ML20085E929
| ML20085E929 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/17/1976 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20085E900 | List: |
| References | |
| NUDOCS 8308170128 | |
| Download: ML20085E929 (3) | |
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!!r. !iorma C. !!onoley, Director Offico of InapEction und Enforcencat gpy U.S. I ucione Regulatory Cor.nionion Region,.II - Suite 818 230,Penchtreo Stroct, IM.
,yg Atlcntn, Georgia 30303 9
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Dear Mr. !!oucicy:
yf 11RO*CIS FERRY UUCLEAR PLAllT UNIT 3 - REPORTABLE DEFICII2 ICY -
.N l'OSSIllILIYY OF !!ARCIl! ALLY ADEQUATE SUPPORT STRUCTURE ON IfAIM STEA!! A1;D RELIEF VALVE DISCIIARGE PIPI!IG - IE C0!!TEOL O
NO. Il0ll27F2 (1A.h
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Initial report of the cubject reportablo deficiency was rndo to G. R. Ylingler,1;EC-IE, Rogion II, on Docenbor 23, 1975, cad van followed by our January 20, 1976, lotter, J. E. Gilleland
'g if,'8 to Donald F. Knuth. A second interin report una nubnitted to 4 .m j#)
l IT.C by our April 29, 1976, letter, J. E. Gillcland to Hornan C.
't j 1:onolcy. Encloacd is our final report concerning this doficiency W
(Encionura 1) and a copy of the Teledyne analyala (I'nclonuro 2) fj relating to this deficicucy.
4, j,:, j f.:.h-Very truly yours, 3,,,3 J.j 7N44,,5.y
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J. E. Gilloland Anaistant Manager of Power
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-Wi CC:/Dr.E.Volgenau, Director d.f[."' J
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{fi Offico of Inspection and Enforcenant U.S. !!ucicar P.cgulatory Cocmission
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Unuhington, DC 20555
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m On D"e n.ber P3, 3 7/S, an i n i t i al repor t was ra.!e to URC-0!E P i
T on II In:.poe b>r, G. H. Klingler by T. V. Abi.atiello,T. W.
B a rk alc7 Lion' The report was cR. i n o al i rume wi th b,i 15. A'i?$0' h5 (e )
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'D u, s 2 :, the fin 11 report for this occurrence.
miinM D.e.:e r i it i on of Oce u r 'ne e l
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o f t1m, p <. a. u,, Fe r ry rt i n <; te un l i n e s n na r el i e f 'alve d i: cirtre e J
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piping, uht"h wts dt.ne in conjunct i on wi th the propored :,ubsti tut. ion af two E
C r onby rel i e f v'ilve for two Target Hock relief valves on unit 3, revealed S
tnat the I nt. ing pi o nc support of these lines was not adequate to prevent r:t r e,>.1 r< tn exceedind those reported in the FDAH.
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7-Cnune of De fi c i enc.y.
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Yhe W wnn Ferry pl:uit was ori gi nall y de ;i cned uni n, thr> c r i t. r i t cet forth in the 1 %'/ i<<.ne of Fa't' h3' 1.1.
,",2nce this con-did not
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J the t.2 e l, nt rel ie f val ve d ;
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nodel of 1hene 1,orceu.ns L o t, ava i l abl e >
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, e r \\ a L 1'..- u u r.t, used in d.lgni ng for t hi s comitti on.
rxp rl" nee ~ ~ i n f c c"' r i l~
5 pl ant d e s i gn h ul chi un th tt, w hi le l i n e" of i tn o-t.,pe do vibrate' e.c
=eg r;turt up systems u.th high pr-nu re c r i t. i c al
- o. v-l s o t ~ bl ir.n n t, d c r.!n fo Lne a
e n')<nner, they :tabi1,ne,tithin a rhort pc.iod of tir.e and <'r.
. I w i t h i n t.hc endurance stras limit of the piping.
Precent da malol and co:uputer sollyt. ion of the transi.ent J oading phenonnon, en corsi
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in conjunct ion wtth the other loadinbr con'li' lons C- <1 exist ing piping a upport'
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t h ow., t i t.. o e.c, in the piping to be above the stated FSAR values.
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-Safet.y Thalications--
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rgle es dysis of the main cteam lines and relief valve di a u :-~
r r, r{ tow the maximum st ress to occur in the 26"x6" sweepolet mbtir de U on considering pressure, deadweight and other cuntained b ehknical im I
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e, seicmic, and rel ief valve opgrat ion, stres ses are above t he stated N
val ue,
and near t.he yield stress of the material <tt c'eo:.gn o
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M uenperature" ftssuming all these loa ls occurring simultaneo'""-l
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Y an'i s ufi le lent nav,nt-i tu(1e to cause a failure at the sweepolet,
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ta1 c1tw_eter nipe loss or
,mas coo)an a.cen. lent could occur.
The emergency core cooling system is sized N
o read ly nit tgat,e such an accident.
Hw ever, the pr.scibility t hat 'much a S
failure cotdd h:tve occurred is very re ote e-ince me n chest calculated n
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stress was still below that necessary to cause such a feilure.
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o penerli)Llon, _of Corrective Act. ion Tc)cdyne lhlerials Research has conducted a new stress nnalysis for each main cleam and relief valve discharge line in all units at Browns Ferry.
The crit.cria of AU3I B31.1,19'/3 edition, including all addenda up to cummer 19'/S, have been used for this ana. lysis.
Additional mechanical shock arrectors and restraints have been added to the lines for satis-faction of the criteria, t
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Mc Taken to Prevent a Recurrence l
All TVA nuclear plants will be analyzed considering all 3cading conditions i
as required by the applicabic codes and SAR commitments.
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i OM DATE OF DOCUMENT DATE RECErt ED NO TDRIESSEE VALLET AlmIORITY 1-20-76 1-27-76 60069 LTH MEMO REFOH f OTHEN
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OTHER ACTON NECESSARY CONCURRENCE O
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l NO AcilON NECES$ARY COMMENT By CL A351F -
POST OF F ICE F IL E CODE RfG NO DE SCR WTION (Ment Be Untlasse8*si agFERRED TO DATE RECElvf D BY DATE DEFruruary agPott
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ERDials FERRY PIMF UNIT 3 N
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ENCLO5URES COPIES FOR NSIC TIC P9R LITOL SENT TO RBC10t4AL COORDINATOR hf) 5 Eb i
REMARKS b
e C0FT 101. MARTFIIta MIPC r
lV u s NUCLE AR Recut AfoRv COMMISSION 7oRM c 32sd a
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