ 624,317 lbm s
(listo -so) STulls 4.
V=
624. m ibe to, c53 4.3 Wis is close to io,ecott.3
=
lo2.1 Ib m / R3 Durinc3 not ma\\ opero.R.ms, the IC shet\\s have a weder inven%
capab\\e of remov'ng deco.u, hec.t fer 1.5 hou ts (re fe.tenc e L). So if We t' Wo.l wake invenb.y is tenu'deied, the T.C sgs km is unpo.ble a f n
remervinc3 dno.3 heckt Or apetextena.Fel3 13 hou.th assuming We e is r
\\o,cc o f+.3 unkt invenbs3 o& led, to I-he shell.
NXXD6 (06-86)
i ENuclear 1
Calculation Sh:et s a,.ci c..e so
's.. so : s..,,,,
Iaotakn cendensec tiekaucoudnqTorredo Event.
c.13c2 2tl.54so.c4o o
41A i
o,. r.,o, c...
a...... m 0.i.
P.S.5miW 2%ug t%g APPtENDn A Em9m.m fo1-cornpunnc3 iv*gredtd deccq heed.
L P R % It. AN Of C M Hit
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i4 lNPUI A." V I ' I N f ' t.1 I IfrF(HRi* 'rIMEim')
$6 I u
.,,o r
' 9 5 i l
is FRACiafNTERPOt.(f. M YS IiMF)
$ ;' piius.pnL un et.e..
18 1:rOPOWER=3.41.(EA*PnUEp 19 F liv tus
.m
?n ir ( I,l.E IInFf1) i r,O F D INI j
si f l ys ' t [ ' n i t,6 <l i
70 0FCA't 9 ( ! 12-liF C A r 1 ( i i
?3 Nt : I f
?4 PRINTf*******a F PROR -I TMF [00 l. ARr,F
- w******i is etnu INI flME9(ilsi
' ;> ms':,?<rsni:RAc1
'> P INTFRAC I x T NTEr.< 0ECAY?, r i nE9 )
w I N i es tur en i n1 F D Ar i.Po r te, ors in kTUIN14 <,413EAeINTPOWER 31 pui.str*iint n
- .nli GNAnrriiMtii una 3 a
4? PRINT (*INXiANTANEOUS DECAY HEAI FRACIION =.
. nEL ONAmE ( FRAf'l n 1 53 vwI sI
( ' r N '.' r n o i :.nr nu r r;1.cn r HI n i
- .NELDNAME(POWEN),* NW")
u 44 PRINI
('
,MELDNAME(1:TUPOWER),' F4 T U / H P ' )
'5 PRI NI <
- r ni s t,Rn t r p DrcAr HIAr rRAc110N
- , MEL.DN AME ( I N I FR All T ( I ) ) )
u 16 PRINT ('TNTEGl<ATED DECAY HEAT 2
- ,MElDNAME(INTPOWER(I)),' MW -HR ' i
- / FtINI
('
. H E l D N A M E ( fli U I N 1 ( I ) ), ' fi T U ' )
18 A5lU (' INPUT Uri[ON (02[ TIT 1 v.t iRF INPUTi' 'OPix'i 39 J T ( fiP I FM i)
,0 f '1 T NPit i 40 END N:'0016 (0686)
l o
c.-
l t
t 2.
Physical Location Of Valves For Operational Accessibility:
V-11 -110, 111 Reactor Building, elevation 56"-9".
The valves are located at 5'-9" above Reactor Building floor (Elevation 51').
No ladder required.
V-11 -4 Ladder required for operation, but alternately V-11-15 can be closed.
V-11-15 Reactor Building, elevation 23'.
The valve is close.to the floor, no ladder required for operation.-
l V-11-34, 36 Air operated valves, operable from control room. Also, manual handwheel availaole for operation.
Valves are on Reactor Building 95' elevation, one foot off the floor.
l 3.
Core Spray Pump NPSH:
Available NPSH using downcomer elevation is greater than pump NPSH requirement (NPSH avail ~,39' > 12' NPSH req'd at 2600 gpm)-
4.
Schedule For Procedure Implementation:
.j Procedure to be revised is 2000-0PS-3024.18. Iso-condenser-Diagnostic and Restoration Actions. This procedure will cover the alternate fill path from the torus using core spray system.
)
The schedule for procedure revision is October 30, 1988.
l S.
Use Of Procedure:
For a tornado event, operator will use normal condensate transfer system first, which is the norcal fill path.
If he finds that this path is not 4
available, he will enter the Diagnostic and. Restoration procedure (see i
item 4 above) and use alternate fill path using torus.
1 i
i I
4 i
I 1
i 7224f J
_