ML20039E941

Final Deficiency Rept Re Containment Spray Sys Pipe Supports,Initially Reported 810918.Supports Reviewed, Qualified & Redesigned Per Corrected Support Loads.Changes to Be Completed Prior to Power Ascension

ML20039E941
Person / Time
Site:	Diablo Canyon
Issue date:	12/22/1981
From:	Crane P PACIFIC GAS & ELECTRIC CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8201110637
Download: ML20039E941 (2)

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l Docket No. 50-275 l

. 50 55(e) Report PACIFIC G-AS AND ELECTR,IC C O M PANY

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. ... . .. .. . co m Mr. R. H. Engelken, Director \ Vg. ! ' f Office of Inspection and Enforcement '

/ 9-Region V .-

f U. S. Nuclear Regulatory Conmission /7 -

3 1450 Maria Lane, Suite 210 /

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Walnut Creek, CA 94596 PCe, . ,L

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/N Re: Docket 50-275 y c 3 Diablo Canyon Unit 1 'v '

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Containment Spray System Pipe Supports - -

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Dear Mr. Engelken:

This report supersedes that forwarded to you on the same subject on October 19, 1981.

On September 18, 1981, Mr. John Burdoin was notified by tele-phone of a deficiency reportable under 10 CFR 50.55(e). The report addressed recently discovered deficiencies in the design of the contain-ment spray system pipe supports located within containment.

Specifically, the following deficiencies have been identified:

1. Incorrect thermal analyses were used for hanger loads.

2. These analyses were performed with one snubber modeled as a rigid member.

3. Variable spring support settings were established utilizing deadload analysis with water; however, the springs were snt with the piping in the dry state. , c3 m

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4. In designing a pipe anchor, the loads from only ose sidev Th, were used. 5 #

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'O 8201110637 811222 PDR ADOCK 0500027]

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Mr. R. H. Engelken December 22, 1981 i

l New analyses were performed addressing all of the above items.

All supports were revicwed, qualified, or redesigned as dictated by the corrected support loads. As a result, two anchors require structural modification and other supports require minor changes. These changes

- will be completed prior to power ascension.

We reported these deficiencies on the assumption that an impact on safety existed. Since the design has been corrected and modifica-tions will be made prior to any possible impact on safety, we do not intend to make the extensive reanalysis required to determine if the 1 systems would have remained operational had these deficiencies remained undetected.

This is the final report on the subject.

Very truly yours, cc: Director

. Office of Inspection and Enforcement i O. S. Nuclear Regulatory Commission Washington, D. C. 20555 l

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