ML20009G108

RO 2-84-55:anchor Bolt Testing Required by IE Bulletin 79-02 Not Performed on Control Rod Drive Piping.Caused by Unusual Arrangements for Installation of Piping.Anchor Bolt Repairs & as-built Verifications Table Done

ML20009G108
Person / Time
Site:	Brunswick
Issue date:	07/29/1981
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEP-80-1263, IEB-79-02, IEB-79-2, IEB-80-17, RO-2-80-55, NUDOCS 8108030334
Download: ML20009G108 (2)

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Brunswick Steam Electric Plant P. O. Box 10429 Southport, N. C. 28461 July 29, 1980

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Mr. James P. O'Ref.Ily, Director d

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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS D /6 ff LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324 CONFIRMA110N FACSIMILE FOR AN IMMEDIATELY REPORTABLE EVENT (2-1.

J Deer Mr. O'Reilly:

This facsimile confirms the conversation between Mr. A, C. Tollison, Jr., General i Plant Manager, Mr. Jerry Waldorf, NPPED Resident Engineer, Mr. E. A. Bishop, Plar.: Project Engineer, Mr. M. J. Pastva, Jr., Regulatory Technician and Mr. Leo Modinas. Mr. Al Herdt, and Mr. Paul Kellog of your office at 1515 on July 28, 1980.

As a result of Carolina Power & Light Company's review of CRD piping in conjunctf on 1

I with IE Bulletin 80-17 concerns, it has been determined that anchor bolt testing as, required by IE Bulletin 79-02 had not been performed on the CRD piping designed 4 and installed tv Reactor Controls lac.

g This is apparently due to the unusual arrangements made to have this piping

( installed as compared to the remainder of all other safety-related piping at the s Brunswick units. Specifically, all other piping was designed by either United Engineers and Constructcrs, the plant A/E, or General Electric, NSSS supplier.

All piping designed by either of these two sources was installed by the plant constructor, Brown and Root, Inc. The CRD piping, however, was designed and Inc.

installed by Reactor Controls, Inc. under subcontract to Brown and Root, Consequently, during the review of safety-related piping to be considered for anchor bolt testing, which was performed for CP&L by United Engineers' and Con-structors, this piping was overlooked.

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i Mr. James P. O'Reilly July 29, 1980 inchor bolts are currently being tested on both units in accordance with approved procedures.' Because of an unusually high rejection rate, the acceptance criteria for the anchor bolt plates has been upgraded to require that all anchor bolts on each plate successfully pass before the anchor plate is accepted. This change was applied conservatively due to the high failure rate (approximately 90 percent) being found on this piping. The 90 percent failure rate compares to a failure rate of about 5 percent for the anchors installed by Brown and Root, Inc. The

. primary reasons for rejection of anchor bolts are related to improper anchor length and thread engagement with the majority of the, bolts passing the torgue test which simulates a tension load on the anchor.

Carolina Power & Light Company has additionally determined that the CRD piping supplied by Reactor Controls, Inc. has not received an as-built walkoff within the 12 months prior to issuance of IE Bulletin 79-14 and thus doec not meet the requirements of the Bulletin 79-14. Therefore, verifications as required by this bulletin are currently teing performed for both units. Records from Reactor Controls, Inc. do, however, document that the seismic analysis has been reconciled with as-built drawings obtained immediately following installation. Review of analysis techniques used by Reactor Controls, Inc. has verified that the square root of the sum of the squares was used in the seismic analysis rather than the algebraic summation method.

Carolina Power & Light Company will complete all anchor bolt repairs and as-built verifications on piping essential to safe shutdown prior to startup of each unit.

Completion of anchor bolt repairs and as-built verifications of piping not related to safe shutdown will be completed within 7 days following reactor startup on each unit.

This event is being reported under Technical Specification 6.9.1.81.

Very truly yours, l

A. C. Tollison, Jr., General Manager Brunswick Steam Electric Plant MJP/bd cc: Mr. R. A. Hartfield Mr. V. Stello Mr. E. L. Zebroski y- -- , ,, - - - - - - . - - - - - -w,,-v , ,.- vv- * ,- , , - - -