ML20154F513

Forwards Safety Evaluation Re Util 880404 Request for Relief from ASME Boiler & Pressure Code,Section XI Inservice Insp Requirements for Essential Raw Cooling Water Piping.Relief Request Acceptable Provided Program Includes Listed Items

ML20154F513
Person / Time
Site:	Sequoyah
Issue date:	05/11/1988
From:	Hermann R NRC OFFICE OF SPECIAL PROJECTS
To:	White S TENNESSEE VALLEY AUTHORITY
Shared Package
ML20154F516	List: ML20154F513 ML20154F531
References
NUDOCS 8805230275
Download: ML20154F513 (2)

Text

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• NUCLEAR REGULATORY COMMISSION g ."

l WASHING TON, D. C. 20555

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Docket Nos. 50-327/328 l l

l Mr. S. A. White  !

Manager of Nucler.r Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattar.coga, Tennessee 37402-2801 l

Dear Mr. White:

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SUBJECT:

REQUEST FOR RELIEF FROM ASME BOILER AND PRESSURE VESSEL CODE, 1 SECTION XI, INSERVICE INSPECTION PROGRAM I i

The staff has reviewed Tennessee Valley Authority's (TVA) request for relief from certain American Society for Mechanical Engineers (ASME) Boiler and  :

Pressure Code,Section XI inservice inspection requirements for Essential Raw Cooling Water (ECRW) piping submitted by two letters both dated April 4, 1988 i and by a clarification letter dated May 4, 1988. This relief was initiated because by leaking occurred microbiologically inducedincorrosion the ERCW (MIC piping)in

. Sequoyah Units 1 and 2, caused The staff finds that the relief request is acceptable provided the program I includes the following additional items:

(1) The frequency of direct visual inspection of weld specific leaks is increased to monthly, and performed as scheduled, (2) at the same time leakage is detected, an essessment is made to ensure the acceptance criterion is not exceeded prior to the scheduled outage or repair, (3) the leakage from a leaking weld does not exceed 0.5 gpm and the total leakage '

from all welds does not exceed 2 gpm. The licensee will establish a threshold below which the leakage is considered imeasurable for the purpose of calculating the combined leakage. )

Ouring a May 6,1988 telephone conference call between R. Hermann of NRC and TVA management, TVA comitted to incorporate the three items specified above into their program by June 1, 1988.

A.ceptance of this relief request is conditional upon these three additional l items being included in the MIC Program. The basis for our conclusions is '

provided in the enclosed staff's Safety Evaluation.

The staff concludes that the Code repair requirements are im ractical to perform at Sequoyah and that pursuant to 10 CFR 50.55a(a)(3) i), the proposed alternatives to the described requirements will provide an acceptable  !

level of quality and safety. The staff also concludes that granting relief I where the Code requireroents are impractical is authorized by law and will not l endanger life or property, or the comon defense and security. The relief is  !

in the public interest giving due consideration to the burden that could result 8005230275 0G0511 PDR ADOCK 05000327

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upon Units 1 TVA andif2.theAccordingly, specific Code requirements pursuant were to 10 CFR imposed6)(i),

50.55a(g) up(on Sequoyah TVA Nuclear Plant, is granted the requested relief , on the conditions set forth above.

Sincerely, '

Robert A. Hermann, Acting Assistant Director for Projects TVA Projects Division Office of Special Projects

Enclosure:

Safety Evaluation cc w/ enclosure:

See next page Distribution Docket-File "u

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~~NRC PDR Local PDR i Projects Reading l S. Ebneter J. Axelrad i I S. Richardson  ;

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