ML20086C506

Interim Deficiency Rept Re Missing Gusset Plates for Steam Generator.Initially Reported 740401-02.Investigation Conducted & Only Three Areas Found to Require Further Investigation.Welds Repaired

ML20086C506
Person / Time
Site:	Salem
Issue date:	05/22/1974
From:	Betz J Public Service Enterprise Group
To:	Knuth D US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20086C505	List: ML20086C506
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8311280097
Download: ML20086C506 (3)

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. . j-John F. Betz Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 91/622-7000 Vice-President - Electnc Operation <

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U. S. Atomic Energy Commission '

Directorate of Regulatory Operations ,

j 7920 Norfolk Avenue-Bethesda, Maryland 20014 Attention of Mr. Donald F. Knuth, Director Gentlemen:

STEAM GENERATOR SUPPORTS NO. 1 AND 2 UNITS SALEM NUCLEAR GENERATING STATION DOCKETS NO. 50-272 AND 50-311 In compliance with AEC Regulation 10CFR50.55(e),-submitted herewith is an analysis and rep ~ ort related to missing gusset f(

plates on No. 1 and 2 Units, Salem Nuclear-Generating Station r steam generator supports. This item was made known to two Region 1 Field Inspectors who were' at the site on April 1-2, 1974. The detail analysis and report was submitted to DRO, Region 1 in answer to their _ inspect" ion of April 1-2, 1974.

Our analysis has shown that had this nonconformance not been discovered, the omission of the subject gdsset plates would

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4 not have-adversely affected the safety,of operations of the nuclear power plant at any time throughout the expected lifetime , e of the plant. The following is the analysis of our investigatiot

, which was requested by DRO, Region 1.as a possible generic problem.in steam generator supports.

The steam generator. supports for Salem Nuclear Generating Station were fabricated by the~ Sun Shipbuilding and Drydock Company. During your site visit of. January 16-18;"1974, 4 concern was expressed about these supports as related to the '

welding of supports of a Westinghouse design fabricated by }.

Sun Shipbuilding and Drydock Company'for other utilities. 'J-

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.In compliance with this verbal'comsent,'PSE&G initiated a- ,.

program to re-examine these supports 'for: any possible welding defects. Ten -areas of weld were ' selected at random ~ onl each ofie the'eight steam generator;suppo'rts. After~the paint was-

• removed, each area was visually inspected and subjected to a i magnetic particle examination. . Of the 480 areas examined, only

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. three.were thought to require further investigation. The results of_the detdlled examinition",of these areas as part

- of this investigation are-as follows:

f ../ Support No, li t - Test Area 11- BB- 10 . The

, indication appfared to be a lack of fusion

/ and was ground-out, to a depth of 3/16-inch

- before all indicationy disappeared.

, Support No. 12 - Test hrea 12- S l- 4 . Upon f

. close examination, this indication proved

^ to be a tool or machine mark in the bas'c

' metal and required no repair.

Support No. 24 - Te st Area 24-8B-lO.

Indications showed a cold lap in the base e material which was removed by grinding cut the material to a depth of 1/8-inch.

The repair velding required,on.the above areas will be done in accordance with Public Service' Electric and Gas Conpany's General Specification No. 70-5050; Detail Specification C-4.

In the course of the inspe~ction of the supports it was found that on six of the eight supports, gusset plates located behind the large reinforcing plates had been omitted during fabrication.

Because of space limitation, it would be almost impossible to install these gusset plates in their original location at this

' time . We have reviewed the design and find that the function of the gusset plates is secondary; we will, however, install an equivalent plate on the faces of the large reinforcing plates which will adequately compensate for the missing gusset plates.

Our design drawings are being revised to show this change for supports No. 13, 14, 21, 22, 23 and 24.

The welding of the steam gene rator supports was done in accordance with AWS Sp*ecification D2.0-69 which does not make stress relieving mandatory. For dimensional stability, our specification called for the assemblies to betstr'ess relieved in the shop after all shop welding had been completed. The repair welding previously done in the field was in accordance with the AWS specification and no stress relieving was specified, as the small areas to be welded would have no affect on the dimensional stability of the assembly.

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U.S. Atomic Energy 5-22-74 Commission During the field inspection of April 1-2, 1974, a visual inspec-tion was made by AEC inspectors of Steam Generator Support No. 11.

Eleven areas were noted by the inspectors as not meeting AWS Specification D2.0-69 in some respect. PSE&G is reviewing these areas and upon evaluation will make any repairs to the welds, if required.

In order to ascure the soundness of full penetration welds, our Specification 69-7031 for these supports calls for magnetic particle testing for the full length of the seam at four different depths as the weld metal was built up. The vendor's surveillance report states that these magnetic particle tests were performed satisfactorily. PSE&G is satisfied that the. welds are sound and we plan no further non-destructive testing.

Detail Rnecification 69-7031, Paragraph 12, requires that after fabrication of the supports, completed welds are to be ultra-sonically tested. This was deleted by our Purchase Order No. E-157603 Also, Change Order No. 1 to the order required that steel plate subject to transverse loading would be ultra-sonically tested. We have clarified the above items in Addendum No. 2 to our specification.

After reviewing the results of our weld test program where 80 areas were selected at random for testing and finding only three areas where indications showed relatively minor deficiencies, we are convinced that the welding on thecc supports is structurally sound. We have assured ourselves by reviewing the design of these supports that they will perform their function under both operating and loss of coolant accident conditions.

If you have further questions, we will be pleased to discuss them with you and further invite your inspection of the fiel records covering this work item.

Very truly yours,

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CC Mr. James P. O'Reilly King of Prussia, Pa.

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