ML19350A672

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Forwards IE Info Notice 81-04, Cracking in Main Steam Lines. No Response Required
ML19350A672
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 02/27/1981
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Gary R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
References
NUDOCS 8103160631
Download: ML19350A672 (1)


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611 RYAN PLAZA DRIVE. SUITE 1000 ARLINGTON. TEXAS 76011 State February 27,198)

Docket Nos.

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ATTN: Mr. R. J. Gary, Executive Vice Z

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Gentlemen:

This IE Information Notice is provided as an early notification of a possibly significant matter and it is expected that recipients will review the informa-mation for possible applicability to their facilities.

No response is requested at this time.

If further NRC evaluations so indicate, an IE Circular or Sulletin will be issued to further reccmend or recuest soecific licensee actions.

If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

Sincerely,

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Karl V. Seyfrit / /

Director

Enclosures:

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IE Information Notice No. 81-04 2.

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Page 1 cf 2 CF./-CKI.93 IN FAIN STEM LINE5 Descri: tion of Circunstances:

The Vitginir. Electric ?c-er COz:any ;rce tiy nctifiec ne NRC en Fe:ruary 23, 1951 that a raciogra:ny exaninatien, curing tre eng:ing stein generater re:lacenent cutage at Surry Unit 1, hac revealed a lengtny cr.tek incica:ica in :ne I.D. counter: re area of a -elcaen: en :ne in-line "T' fitting.nicn

nnects the vertical run of 30-inct : icing :: :ne safety relief valve nea:er and 30-inen sain stets line of 5:ean Genera:Or *A."

This ci ing ::nnecticn is 1ccated cuisice tne contain=ent :enetration imeeciately c:streas cf :ne

=ain steam isciatien valve as she-n in tre atta:nec sketen.

A visual and eye :enetrant examina:10n en :ne pi:e 1.0. surface Of tne.elesen:

nearest tne containment penetratien esta liste: na: ne cracking exte.:ec accut 120 F arcunc One fitting : enter cre :etween :ne a c'cleck to 5 c'cle:k pcsition.

Cracking was else caserved in :ne wel: :unter:cre at tre c::: site end of the T-fitting curing visual examinatien of :ne = icing intericr.

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gra:nic exasinatien of "B" anc "C" sain steam line T-fitting weics ciscl sec crack indications at similar locaticas.

Metallurgical s;ecinens of tne cracking -ere tre:annec fren One T-fitting of the "A" sain steam line for analysis.

Centrolled excavatien and ce:tn

easuresents of the crack at its =ic-leng:n indicated a crack ce:ta of ateut 0.090" in tnis locatica.

The cause of cracking nas not yet :een estariisted.

VE?CO nas lannec an ultrasonic exaninatica of similar *ei:nents in Surry Uni-2 sain steam lines utilizing "Het ? icing" ultrasonic tecnnicues.

re
ara-ions are als: eing race te riltrasenic exanine si=ilar.elc ents at Nortn Anna Uni 1,

currently in colc snu :.n fer refueling.

Rect encatien :0 Licensees:

Inis infernatien is crevicec as an early notifica:ica Of a significant safety satter tna is s-ill un er review :y ne NRC staff.

It is ex:ectec ina reci ients '=ill revie='* e inf r2ation fOr ::ssible a:Olica ility *: neir clants.

For tnese :lants naving sinilar sain stein line C:nfigurati:Os ani0n are currently in a refceling er extenrec re: air Outage, it is ree:rcencec na a ultras:nic anc/cr raciegra:nic exanination cf ne inree weies anc

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IN 81-04 February 27, 1981 Page 2 of 2 No response to this notice is requested at this time.

If you have ny questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

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IE Information Notice No. 81-04 February 27, 1981 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.

Issued 80-41 Failusa of Swing Check 11/10/80 All power reactor Valve in the Decay Heat facilities with an Operating Removal System at Davis-License (0L) or Construction Besse Unit No. 1 Permit (CP) 80-42 Effect of Radiation 11/24/80 All power reactor on Hydraulic Snubber Fluid facilities with an Operating License (OL) or Construction Permit (CP) 80-43 Failures of the Continuous 12/5/80 All power reactor Water Level Monitor for facilities with an the Scram Discharge Volume Operating License (OL) at Dresden Unit No. 2 or Construction Permit (CP) 80-44 Actuation of ECCS in the 12/16/80 All power reactor Recirculation Mode While facilities with an in Hot Shutdown Operating License (OL) or Construction Permit (CP) 80-45 Potential Failure of 12/17/80 All pressurized water BWR Backup Manual Scram reactor facilities with Capability an Operating License (0L)

Construction Permit (CP) 81-01 Possible Failures of 1/16/81 All power reactor facilities General Electric Type with an Operating License HFA Relays (OL) Construc+, ion Permit (CP) 81-02 Transportation of 1/23/81 All Radiography licensees Radiography Devices 81-03 Checklist for Licensees 2/12/81 All power reactor Making Notifications of facilities with an Significant Events in Operating License (OL)

Accordance with 10 CFR Part 50.72 Enclosure