ML20212N065

Final Deficiency Rept CDR 84-00-06 Re Components & Component Supports Spanning Expansion Joints.Initially Reported on 840405.Field Walkdown of All Bldgs Performed & Design Changes Issued to Assure Sys & Structure Integrity

ML20212N065
Person / Time
Site:	Seabrook
Issue date:	07/25/1986
From:	George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
CDR-84--6, CDR-84-00-06, SBN-1172, NUDOCS 8608280074
Download: ML20212N065 (3)

Text

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sg ff-Oo-oG h George S. Thomas Vice President-Nuclear Production July 25, 1986 Public hke of New We SBN- 1172 Niw Hampshire Yankee Division T.F. Q2.2.2 United States Nucacar Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. Richard W. Starostecki, Directo r Division of Project and Realdent Programs

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) Telecon of April 5,1984, A. L. Legendre, Jr. (YAEC) to J. Beall (NRC Region I)

(c) PSNH Letter (SBN-713), dated September 13, 1984, " Interim 10CFR50.55(e) Report; Components and Component Supports Spanning Expansion Joints", J. DeVincentis to R. W.

Staros te cki Subj ect : Final 10CFR50.55(e) Report; Components and Component Supports Spanning Expansion Joints (CDR 84-00-06)

Dear Sir:

In Reference (b), we reported a 10CTR50.55(e) deficiency regarding components and component supports which span expansion joints located in the Containment Building annular steel framing. The expansion joints serve to relieve thermal stresses applied to the annulus framing during plant operation. The original design of these components and component supports did not consider the additional stresses which could be applied due to the expansion joint movement.

We have completed the following corrective actions to assure that the integrity of the structures and systems is not adversely affected:

a) Performed field walkdown of all buildings to identif y areas where an expansion joint movement could af fect a component, component support, or the building steel.

b) Performed analysis to define those components or supports which are acceptable as designed.

8600280074 860725 .

PDR ADOCK 05000443 S PDR 1 67 5 i o P.O. Box 300. Seabrooh NH 03874 . Telephone (603) 474-9574

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14F United States Nuclear Regulatory Commission SBN-1172 Attention: Mr. Richard W. Starostecki Page 2 c) Issued design changes where it is expeditious to do so in lieu of extensive analysis to assura the integrity of the systems and structures.

. d) Instructed contractors and pre-construction walkdown crews such that any new installations vill meet the design requirements.

All modification 3 required fo: components spanning expansion joints have been completed. Expansion joint design information will be incorp-orated into New Hampshire Yankee Design Guides for future use. Therefore, this is considered our final report en this item.

Very truly yours,

' /  ;

-X/ Mc L- i .

George S. Thomac cc: Atomic Safety and Licensing Board Service List Director, Of fice of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 i

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