ML20150D264

Forwards Recent NRC Memos Re Problems Associated W/Pipe Support Base Plate Design Which Apply to Subj Facil.W/Encl ANO:7811020332,7811020343 & 7811020336

ML20150D264
Person / Time
Site:	Yellow Creek
Issue date:	11/14/1978
From:	Ketchen E NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To:	Kornblith L, Paris O, Smith I NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
References
NUDOCS 7812050091
Download: ML20150D264 (9)

Text

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gC pyELIC D November 14, 1978

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Ivan W. Smith, Esq. , Chairman Mr. Lester Kornblith Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Washington, D. C. 20555 Dr. Oscar H. Paris Atomic Safety and Licensing Board E U.S. Nuclear Regulatory Commission Washington, D. C. 20555 \

In the Matter of E jB N2' ~

TENNESSEE VALLEY AUTHORITY (Yellow Creek Nuclear Plant, Units 1 "& 2)$ ggya N[ge .

Docket Nos. 50-566 & 50-567 geydy** 3 b

Gentlemen: m Enclosed are recent memoranda discussing certain problems experienced in connection with pipe support base plate design. The NRR Staff has informed us that the problems discussed in Mr. Stello's memorandum dated September 28, 1978 are applicable to the Yellow Creek facility, and that DSS is presently reviewing this aspect of piping design analysis on a case-by-case basis under SRP section 3.9.3 - ASME Codes 1, 2 and 3 Components, Component Supports and Core Support Structures. If the Board or any of the parties wish additional information, please let us know.

Sincerely, k .i.,,.f :h'

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Edward G. Ketchen Counsel for NRC Staff l

Enclosures as Stated l cc (w/encls.):

Ira L. Myers, M.D.

Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Panel Docketing and Service Section Herbert S. Sanger, Jr. , Esq.

'- Honorable A. F. Summer Alton B. Cobb, M.D. .

William B. Hubbard, Esq. _

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r Milton J. Grossman, Hearing Division

• MEMORANDUM FOR:

Director and Chief Counsel, OELD FROM: Victor Stello, Jr,, Director Division of Operating Reactors, NRR -

SUBJECT:

BOARD NOTIFICATION - PIPE SUPPORT BASE PLATE DESIGN i

The attached memorandum ~.oger Mattson, dated June 28, 1978, presents information conc ning failures of safety-related pipe supports at Millstone 1 and design deficiencies on similar equip-ment at Shoreham Unit 1. As indicated in the attachment, two factors appeared to contribute to failure of anchor-bolt connec-tions of pipe supports, These are, 1) the design assumption that base plates perforn structurally as rigid load-bearing members when they may be flexible members, and 2) incorrect anchor bolt torquing.

Recent audits of Architectural Engineering firms and assessments of the actions taken at Millstone, as noted in the attachment, provided the following general information:

1. During the last few years, the A/Es have changed their design and installation procedures for concrete embedded pipe supports.

2. Past and current design and installation procedures vary among the A/Es,

3. In the past many of the pipe support designs have been con-tracted, and were done with methods not known by the principal A/Es.

We have concluded that the more detailed information required must be obtained from each operating facility, We are preparing a generic

Milton J. Grossman letter to each operating facili > requesting detailed design, installation, and testing inform > tion of concrete-embedded anchor-bolted pipe supports of safety-related equipment.

We recommend that this information be provided to the following Boards:

1. Monticello (FTL)

2. Indian Point 1,2,3 (Seismic Design)

We will provide an assessment of this issue upon completion of our evaluations. i

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Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation

Enclosure:

June 28,1978 memo, Stello to Mattson cc w/ enclosure:

D. Vassallo V. Stello R. Mattson R. Bevan L. 01shan

. L. Nichols l V. Noonan A. Schwencer T. Ippolito J. Fair

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MEMORANDUM FOR: B. K. Grimes, Assistant Director for Engineering and Projects, D0R '

D. G. Eisenhut, Assistant Director for Systems and Projects. 00R t

. FROM: Acitng Branch Chief, .

Engineering Branch, DDR ,

SUBJECT:

PIPE SUPPORT BASE PLATE PROBLEM The Engineering Branch, Division of Operating Reactors, has contacted Bechtel, Bergen - Paterson, Gilbert, and Stone & Webster in regard to their past and current design procedures for support base plates '

utilizing drilled anchor bolts. Bechtel and Stone & Webster indicated that they became aware of base plate flexibility effects on anchor bolt pull-out loads within the past couple of years and are now considering this in current designs. Gilbert and Bergen - Paterson indicated they are using rigid plate assumptions ,

for calculating bolt loads.

g Review of the support redesigns at Millstone shows a considerable increase in base plate thickness and anchor bolt sizes over the previous design. The original designs by Bergen - Paterson did not meet the current rigidity requirements used by Stone & Webster.

Design deficiency reports by Long Island Lighting Company on Shoreham show that consideration of base plate flexibility has increased the pull-out loads on some bolts, and inspection of the supports has shown that approximately 55 percent of the anchor bolts had incorrect embedment lengths.

Currently, I&E is considering whether Stone & Webster should be investigated for a Part 21 deviation and will be further investigating this matter.

The Engineering Branch considers the problem at Millstone where several support plates were pulled out to be a combination of base plate flexibility and anchor bolt design problems. Since the anchor bolts were never tested for cyclic loadings, and the lines at Millstone experienced flow induced vibrations, the capability of the anchor bolts to withstand cyclic loadings should be addressed, s

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f*.; h. K. Griacs .

D. G. Eisenhut

. 2-Based on the above infomation, the Engineering Branch recomends that this be considered a generic item for all operating plants, and a vendor inspection program be implemented with I&E to review the vendor design procedures used for analyzing support base plates ,

utilizing dHiled anchor bolts along with the field insta111ation procedures utilized in installing the anchor bolts. Also, the load rating techniques used by the anchor bolt manufacturers for cyclic ,

loadings should be reviewed. The Engineering Branch has talked with I&E and consider the vendor inspection program to be the most efficient method of completing the necessary review. The Engineering Branch estimates approximately 15 man-weeks will be required to review design procedures used by vendors and A/E firms. The

• Engineering Branch will set up a meeting with both AD's to detemine the interface between the Engineering Branch and I&E required to implement the review.

The Engineering Branch is in the process of preparing a feedback' memo to DSS on the base plate problem which is expected to be completed by June 9,1978.

AtisichkPl p 4 W V. S. floonan, Acting Branch Chief Engineering Branch Division of Operating Reactors ce: V. Stello, Jr., DOR W. Rutherford IE U. Potopous IE l

R. }iattson, DSS J. P. Vaight, DSS l R. Dosnak, DSS

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MEMORANDUM FOR: R. J. Mattson, Director .

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Division of Systems Safety FROM: Victor Stello, Jr., Director Division of Operating Reactors

SUBJECT:

OPERATING EXPERIENCE MEMORANDUM NO. 13 PIPE SUPPORT BASE PLATE PROBLEM PROBLb' Recently a ci' inservice inspections at Millstone Unit 1, structural failures of rh,,id pipe supports for class 2 safety equipment were observed. These inspections, recently implemented at Millstone, were conducted in accordance with Section XI of the ASME Code, as endorsed by regulation,10 CFR 50.55 a(g), in February 1976.

Several base-plate anchor bolts of pipe supports in the Core Spray and the Low Pressure Coolant Injection Systems at Millstone were not properly embedded; and, in some cases the anchor bolts were completely pulled out and no supporting function was provided.

Deficiency reports, in accordance with 10 CFR 50.55(e), filed by Long Island Lighting Company, on Shoreham Unit 1, indicate that design of base plates with drilled anchor bolts using rigid plate assumptions has resulted in underestimation of loads on some anchor bolts. Inspection of anchor bolt installetions at Shoreham has shown over fifty percent of the bolt installations were deficient. Supports for both piping systems and electrical raceways have been reported as deficient at Shoreham. ,

PRESUMED CAUSE 1

It is currently believed that two interacting factors contribute to the failure of the supports. First, the design assumption that the base plates perform structurally as rigid instead of flexible members may provide low estimates of imposed loads on the supports.

Secondly, incorrect anchor bolt embedment may also contribute to insufficient support.

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) The attached memoraridum from V. Noonan to B. Grimes, dated i June 2, 1978, provides additional information.

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1 SAFETY SIGNIFICANCE Depending on equipment layout, improperly designed or installed anchor supports could:

1. result in loss of support function in some cases; and,

2. result in high stressing of piping systems during a seismic event or during a significant flow transient.

REPAIR Millstone with assistance from Teledyne Engineering has completed design modifications and repairs. These changes include increased base plate thickness and larger anchor bolts for failed supports Shoreham in conjunction with Stone and Webster is evaluating both piping and electrical type supports. The review is scheduled to be completed by December, 1978.

00R ACTION

< 1he Engineering Branch will review the design procedures used on operating plants to determine anchor bolt loads, the techniques used to determine load ratings for anchor bolts, and the installation procedures.

This review will be done through an A/E vendor inspection audit in conjunction with IE. These A/E audits will be started during early July, 1978.

We anticipate that criteria will be developed for design and installation of base plate-anchor bolt assemblies, and those operating plants requiring corrective action will be identified.

f Additionally EB staff will further assess the occurrence and corre'ctive actions taken at Millstone.

RECOMMEt!DATIONS We recommend that this problem be addressed on all CP and OL reviews.

At this time it appears that considerations should be given to the analytical methods used to determine whether or not base plates behave as flexible or rigid members. This in turn may effect the anchor bolt size and embedcent to properly copa with loads imposed on the supports.

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It may be appropriate to require that applicants provide for review their: ,

1. methods for determining base plate thickness and anchor bolt loads;

2. criteria for anchor bolt installation; and,

3. criteria for load rating techniques for anchor bolts, including cyclic loads.

We shall coordinate our meetings, discussions and evaluations of this issue with your staff. Supplemental information will be provided.

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') 1 Vic' tor Stello, Jr., Director Division of Operating Reactors PRINCIPAL D0R PERSONNEL Reviewer: J. Fair

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Enclosure:

Memorandum dated 6/2/78 cc: w/ enclosure E. G. Case S. Hanauer R. S. Boyd H. R. Denton F. Schroeder DSS AD's DDR AD's D0R BC's 00R SL's J. Fair l

W . Nichols t W. Rutherford

J. Sniczek l

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