ML18283B369

Reportable Deficiency - Possibility of Marginally Adequate Support Structure on Main Steam and Relief Valve Discharge Piping

ML18283B369
Person / Time
Site:	Browns Ferry
Issue date:	04/29/1976
From:	Gilleland J Tennessee Valley Authority
To:	Moseley N NRC/IE
References
Download: ML18283B369 (18)

Text

r >r iu>lpga

~ 830 Power Building cy~

O Al

~ TENNESSEE VALLEY AUT~ITY CHATTANOOGA. TENNESSEE 37401 F76.1' April 29, 1976 Mr. Norman C. Moseley, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 818 230 Peachtree Street, NW.

Atlanta, Georgia 30303

Dear Mr. Moseley:

BROWNS FERRY NUCLEAR PLANT UNIT 3 - REPORTABLE DEFICIENCY POSSIBILITY OF MARGINALLYADEQUATE SUPPORT STRUCTURE ON MAIN STEAM AND RELIEF VALVE DISCHARGE PIPING IE CONTROL NO. H01127F2 Initial report of the subject reportable deficiency was made to G. R. Klingler, NRC-IE, Region II, on December 23, 1975, and. was followed by our January 20, 1976, letter, J. E. Gilleland to Donald F. Knuth. In compliance with paragraph 50.55(e) of 10 CFR Part 50, we submit this second interim report of the subject deficiency.

The entire analysis by Teledyne of all piping and structures related to this deficiency has been received and. is being reviewed. by TVA s Division of Engineering Design. The final report on this deficiency will be submitted. to you by May 14, 1976.

Very truly\ yours, J. E. Gilleland Assistant Manager of Power CC: Mr. John G. Davis, Acting Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 An Equal Opportunity Employer

h e~

l

JUN 4 1976 Docket No. 50-296 e Tennessee Valley Authority ATTN: Mr. J. E. Natson Manager of Power 818 Power Building Chattanooga, Tennessee 37401 REF: DEFECTIVE CAM FOLLOWERS IN GE TYPE SBM SNITCHES Gentlemen:

Thank you .for your letter dated May 19, 1976 pursuant to 10 CFR 50.55(e) regarding. the above item. Ne are looking forward to receipt of your final'report on this matter.

Please refer to Control No. HO 1306 F2 in future correspondence in reference to this item.

Your cooperation is appreciated.

Sincerely, OriI innl sign06 b J i), 'I'iIoInpson Dudley Thompson Acting Director Division of Field Operations Office of Xnspection and Enforcement bcc: w/cpy ltr dtd 5/19/76 PDR LPDR NSIC TIC" Region XX Central Files IE Files DF sled FCE C) FCEB AD, DFO

-GCGo er:mk - GWIIoy-- - - -" Thompson-

~ /76 3s'URNAMd3m'ATd 6/ 6Jg. /76 6/ g /76 NU 3m'orm hEC 318 (Rcs, 9.33) hECbf 0240 S. ODVSRNMdNT PRINTINO DFPICKI I074 520 ISS

~ J>> +

f

'b P

l tf g

't

x XUT~O+"":

<<9g 830 Power Building TENNESSEE VALLEY AUTI-~ITY O m CHATTANOOGA, TENNESSEE 37401

/~-~4 Z'p)6 1S16 April 29, 1976 Mr. Norman C. Moseley, Director Office of Inspection and Enforcement U.S. 1Iuclear Regulatory Commission Region II Suite 818 230 Peachtree Street, NW.

Atlanta, Georgia 30303

Dear Mr. Moseley:

BROWNS FERRY NUCLEAR PLANT UNIT 3 REPORTABLE DEFICIENCY POSSIBILITY OF MARGINALLYADEQUATE SUPPORT STRUCTURE ON MIN STEAM AND RELIEF VALVE DISCHARGE PIPING IE CONTROL NO. H01127F2 Initial report of the subject reportable deficiency was made to G. R. Klingler, NRC-IE, Region II, on December 23, 1975, and was followed by our January 20, 1976, letter, J. E. Gilleland to Donald F. Knuth.'n compliance with paragraph 50.55(e) of 10 CFR Part 50, we submit this second. interim report of the subject deficiency.

The entire analysis 'by Teledyne of all piping and structures related to this deficiency has 'been received and is being reviewed by TVA's Division of Engineering Design. The final report on this deficiency will be submitted to you by May 14, 1976.

Very truly yours, J. E. Gilleland Assistant Manager of Power CC: Mr. John G. Davis, Acting Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 An Equal Opportunity Employer

f' l'5 P'uc lear Regulator>. Cm ission Rem i r>r>

230 Feac.h t.roe St.,

Atlanta, GA 30303 SVzo 296/782 e cjro>.ws r errv Nc c)car P)ant unit 3 Rendix electric'a3 co".nc'" tora f>>i3ccl c-. oat>s the ate a-... cnv5ron>>c~>t:est as c3cscribe6 i~ Ket. ec8 ctaced Rove'bee 28, 19?7, frt>m .J, K. 05 1 le)and to Fdson G. Case: revi sicn ),

dated t)c'@em~<<.r 7, 3977, and r+v$ c$ c;> 2, dated Decpmbc r 6, k9'77 ~ 1t appears that acceieratet3 aging vss the conf ribucf ng factor since unaceo <onnec toes satisfactori1v parsed the steam environment test made $ n Xoverbc'r )977.

Since the unaged connectors passed the steam environs>ent test and>>nc'e Lho conncc'.ten'a used fns<BE conrnln>>>ant on unit t ate 0'clat fLY)7 >Jn<p'ct, contra>ueb t>Z erat.ion of 1)>e facie kl v is >c>ct i f ted. Reporxahi)e eveT>t xmcter

6. 7. 2. a. Cg) .

Polar>t J. G. 3evea sa Power Super intender>t Bravnserrv >>uc LLc:ar Plant

0 S. Huclesr Regulatory Cccssiseion 230 Peachtree St , M Suite 818 htlanta, Gb, 30303 BFRO-a~61 785 On Hazch 14~ 1978, during qualification testing of penetration connectors, the-480 volt connector apparently failed. Confirmation of the failure Wll be made upon completion of tba test program scheduled for 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> arch 15, 1978. The affected unit (unit 3) will be in cold shutdown by 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Narch 17 1978. Corrective action ie. dependent upon final, teat

~

results.

CCs Shift Engineer 8, J Creen, 727 EB-C Power Plant Superintendent F. A. Szcsepsnski ~ 4ll OBB-C Nike Butler, E12D 47 C-K Browns Ferry nuclear Plant J. E Cilleland, 830 PRB-C N. N. Price, Browas Ferry R. C. Parris, 830 PRB-C C. S. Mslker, Ã9D 199C-K P. I Duacaa~ V119135 C-K A. Q. Crevasse, 401 UBB-C J L, Harness'rowne Ferry

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: OREILLY J P ORG: FOX H S DOCD ATE: 03/30/78 NRC TN VALLEY AUTH gATE RCVD: 04/03/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i ENCL i LICENSEE EVENT REPT (RO 50-296/77-0i2) ON 07/i7/77 CONCERNING DURING NORMAL OPERATIQNr TEMPERATURE TRANSIENTS WERE EXPERIENCED WITH THE SIX CHARCOAL ABSORBER BEDS IN THE OFFGAS SYSTEM. DRAINLINE ON THE OFFGAS PREHEATER WAS FOUND PLUGGED... W/ENCLS.

PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER INITIAL:

DISTRIBUTOR 1NITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS

~

X JM INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: AR++W/ CL INTERNAL: REG FILE++W/ENCL NRC PDR++W/ENCL MIPC44W/3 ENCL SCHROEDER/I PPOL I TO~~ W/ENCL HOUSTQN++W/ENCL NOVAK/CHECK4+W/ENCL GR IMES4 +W/ENCL KNIGHT+4W/ENCL BUTLER++W/ENCL HANAUER++W/ENCL TEDESCO+4W/ENCL E I SENHUT++W/ENCL BAER++W/ENCL SHAQ4+W/ENCL VOLLMER/BUNCH++W/ENCL KREGERl J. COLL I NS++W/ENCL ROSA++W/ENCL K SEYFRIT/IE44W/ENCL EXTERNAL: LPDR'S ATHENS'L+~W/ENCL TI C+4W/ENCL NSI C++W/ENCL ACRS CAT B~+W/16 ENCL COPIES NOT SUF.'fITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 780950046 SIZE: i P+2P+4P THE END

E, TENNESSEE VALLEY AUTHORIT IMI,nILmm> mI, <

tAAR 30 3918 gC ril Mr. James P.

U.S. Nuclear 0'illy, R

Director gulatory Commission r>

<mr')

i 'I1 Office of Ins ction and Enforcement Region II foal CA 230 Peachtre Street, Kf., Suite 1217 Atlanta, Ceo gia 303 03

Dear Mr. 0'illy:

TENNESSEE V AUTHORITY - BROOMS FERRY NUCLEAR PLANT UNIT 3 DOC1KT NO. 50-296 - FACILITY OPERATING LICENSE DPR&8 - REPORTABLE OCCURRENCE REPORT BFRO-50-296/7712 The 'enclosed report is a supplement to my letter dated July 29, 1977, concerning temperature transients which were experienced with the six charcoal adsorber beds in the offgas system during normal operation.

This rcport is submitted in accordance with Brooms Ferry unit 3 Technical Specifications, Section 6.7.2.A.(9) ~

Very truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Mrector of Power Production Enclosure (3) cc (Enclosure):

Mrector (3)

Office of Management XnfIormation and Program Control U.S. Nucleax Re~atory ommission Uashington, DC 20555 Director (40)

Office of Inspection and En orcement Q.S. Nuclear Regulatory Com ssion washington, DC 20555 An Equal Opportunity Employer

Ik li k

<<jan

<<k+ ~ I I a" f ~ fi I

lf

~ Ia ",,f<<a,"k <<I ffnfl II'f,f 4

4 n + $ <<QI<<P 'n+I fl f P<<) ) 1 k ag fkf Ia( . nVl Pk"I k P'aP kayak,l a

'.l'.< i~f'<

k

."" wc'<>,

h I

' I I l< I I I I

g I', in I Ik I'r kh r I lk k <<I <<<<raa I

~ SI

~<<53tjn< 4.

hk nll '

A a".

CI,I<<O nk

~ I ~ k)kk)n f I h O n

<<nfl f '<<y ~h 1 ~1 pf l' h

. ('), I

~ I'J'g f fir lt5'

'K'n<<"r <

~ e r

<<ll <<Ia<<Q ) << if<< <<<< fhgf,h<<I', -~r; >

kq" Pk tC'

~, "

I a) l ial In ahf- Ir'-

I wA t

TElZCOPY 'EO KRC I'5'c'lear Regulator j Craxe.i sr ion Remi vn EE 230 'Feachtree St., hV Atiants, QA 30303 IF+-50-296(782 The Brtnws Ferry Ãoclear p)ant unit 3 Bendix e)ectricai cw;nec'tora h'ave failed to pass the st ear:. environs>5 test as described in letters <<feted

Ã~vetcber 28, 1977, fran J. E, Gi11e)and to Kdson G. Case; revisice .5;-

dated Decc~~er 1, 1977, and revis5nn 2, dated December 6, H77. Et appears that accelerated aging @as the contributing factor since unaged ronnectors satisfactorily pssred the steam enviro~nt test cade 5n Kovecber 1977.

Since the Unaged connectors passe<<5 the steam environs>ent test and since the connectors used 5nside conrsfnment on unit 3 are eelati,', y continued operation of i)>e facility 1s )vat5fied. )teportaMe exent. under 6.7.2.e. CPf.

I

(( Jg( f f(~(~<'C ((4ZP4 <<C J. C. Decrease Pmter $ 'lant Superintendent Snnrac terry Xoc1eat Fiant

go-a<

a~f tf

~ $ A I

l P

~y %8. %077

%jan r

XX, 230 Peachm'ee 4e 8%8 P,'e~~

c f

. ~area Qk 80305 I

1 I

t I

jeR'~ ~

an 7/17/77mair S ~sxeeaX

~sapeeataxe Su8Sea~ Lu

~~hem

~ a8eazbex.

~~ ~c. ~~rue.'R be~ee mrna ~ 590 ~

l

~ ~~Cia o

<<++~-~

E.&~ 4'SIPHRCtOO I C I l P W~t Sepo~ro+8eyt

~

%rema:

l ',Ram ma e ~ ~

~

4 P ~ ~

It A

I C

4h r, ~

.J U8 inc lear @ego'Ratazy C~faaf.on 230 jPcechtc'oct StreetUH Svita OX8 Ae1aaLa~ QA 30303 DmO-50-295 / 762'n JeXy 2$ 4976~ 6m~g the revims o9'~r:eW'Eence teyL lug, thy caatraX rod accmmlatora vere fora@ dXsch:>rgcd vitae'. tha contxol. xone drive boiaS eiccbrfceJ.Iy diaarcnO~

a f4 8+ Crees

a TBD 141 (2251) (2-021555E 187) PD 07/05/76 2250 ICS IPNBtJGZ CSP 20572983IS~N;TDBN ATH NS AI.'OO 07-05 I050P EST F 0 N 4 04 5264 503 US NUCLEAR REGULATOR Y COD! 1 ISSI 0 N REGION 2 230 PEACHTREE ST NW ~,'Q 8/8 ATLANT A G A 30303 AT 2.130-HOURS=GULY 4 A UNIT 3 BLADE GUIDE WAS DROPPED DURING

) P-,:REN Ql AL. HO. APPARENT DAMAGE I NESTIGATIONS.-STILL I N PROGRESS

.:-; .-HJ CREEN

'~NNNN

~ W'w 3 r, ~ 2