ML19224A284
| ML19224A284 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/14/1978 |
| From: | Mcgurren H NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Johnson W, Rosenthal A, Sharfman J NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP) |
| References | |
| NUDOCS 7812050090 | |
| Download: ML19224A284 (9) | |
Text
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November 14, 1978
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Alan S. Rosenthal, Esq., Cnairman Dr. W. Reed Johnson, Member Atomic Safety and Licensing Appeal Atomic Safety and Licensing Appeal Panel Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Washington, D. C.
20555 Jerome E. Sharfman, Esq., Member Atomic Safety and Licensing Appeal Panel U.S. Nuclear Regulatory Commission Washing ton, D. C. 20555 In the Matter of Metropolitan Edison Company, et al.
(Three Mile Island Nuclear Station. Unit 2)
Docket No. 50-320 Gentlemen:
Enclosed are recent memoranda discussing ce-tain 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 Three Mile Island Unit 2 facility, and that DSS is pres-ently reviewing this aspect of piping design arulysis en a case-by-case basis under SRP section 3.9.3 - ASME 1, 2 and I Components, Component Supports and Core Support Structures. If the Board desires additional information, please let us know.
Sincerely, Henry J. McGurren Counsel for NRC Staff
Enclosure:
Memo 9/28/78 Stello to Groce=n (w/encls)
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.NRC FORM 313 (9-76) NRCM 0240 esm.ee orrica, iere - ass.424
. cc w/ enclosure:
Edward Luton, Esq.
Ms. Judith H. Johnsrud Mr. Gustave A. Linenberger Atcmic Safety and Licensin;;
George F. Trowbridge, Esq.
Board Panel Dr. Ern est O. Salo Atomic Safety and Licensing Dr. Chauncey R. Kepford Appeal Panel Karin W. Carter. Esq.
Docketing and Service Section DISTRIBUTION:
HJMcGurren SATreby HShapar TEngelhardt HSilver Rm - 116C - Phillips SVar -p Rm - 13 C - Phillips JNorris - EF WRegan - EP HSmith Rm - 314 - Philhps DVass allo Rm 110 - Phillips NRC Central File LPDR ELD FF (2)
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11/.d /78 NRC FORM 318 (9 76) NRCM 0240 W u. e. sovs omm awv pointine oprican s en - one.eu
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LEP : 3 ;34 MEMORA"DUM FOR: Milton J. Grossmcn, Hearing Division Director and Chief Counsel, CELD FROM:
Victor Stello, Jr., Director Division of Operating Reactors, NRR
SUBJECT:
BOARD NOTIFICATION - PIPE SUPPCRT BASE PLATE DESIGN The attached memorandum to Roger "attson, 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 atccchment, two
, actors appeared to contribute to failure of anchor-bolt cor.nec-tiens of pipe supports. These ace, 1) the design assumption that base plates perform structurally as rigid load-bearing numbers when they may be flexible men.bers, and 2) incorrect
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anchor bolt torquing.
Recent audits of Architectural Engineering firms and assessments of the actions taken at Millstone, as noted in the attachment, provided the folicwing general informaticn:
1.
During the last few years, the A/Es have changed their design and installaticn procedures for concrete embedded pipe supports.
2.
Past and current design and installation procedures vary crong the A/Es.
3 In the past many of the pice support designs have been con-tracted, and were done with methods not kncwn by the principal A/Es.
We have concluded that the more detailed informaticn required must be obtained frcm each ocerating facility.
We are preparing a generic T
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letter to each operating facility requesting detailed design, installaticn, and testing infor ation of concrete-entedded anchor-bolted pipe supports of safety-related equipment.
We recorend that this inrormation be provided to the following Boards:
1.
Monticello (FTL) 2.
Indian Point 1,2,3 (Seismic Design)
We will provide an assessrent of this issue upon completion of our evaluations.
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- m Victor Stella, Jr., Director Division of Operating I'eactors Office of I'uclear neactor Regulation
Enclosure:
June 28, 1973 memo, Steilo to Mattson cc w/ enclosure:
D. Vassallo V. Stello R. Mattson R. Bevan L. Olshan L. Nichols V. Noonan A. Schwencer T. Ippolito J. Fair 9
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R. J. lattson, Director Division of Systems Safety FRCM:
Victor Stello, Jr., Director Di'.'ision of Operating Reactors
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Recently during inservice inspections at Millstone Unit 1, structural failures of rigid pice supports for class 2 safety ecuipment s.ere observed. These inspections, recently it.plemantad at "ilisty.e, were ccnducted in accordance with Secticn,XI, of the ASME Ccde, as en,orse, uy regulcticn, 10 c, u.co u gj, in reyruary bn--/a.
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Several base-plate anchor bolts of pipe supports in the Ccre Spray and the Lcw Pressure Coolant Injection Systems n' Millstcne ware not properly ectadded; ar.d, in some cases the anchor bolts v.ere ccmpletely pulled out and no sup;crting function was provided.
Deficiency repcrts, in accordance with 10 CFR 50.55(e), filed by Long Isicnd Lighting Cem;cny, on Shcreham Unit 1, indicate that design of base plates with drilled anchor bolts using rigid plate assumpticns has resulted in underestimation cf Icads en scme anchor bolts.
Inspection of anchor bolt installations at Shoreham has shc,in over fif ty percent of the bolt installaticns were deficient.
Su;pcrts for both piping systems and electrical raceways have been reported as deficient at Shorencm.
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m It is currently believed that two interacting factors contribute to the failure of the supports.
First, the cesign assumpticn that the base plates perform structurally as rigid instead of flexible members may provide low estimates of imposed Icads on the supacrts.
Secor.dly, inccrrect anchor belt etc.bedment.n?.y also contribute to insufficient suppcrt.
The attached memcrandum frca V. f'conan to B. Grim-as, dated June 2, 1978, provides additional information.
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. StrETY SIGN!FICpnCE
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Dcptnding cn equipment layout, imprcperly desigaed er installed anchcr
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supports cculd:
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result in icss of support function in scn2 cases; and, 2.
result in high stressing of piping systems during a seismic event or during a significant fica transient.
REPAIR Millstone with assistcnce from Teledyne Engineerin; has ccmpleted design mcdifications and repairs.
These changes include increased base plata thickness and largar anchor bcits for failed supportsi Shoreham in conjuncticn with Stcne and '..'ebster is evcluating bcth piping a:.] clectrical type supports.
The review is scheduled to be completed by December, 1978.
DDR f.CTION The Engineering Sranch will review the design precedures used cn operating plants to determine anchor bolt icads, the techniques used to determine load rctings for anchor bolts, cnd the installation prcccdures.
This revie.. will be dene thrcugh cn A/E vendor inspection audit in conjunction with IE.
These A/E audits '.a il be started during early July, 1978.
We anticipate that critaria will be developed for design and installaticn of base plate-anchcr boit assemblies, and those operating plants requiring corrective action will be identified.
Additionally E3 staf# will further assess the occurrence and corrective acticr.s taken at Mills:cne, p er_0.v.>..u.r
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.m Ue reccmmend that this probt'm be add-essed on all CP cnd CL reviews.
At this t r.:e it appears that censiderations sncaid be given to the i
analyticai 7.ethods used to.detenine wac:her or not base plates behave as flexible or rigid matters.
This in turn may effect the anchcr bclt sice and embedn nt to properly ccpe with loads imposed on the s'Jpports.
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- It may be apprcpriate to require that cpplicants provide for revica their:
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methods for determining base plate thickness and anchor bcit lcads; 2.
criteria for anchor bolt installation; and, 3.
criteria for lead rating techniques fcr anchor bolts, including cyclic leads.
We shall coordinate cur meetings, discussions ard cvaluaticns of this issue with your staff.
Supplemental information will be provided.
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'm Vic't6r Stello, Jr., Director Division of Operating Reactors PRINCIPli DDR PERSCNNEL Reviewer:
J. Fair
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Enclosure:
lie:crandum dated 6/2/73 cc: w/ enclosure E. G. Case S. Hanauer R. S. Boyd
'-C. Nichcis W. Rutherford J. Sniezek W
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B. K. Grimes, Assistent Director for Engineering and Projects, DOR D. G. Eisenhut, Assistant Director for Systems and Projects, DOR
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FROM:
Acitng Branch Chief, Engineering Eranch, DOR
SUBJECT:
PIPE SUPPORT BASE PLATE PROBLEM The Engineerin; Branch, Division of Operating r.2:ctors, has contacted Dechtel, Bergen - Paterson, Gilbert, and Stone !. Webster in regar to their past and current d2 sign procedures for su?p;rt b?se plates utilizing drilled anchor bolts.
Becntel and St:ne & Web:ter indicatcd that they became a.iare of base plate flexibility effects on anchor bolt pull-out lcc.ds within the past couple of years and are new considering this in current designs.
Gilbert and Bergen - Paterson indic ted they are using rigid plate c :umptions for calculating bolt loads.
Revic." of the support redesigns at Millstone shr,es a considar:ble increase in base plate thickness and ar.cher bolt sizcs over the previous design.
The original designs by Scrgen - P:ters;n did not meet the current rigidity require =2nts used by St:ne & Webster.
Design deficiency reports by Long Island Lighting Compar.y en Shorch;a show that consideration of base plata flexibility has increased the pull-cut locds on some bolts, and inspeccion of the supports has shcwn that approximately 55 percent of the anchor bo'ts had incorrect embedcent lengths.
Currently, ILE is considering whether Stena & Ucb:ter shculd be investigated for a Part 21 deviation and will be furth?r investigating this matter.
The E.gineering Branch considers the problem at Millstene.there severa' support plates were pulled out to bc 5 cccbination of ba:e plate flexibility and anchor boit design probicms.
Since the enchor bolts were never testec for cyclic loadings, and the lines at l',iii: tone experienced fica induced vibrations, the canability of.ne ancncr bolts to withstand cyclic leadings should be cdcrested.
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v C:.r.ed on the clave infor= tion, the Engincering Cr:nch r cor nds th:t this b6 ;onsidered a c:neric itta f or cil op;r?.'.ing pl::.t:,
nnd a vendor inspecticn progr:.m be inpi:r nted stith !!.E to r-evic.:
the vendor desica procedure: c cd for Lnblyzing sup;' ort 5:0c pit:c: '
utilizing dHlied cnchor bolts Liong with the i'icid installic. tion l'roccdures utilized in inst:lling the nn: hor bolts. /il:c, the load rating techn' ques u:ed by the t:nchor Lolt t..:nufacturcr for cyclic i
loadings fould be revicwed.
The Engincaring Ercnch has t:lhed with ILE and contitier the vendor in:pection program to be th: ast officient inethod of cc picting the r4;ctss:.ry rtview.
The Engin cring tr:n:F c:ti=tes approxt :tel; 15 c:n-tt:kt will be r:cuired to revic.< design procedur:s used by vendors cnd //E firc:.
The Engineering Branch.-till set un c aceting uith both /10's to d.t r,:ine the interf::e bott::en the Er. gin:cring Branch and ICE r: quired to inplcment the revicu.
The Engineering Cr:n:h is in the proccs: of crep:rir.; a f:cdt::k'=r,o to DSS en the base plate prcM cr. t:hich is cxpected to be cc.ple:cd
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