ML18031A260

Submits Interim Rept Re Deficiency in Pipe Support Design Drawings Released for Fabrication & Installation.All Safety Implications Are Unknown.Estimated That 1,000 Pipe Supports May Require Design Changes

ML18031A260
Person / Time
Site:	Susquehanna
Issue date:	09/05/1979
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 7909140290
Download: ML18031A260 (4)

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ACCESSION NOR:7909140290

.D(jC ~ DATF: 79/09/05 NOTAHlZED:

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',DOCKET FACI 'squehanna'Steatii Electri,c Station<

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RECIP ~ NAb!E

'ECIPIENl'FFILIAi'ION

'GR IEH pH ~ H, Region ii Philadelphian Office of the Dire'ctor SUVJEC1:

Submi ts interim rept re deficiency in. pipe Support design drawings'eleased for fabricati.on 8, installation,A11 safety implications unKnownihowever.best estimate is l>000 pipe sUpports may require design changes.

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0 PpaL TWO NORTH NINTH STREET ALLENTOWN PA 18101 PHONE. (2I5) 82\\.5151 NORMAN W. CURTIS Vice President.Eng'neering 8 Construction

'21-5381 September 5, 197 9 Mx. Boyce H. Grier Director, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 SUSQUEHANNA STEAM ELECTRIC STATION INTERIM REPORT OF A DEFICIENCY IN PIPE SUPPORT DESIGN DRAWINGS RELEASED FOR FABRICATION AND INSTALLATION ERs 100450/100508 FILE 840-4 PLA-391

Dear Mr. Grier:

T?es serves to confirm 'nformat'on provided to R. Gallo, NRC, Reactor Inspector hy A. R. Sabol,, PP&L, on August 2, 1979 regarding the sub)ect deficiency which is deemed reportable under 10 CFR 50 '5(e)

~

The deficiency involves discrepancies between the Bechtel Plant Design.Group's finalized stress analyses calculations and the 'loads which were used in the design of pipe support detail drawings which were fabricated and released for installation during the construction of the plant.

The released pipe support.

detail drawings did not have factored into them revised piping system stress values whichhad been developed subsequent to the initial piping system stress calculations.

Allof the safety implications are not known at this time; however, our best estimate is that there will be approximately 1000 pipe supports which may require design changes.

Had the deficiencies gone undetected, it is. anticipated that some supports could have been overstressed beyond allowable design 1fmits by an order of 100 percent or greater.

The condition was first detected by Bechtel engineering personnel during preparations'or piping systems stress walkdowns in the first quarter of 1979.

At that time, a review performed on the basis of a random sample indicated that the problem was not generic or widespread.

The problem appear ed to have been confined to calculations which had been perfozmed prior to mid-1976 and subse-cgxently revised.

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~@~>NAY DOCKEt FILE trot l PENNSYLVANIA POWER 4

LIGHT COPAPANY

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Mr. Boyce H. Grier.

September 5, 1979 Subsequently, in preparation for turnover of the feedwater system 'to startup, a relatively large number of pipe support details, approximately 40 out of

"'276, which were found to be discrepant.

Therefore, in order to facilitate as orderly and complete as possible turnover of systems for startup, a

thorough verification program has been i.nstituted.

The verification program, which instituted following discovery of the condition, will cover all force, moment calculations and their related pipe support details.

On July 25>

1979,, Bechtel QA identified the condition in -its MCAR-1-36 requesting that Bechtel engineering evaluate the conditi.on for reportability.

Based upon Bechtel engineering's conclusion that the condition is reportable, a final report to MCAR-1-36 will be submitt'ed to PPaL by December 28, 1979.'ollowing, PPaL'will'ubmit its final report of said deficiency to the Commission by March 1, 1980; Very truly yours, N. W. Curtis Vice President-Eng'neering a Construction

>M:mcb

'cc:

Mr. Robert M. Gallo

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U. S. Nuclear Reguiatory Commission P

0 Box 52 S

c hi kshxnny, Pennsylvania 18655 Mr. Victor Stello (15)

Director-Office of Inspection S Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Mr. G. McDonald Office of Management Information a Program Contr'ol U. S. Nuclear Regulatory Commission Washington, D.C.

'20555