ML20062E665
| ML20062E665 | |
| Person / Time | |
|---|---|
| Site: | 05000516, 05000517 |
| Issue date: | 11/16/1978 |
| From: | Bordenick B NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Johnson W, Salzman R, Sharfman J NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP) |
| References | |
| NUDOCS 7812110221 | |
| Download: ML20062E665 (8) | |
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- Jerome E. Sharfman, Esq., Chairman W. Reed Johnson Atomic Safety and Licensing Appeal Atomic Safety and Licensing Appeal Board Board U.S. Nuclear Regulatory Comission '
U.S. Nuclear Regulatory Comission Washington, D. C. 20555 Washington, D. C. 20555 Richard S. Salzman, Esq. Atomic Safety and Licensing Appeal Board hkjj, e r, U.S. Nuclear Regulatory Comission j <,! 4 _ Washington, D. C. 20555 y _. Y~ s-
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In the Matter of . E V,1 ' 2 LONG ISLAND ly=J' .TIJ* G COMPANY t ?? (Jamesport Nuclear P,cwer Stahion, Units 1 & 2)Y.'s:- -Y- e9' Docket Nos? 50-516 & 50-517 V:)y Gentlemen: - Q N o..' Enclosed are recent memoranda discussing certain problems experienced in connection with pipe support base plate design. The Nuclear Reactor Regulation staff has infonned us that the problems discussed in Mr. Stello's memorandum dated September 28, 1978 are applicable to the proposed Jamesport facility, and that the Division of Systems Safety is presently reviewing this aspect of piping design analysis on a case-by-case basis unde ~r 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, r -
,M ernard M. Bordenick Counsel for NRC Staff Enclosure as Stated cc (w/encls.):
Sheldon J. Wolfe, Esq. Dr. Harris Fischer Ira Lee Zebrak, Mr. Ralph S. Decker Irving Like, Esq. Dr. Arthur Tampi Dr. E. Leonard Cheatum Mrs. Laetitia deK. Bradley Jeffrey Cahen, E. Edward J. Walsh, Jr. , Esq. Ms. Shirley L. Bachrach W. Taylor Reveiey, III, Esq. Ms. Adelaide Flatau Mr. A. E. Kintigh William C. Chapek Environmental Protection and Joseph C. Gramer, Esq. Progress Committee Carl G. Dworkin, Esq. Dr. Caryl R. Granttnam Frederick H. Lawrence, Esq. Ms. Jean H. Tiedke Atomic Safety & Licensing Appeal Panel 7g ocketin and Service Section Atomic Safety & Licensing Soard Panel
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MEMORANDUM FOR: Milton J. Grossman, Hearing Division b Director and Chief Counsel, OELD
% v FROM: Victor Stello, Jr. , Director Division of Operating Reactors. NRR -
SUBJECT:
BOARD NOTIFICATION - PIPE SUPPORT BASE PLATE DESIGN s The attached memorandum to Roger Mattson, dated June 28, 1978, presents information concerning 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 perform 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
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e , Milton J. Grossman letter to each operating facility requesting detailed design, installation, and testing information 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. .
r' (~. c,j e . .. 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 V. Noonan A. Schwencer T. Ippolito -
J. Fair [ I
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h ,,, MEMORANDUM FOR: B. X. Grimes, Assistant Director for Engineering and Projects, DOR 8,, \ WI k '
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D. G. Eisenhut, Assistant Director - for Systems and Projects, DOR g\CN a
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Acitng Branch Chief, p#a%M
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Engineering Branch, DOR b SUBbCT: PIPE SijPPORT BASE PLATE PROBLEM % y . The Engineering Sranch, 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 couole of years and are now considering this in current designs. C:7 cert and Bergen - Paterson indicated they are using rigid plate assumptions fo: calculating bolt loads. g Review of the support redesigns at Millstone shows a considerable increase in basr plate thickness and anchor bolt sizes over the previous design. The original designs by Bergen - Paterson did not meet the current rigidity recuirements 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 inspectio'n 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 ccmcination of base plate flexibility and anchor bolt design ::roblems. Since the anchor bolts were never tested for cyclic loacings, and the lines at Millstone experienced flow induced vibrations, the capability of the anchor bolts to withstand cyclic leadings should be addressed.
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",. K. Grimes D. G. Eisenhut -
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Based on the above information, 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 derign procedures used for analyzing support base plates . utilizing drilled 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-weks will be required to review design procedures used by vendors and A/E fims. The ' Engineering Branch will set up a meeting with both AD's to determine the interface between the Engineering Branch and I&E required to implement the review. The Engineering Branch is in the process of pnparing a feedback' memo to DSS on the base plate problem which is expected to be completed
'by June 9,1978.
gtisisisJs:6.EZ.i V. S. Noonan, Acting Branch Chief Engineering Branch Division of Operating Reac+4rs
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ce: V. Stello, Jr. DOR W. Rutherford, IE U. Potopeus IE R. Mattson, DSS J. P. Knight, DSS R. Bosnak, DSS
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4 MEMORANDUM FOR: R. J. Mat.tson, Director 11 4Y s, Division of Systems Safety
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FROM: Victor Stello, Jr., Director c'p"g>J / Division of Operating Reactors b y w s~ ]n
SUBJECT:
OPERATING EXPERIENCE MEMORANDUM NO. 13 PIPE SUPPORT BASE PLATE PROBLEM PROBLEM i Recently during inservice inspections at Millstone Unit 1, structural failures of rigid 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 Injectior 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 Ccepany, 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 installations 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 . 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 icw estimates of imposed loads on the supports. Secondly, incorrect anchor bolt embedment may also contribute to insufficient support. The attached memorandum from V. Noonan to B. Grimes, dated June 2,1978, provices additional information. o
. -{ t SAFETY SIGNIFICANCE Depending on equipment layout, improperly designed or installed anchor supports could: <
- l. re.sult 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 e 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 complete'd by December, 1978. 00R ACTION The 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 con,iunction 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.
- Additionally EB staff will further assess the occurrence and .
corre'ctive actions taken at Millstone. REC 05.E!!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 f'.cxible or rigid members. This in turn may effect the ancher bolt sire and embedment to properly copa with loads imposed on the supports. _= . .. i
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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' Vic' tor Stello, Jr., Director Division of Operating Reactors PRINCIPAL DOR PERSONNEL Reviewer: J. Fair l
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 DOR AD's
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DOR BC's DOR SL's J. Fair
'-1'. Nichols W. Rutherford .
J. Sniezek
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