ML19330B468

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RO 2-80-55,confirming 800728 Conversation W/Nrc:As Result of Review of Control Rod Drive Piping in Conjunction W/Ie Bulletin 80-17,determined That Anchor Bolt Testing Per IE Bulletin 79-02 Was Not Done
ML19330B468
Person / Time
Site: Brunswick  
Issue date: 07/29/1980
From: Tollison A
CAROLINA POWER & LIGHT CO.
To:
References
IEB-79-02, IEB-79-2, IEB-80-17, NUDOCS 8008040057
Download: ML19330B468 (2)


Text

{{#Wiki_filter:. e ~ C90!A Carolina Power & Light Company Brunswick Steam Electric Plant P. O. Box 10429 Southport, N. C. 28461 July 29, 1980 FILE: B09-13516 SERIAL: BSEP/80-1263 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 BRUNSWICK STEAM ELE GtIC PLANT, UNIT NOS. 1 & 2 LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324 CONFIRMATION FACSIMILE FOR AN IMMEDIATELY REPORTABLE EVENT (2-80-55)

Dear Mr. O'Reilly:

This facsimile confir=s the conversation between Mr. A. C. Tollison, Jr., General Plant Manager, Mr. Jerry Waldorf, NPPED Resident Engineer, Mr. E. A. Bishop, Plant Proj ect 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 conjunction with IE Bulletin 80-17 concerns, it has been determined that anchor bolt testing as required by IE Bulletin 79-02 hcd not been performed on the CRD piping designed and installed by Reactor Controls Inc. 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 Brunswick units. Specifically, all other piping was designed by either United Engineers and Constructors, 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 installed by Reactor Controls, Inc. under subcontract to Brown and Root, Inc. 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. T }0 800804,9 9

Mr. James P. O'Reilly July 29, 1980 Anchor 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 percen't 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 79-1.4 and thus does not meet the requirements of the Bulletin 79-14. Therefore, verifications as required by this bulletin are currently being performed for both units. Records from Reactor Controls, Inc. do, however, document that the seismic analysis has been reconciled with as-built drawings obtained is=ediately following installation. Review of analysis techniques used by Reactor Controls, Inc. has verified that the square i 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, A. C. Tollison, Jr., General Manager Brunswick Steam Electric Plant MJP/bd cc: Mr. R. A. Hartfield Mr. V. Stello Mr. E. L. Zebroski =}}