ML20141E565
| ML20141E565 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2355, NUDOCS 8601080184 | |
| Download: ML20141E565 (22) | |
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/25/E ISSUED: 10/31/85
SUMMARY
/ MINUTES OF THE COMBINED MEETING OF ACRS SUBCOMMITTEES ON STRUCTURAL ENGINEERING, SEISMIC DESIGN OF PIPING, AND METAL COMP 0NENTS SEPTEMBER 23-24, 1985 WASHINGTON, D.C.
The ACRS Subcommittees on Structural Engineering, Seismic Design of Piping, and Metal Components met in Washington, D.C. on September 23 and 24, 1985 to review the research programs on structures and seismic margins, containment integrity, and leak-before-break concept applied to high energy lines aside from the PWR primary coolant piping system.
Notice of the meeting was published in the Federal Register on September II, 1985 (Attachment A). The schedule of items covered in the meeting is in Attachment B. A list of handouts kept with the office copy of the minutes is included in Attachment C. The meeting was entirely open to the public. There were no written or oral statements received or presented from members of the public at the meeting. E. Igne was the cognizant ACRS staff member for the meeting.
Principal Attendees ACRS C. Siess, Chairman, Structural Engineering and Seismic Design of Piping Subcommittees P. Shewmon, Chairman, Metal Components Subcommittee J. Ebersole, Member C. Mark, Member E. Rodabaugh, Consultant
, M. Bender, Consultant i
NRC Presenters Other Presenters L G. Arndt R. Budnitz, Future Resources l H. Ashar Associates, Inc.
l R. Bosnak R. Cloud, Robert L. Cloud i J. Burns Associates, Inc.
J. Costello l H. Graves
! D. Guzy R. Kennedy P601osois4 e51031 l 5 PDR
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. l Str.Eng..Seis. Des. Piping, Metal Comp. 2 Sept. 23-24, 1985 Meeting l I
l Structural and Seismic Research New seismological information indicates that some operating plants, especially those in the eastern U.S., may experience an earthquake larger than that they were originally designed for; e.g., the USGS has stated that an earthquake similar to the 1886 Charleston, S. C., earth-quake may occur over a wider area than originally thought. Although the Staff believes that there are considerable seismic safety margins in present designs, there is need for improved bases and methods for determining the proper seismic acceleration design level for present plants, and for well-validated methods for seismic analysis that can be used ta reassess older operating plants to ensure that adequate safety margins exist and to quantify these margins. It is important to under-stand the behavior ano capacity of nuclear power plants to withstand earthquakes larger than their original design basis in order to make regulatory decisions and not impose unnecessary modifications or shut-downs. Excessive use of snubbers has led to overly stiff piping systems that may diminish overall safety.
Some of the major objectives of this program are listed below:
To validate experimentally complex methods used to predict the j behavior of structures, systems, and components under large earth-quake loads that could cause response into the non-linear range.
These complex methods will then be used to benchmark simplified approaches to be used to make regulatory decisions for individual plants whose design earthquake has been increased.
To improve and reduce the large uncertainties in the data base that describes the fragility (functional capacity) of critical compo-nents and is used to quantify the seismic margin of a nuclear plant j and perform probabilistic risk analysis.
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Str.Eng.,Seis. Des. Piping, Metal Comp. 3 Sept. 23-24, 1985 Meeting To develop and demonstrate procedures to estimate the seismic design margins of nuclear power plants.
To develop criteria for reducing the number of piping and component snubbers used and thus to provide a better balance in safety between operating and accident conditions and reduce radiation exposures to workers.
The major program elements in determining the effects of earthquakes on operating plants are as follows:
Validation of methods: In FY 1986 and 1987, RES will participate in high level vibration experiments at HDR in cooperation with FRG to partially validate seismic codes. RES will also cooperate with EPRI in a soil-structure interaction experiment being built in an active earthquake region in Taiwan. In FY 1987, RES will partici-pate in vibration experiments in cooperation with the Japanese on large integrated piping systems at the Tadotsu facility to validate non-linear piping computer codes. Validation efforts will be completed in FY 1987.
Improved Fragility Data Base: In FY 1986, RES will complete gathering of component fragility (failure) data, in cooperation with EPRI and industry (SQUG), and identifying the specific fragil-f ty ht: needed, and in FY 1987 will complete fragility testing of selected componenth In FY 1986 through FY 1988, experiments on tra U cule concrete shear-wall structures will be. performed to investigate their behavior under seismic loads exceeding the design basis, to determine'the mode and level of failure. The component and structural fragility effort will be completed in FY 1988.
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Str.Eng.,Seis. Des. Piping, Metal Comp. 4 Sept. 23-24, 1985 Meeting Seismic Design Margins: In FY 1986, RES and EPRI will complete the development of procedures and review guidelines to estimate the seismic margins of PWR plants and conduct a trial plant review to demonstrate and improve the procedures. In FY 1987, similar procedures and plant review will be completed for a BWR.
NRC research is focused on developing the technical basis for licensing decisions and establishing regulatory criteria using the results of industry research where possible. More money is being. spent by coop-erating industries, as compared to RES budget, by about a factor of four to one.
Some regulatory uses of this program are as follows:
Improved fragility data base will be used to evaluate available seismic margins and provide improved. input to PRA.
Seismic design margin procedures will be used to assess capacity of nuclear plants to withstand larger earthquakes.
ASME Code, Reg. Guides and SRP will be modified to permit removal of snubbers to make pipe systems more flexiole and provide improved balance of overall safety.
Quantification of Seismic Margins R. Budnitz, Chairman of the Expert' Panel on Quantification of Seismic Margins, presented the Panel's conclusion on this matter. He stated:
given that an earthquake level is chosen for " margins review" the Panel believes the following:
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- Str.Eng.,Seis. Des. Piping, Metal Comp. 5 Sept. 23-24, 1985 Meeting
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It is feasible to identify those few safety functions whose failure contributes most to core-melt frequency, and the systems and components supporting those functions.
It is feasible to determine the high confidence of low probability of failure (HCLPF) value for each component, and to determine if it is above or below the earthquake level chosen for review.
The Panel's approach will provide: 1) If no accident sequences exist below the earthquake review level, there will be HCLPF at that. review level and 2) If some sequences do contribute below the earthquake review level, these will be identified, and their approximate importance understood.
In August,1985 the Panel's first report, establishing the approach and providing guidance on the margin review process, was published. The
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next report, due in October-November 1985 will provide detailed guidance for doing trial review and interactions of systems analysts and fragili-ty analysts. In 1936 the Panel will perform one or two trial plant margin reviews and, if necessary, modify the review guidance.
Containment Integrity The containment building is the final barrier to release of radioactive material to the environment from a severe accident.- In order to evalu-ate the effects on public health and safety resulting from postulated severt accidents, the ability of the containment building to provide a barrier against the release of radioactive material to the environment must be known. There are large uncertainties in predicting the leakage and structural behavior of the containment system under severe accident conditions of pressures and temperatures larger than the design basis.
Str.Eng.,Seis. Des. Piping, Metal Comp. 6 Sept. 23-24, 1985 Meeting The objectives of this program are 1) to develop and carry out experi-ments on scale model steel and concrete containments to support develop-ment and validation of methods for estimating the leak and structural behavior of containment buildings under severe accident conditions that exceed their design basis and 2) to develop reliable methods for assess-ing the interaction between containment penetrations, e.g., hatches, airlocks, mechanical and electrical penetrations and containment struc-tures to predict leak behavior under severe accident conditions that exceed the design basis. The methods developed will be validated experimentally.
The 1/8-scale steel containment, completed in FY 1985, was designed to verify the adequacy of the ASME Boiler and Pressure Vessel Code used to design steel containments. Post-test analysis of the failed 1/8-scale steel containment indicated the following:
Failure mechanism of the model was not predicted correctly.
Metallurgical investigations showed that the failure was ductile.
-A crack in the formed stiffener adjacent to the reinforcement of a containment penetration was observed at about 165 psig, correspond-ing to a maximum principal strain of 16 percent.
As ~a result of the crack in the stiffener, strain redistribution occurred which resulted in a redistribution of load from the cracked stiffener into the containment shell wall. Subsequent pressure increase to 195 psig failed the containment catastroph-ically.
The containment penetrations were essentially leakproof up to containment failure.
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Str.Eng. ,Seis. Des. Piping, Metal Comp. 7 Sept. 23-24, 1985 Meeting 4
.In FY 1986, a 1/6-scale reinforced concrete containment building, including penetrations, will be constructed. Experiments will be conducted on this building in FY 1987 to investigate its behavior under
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severe accident conditions in order to validate predictive methods.
In FY 1986, leakaga experiments will be completed on various seal and gasket materials under severe accident conditions. In FY 1987, experi-ments will be completed on large penetrations, e.g., airlocks.and pipe bellows to investigate their leak behavior under severe accident con-ditions. Boundary conditions at the containment penetrations obtained 4
during the steel and concrete model tests will be applied to separate penetration configurations to determine realistic leakage characterfs-tics. In FY 1988, the containment integrity program will be completed with validation of analytical methods using the experimental data and investigating the behavior of containments under very large earthquake loads.
i EPRI is conducting separate investigations on concrete wall elements and wall-base mat interactions tha't will provide input to the NRC program.
EPRI, France-CEA and UK-NII will provide pretest predictions to evaluate methods for concrete model experiments. FRG-KKF is conducting experi-ments on steel vessel material to investigate biaxial effects and.will also provide analysis and insights on steel containment behavior under large earthquake loads. NRC research efforts are focused on behavior and leakage of containment beyond the design basis (severe accidents) while industry effort is essentially focused on behavior of containments
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for design basis accidents.
i The results from the scale-model containment and penetration tests will provide the basis for validating analytical predictive methods. These j methods will be used by the NRC licensing staff to make regulatory j
decisions regarding the integrity and leak behavior of containments
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J Str.Eng.,Seis. Des. Piping, Metal' Comp. 8 Sept. 23-24, 1985 Meeting under severe accident conditions. The results from this program will also support the Commission's policymaking on severe accidents.
Leak-Before-Break Dr. R. Cloud, contractor to Duquesne Light Company presented an overview of the leak-before-break (LBB) concept applied to the high energy piping system of the secondary side (Class 2 and 3) of Beaver Valley Power Station, Unit 2 (PWR). The Whipjet Program (for the rational'elimina-tion of pipe whip restraints and snubbers and jet impingement shields) is an alternate engineering method for pipe break protection. This will involve the following:
perform test and analysis to show that LBB approach is appropriate for the balance-of-plant piping (Class 2 and 3) systems.
demonstrate that leaks occur before break, and develop a compatible leak detection system.
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He further stated that pipe rupture restraints in areas where LBB is not applicable or economical will be retained. Also retained will be double-ended guillot.ine break (DEGB) assumption for ECCS, containment design, etc. R. Cloud stated that at present pipe rupture mitigation hardware assembifes for BVPS-2 numbers 272 (restraints and jet shields only), which is distributed as follows:
primary system -9 arbitrary intermediate breaks - 127 balance of plant (whipjet) - 136 (or 50% of total)
The elimination of rupture-mitigation hardware in the primary system was
.the result of the recent limited scope rule change to GDC-4. Arbitrary intermediate breaks were recently eliminated by changes to the Standard Review Plan. LBB applied to high energy lines will be allowed when the
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Str.Eng.,Seis. Des. Piping, Metal Comp. 9 Sept. 23-24, 1985 Meeting !
broad scope rule to GDC-4 is promulgated. [ Note: RES is presently in the process of modifying GDC-4 so that LBB may be applicable to high energy lines, in general. The Metal Components Subcommittee plans to review this document when it becomes available.]
Some of the benefits of eliminating or reducing pipe rupture restraints are as follows:
Improve accessibility to minimize restrictions to ISI and reduce personnel radiation exposure, Minimize unanticipated thermal expansion stresses due to restraint interfere:ce.
Better understanding of piping failure mode, and Reduce plant cost by about 12 to 16 million dollars.
I'r. Cloud stated that Duquesne Light Co. would suggest the following schedule for the implementation of the Whipjet Program:
NRC grants schedular exemption of Balance-of-Plant whip restraints . Sept. 1985 Duquesne Light Co. completes Whipjet Program Dec. 1985 Install whip restraints, if any are required At refuel-ing outages The Subcomittee, in its deliberations, and its consultants felt that the Whipjet Program is a really worthwhile program and should be pur-sued.
The meeting was adjourned at about 3:00 p.m.
NOTE: A complete transcript of the meeting is on file at the NRC Public Document Room 1717 H Street, N.W., Washington, DC or can be w
Str.Eng. Seis. Des. Piping, Metal Comp. 10 Sept. 23-24, 1985 Meeting obtained at cost from Ann Riley & Associates, Court Reporters, 1625 I Street, N.W., Suite 921, Washington, DC 20006, telephone (202)293-3950.
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"AtTACHMENTpA g e. s.-
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7 Federal Eegister / Vol. So, No. De / Wednesday, S ' epider 11 2mes T Ecel"ot c ' C - WW7 LocoIPublicDommentRoam -
%e Commission's telated evaluation I
, ' locations Board of Supervisors Office, AncikyQuerodry Mamuse31a*WMP4 louisa County Courthouse. Iouisa, of the araendments la contained in e Amanadment sevised die e-amind p Virginia 23093, and Alderman ubrary, Safety Evaluation dated Angest 21,1985. Specificationa, m ; h c*l v4.* ;rin 3 No significant hazards --hation DWe ofisi#dnacar de Modummi M, Manuscripts Department. Univesity of comments received; No.
Virginia, Charlottasville. Virginia 22901.
. - Registac ]aly tr.2ee6 0s FR asom mt. 4 's LocalPublic DocumentRoom asoach . .m *<.m to M Virginia Electric and Power Company, et locations: Board of Supmisors N ne on-m==m's alsted M ,
al., Docket Nos. lso-838 and 56-339, louisa County Courthouse, buisa. - oW OW h h A*
North Anna Power Station, Units No.1 ' Virgima 23093, and the Alderman . . . Safety Evalentissi dated August 21, a885,.
and No. 2,Iouise f'e==dy' Virgmla Library. Manuscripts Department, No -- - - hazards se a.a.-ae=. ,
Date of applicationforamendments: University of Virginia. Charlottesville, conments received: No. +rW D September 28,1984. Vitginia 22901. LooniPtiblicDocmnant naasa r' n e Briefdescription ofamendments:De Virginia Electric and Per Capany' locations: Board of Supervienes OdBoo, c -
1smendments are administrative in Docket Nos. 50-280 and 50-281, Surry Los se County Courthones, t-i== .il nature and conect discrepancies Power Station. Unit Nos.1 and 2 Surry Virginia 23003, and the Alderuman W-presently existing in the NA-1&2 TS County, Virginia Ubray Manuscripts 3 n?
which relate to the Radiological Effluent University of Virgmla. '?
Technical Specifica tions (RETS). He Date of applicationforamendments: Virgiana 22901. ec.e.g $Pm May 13.1985. -
emendments add the Containment Deted et Betheses. Maryland Gds 5th day '"
Vacumm S Briefdescription of amendments: of sepeseber ans. - w .-c- '
gaseous re, team Ejector (Hogger)
.csse pat.. that la inunitorea as a ,
These amendments revise Technical .
Specif cations Section 5.3 to modify t)e rceche w a r R=adstorf Canu msse m 7
, and specify the figure for the Low adwwd I.peder, ' , ^ ** - ' I Population Zone in the appropriate TS description of the fuel assemblies sol ' ~
Acting Cfrief C)emtingRooctars Binnea 83 figure and correct numbers are asugned that reconstituted assemblies may be -*
to appropriate TS Table numbers. placed into the core. In the reconstituted ajrf,jon efum, fry .
assemblies, fuel rods which are kdown pg pac, g5.,25rse Fued s-to-as a;45 am]
Date ofissuance: August 29.1985. * **
Effective date: August 29,1985. to bive failed have been removed and . -
. ' - b Amendments Nos.:87 and 53. replaced with dummy (non. fueled) rods.
Facility Operating License Nos. NPF- Date ofissuance: August 26,1985. Advisory Committee on Reactor I Effective date: August 28.1985. Sateguards, Jo?nt 86commettee on ~
d andNPF-7. Amendments revised the Amendment Nw.102 and 102. Structural Engineering and Selesnic 1
Da e n i 1a $e Federal Register: Facuit&mung 1.icense Noe.DPR- %nM % % a
% Commission's related evaluat:on of 32andDPR47. Amendments revised '
the amendments is contained in a Safety the Technical Specifications. %e ACRS Subcommittees on #~ 7'*
Evaluation dated August 29.1985. Date ofiniuolnoticein Federal Structural Engineering and Selsmic No significant hazards consideration Register: June 4.1985 (50 FR 23555). Design of Piping will hold a joint ' #
commente received: No. %e Commission'a related evaluation meeting on September 23 and 243985, -
LocoIPtiblic Document Room of the amendment is contained in a locations: Board of Supervisors Office. Safety Evaluation dated August 20.1985.
Room 1046,1717 Washington, DC. .
- H Street. NW. P. 2I-louisa County Courthouse, Louisa, No significant hazards consideration The entire meetin Virgina 23093, and the Aldmnan public attendance. g wD} be open * " to - .5 comments received: No. '
Ubrary, Manuscripts Department. The agenda for the subject meeting LocalPublic Roomlocation:Swem shall be as follows: . . -t , - ?. .~
University of Virginia. CharlottesviDe, Ubrary, College of William and Mary, .
Virginia 22901. Williamsburg, Virginia 23185. ' Afonday, Septestbar.23, M . . ~
'a.m. untilthe cocchision of A=====s.
Virginia Electric and Power Company, et Virginia Electric and Power Company, et 7hessy. SeptestbarM. 2s84s30 al. Docket Nos. 50-338 and 50-339, al., Docket No. 56439, North Anna Power Station, Unit No.2. Iouisa c.m. antil the conclue:on of bar==== - l North Anna Power Station. Units No.1 %e Subcommittees willrweiew the and No. 2,louisa County, Virgmla County, Virginia ., statne of resarch programs on .
Date ofapplicationfor amendments: Date of applicationforamendment: ontainment integrity, seismic margins, April 15.1985. February 11.19ss. piping reliabillty, and other selated Briefdescription of amendments:%e Briefdescription ofamendment:%e ma tters. In addition. leak-befme. break amendments revised the NA 1&2 TS 3/4 amenb nt i provides relief from concept applied to h1gh enersy piping 9.3 to specify a minimum decay time of Surveitsnce Requirement 4.4.7 [rable systems other than the primary coolant 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> instead of the presently 4.4-3) which requires that reactor line will be diamaaad a specified 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to any coolant system chemistry limits for Oral staterments may be presented by movement of fuels for refueling chlorides and Doorides be sampled on a members of the public with the operations. continuing 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> basis.%e relief from concurrence of the Subnnanmittee . - .
Date ofissuana: August 21.1985. Surveillance Requirements 4.4.7 (Table Chairman: written statements will be * ,
Effectisw date: August 21.1985. 4.4-4)is applicable when the reactor accepted and made available to the -
Amendments /os.:es and 52. coolant system is drained below the Cnemittee. Recordings will be per-ana.A Facility Opemtittg License Nos. NPF. reactor pressure nozzle and the intamals only during those portions of the -: .
d andNPF-7.M="Amants revised the and/or head are in place.%e reliefis meeting when a transcript is being kept. '
{ Technical Specifications, and questions may be asked only by .
l Date ofinitiolnotice in Federal only applicablein Mode 6 (Refueling). . members of the Subcommittee,its Date ofissuanca: August 21,1985. .
l Register: Msy 21,1985 (50 FR 20909 at Effective date: August 21,1965. consultants, and Staff. Persons desiring
( 20995). ~ to make oral statements should notify
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AmendmentNo.:51. ,
the ACRS staff member named below ae l
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- 37098 Federal Register / Vcl. 50, N2.176 / Wednesday, Sept ber 11, 1985 / Noticee far in advadce as is practicable so that 1 individual one or two days before the appropriate arrangements On March 25.1965 Mr. Husted f. 'I During the intial portion of thecan be made. . scheduled meeting to be advised of any requested a hearing.Mr.Husted also '
meeting, the Subcommittees, along with changes la schedule, etc., which may - j have occurred. requested that the proffered hearing be l any ofits consultants who may be a expanded to address whetherhe "is -
3 Dete september 5, tees. - '
pesent, may er.hange preliminary views baned by concerns about his attitude or regardmg maWas to be considered Mortom W. IJberkin, ;.
. IntegrHy from sadng as an E during the balance of the meeting. > AssistantLecutire Discto@P$t- Ilcen8ed perator, or a licensed ytoe g,,f,,,, ,
Instructor or training supervisor.
%e Subcommittees will then hear .
1 presentations by and hold discussions p Doc. 85-217W Filed 9-10 45 M5 am) Mr. Husted maintained that the with representatives of the NRC Staff, ~******'** expanded scope he requested would not its consultants, and other interested require additional agency resources t persons regarding this review.
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. because it would involve consideration - .'
Further information regarding topics . . (Docket Noe.so-ssa ot., so-ass 08.1 of th: same factualissues as would the ,
to be discussed, whether the meeting Philadelphia Electric Co; Oral proffered hearing. nerefore, Mr. Husted has been cancelled or rescheduled, the Argument argued, the potential benefit to himself <
Chairman's ruling on requests for the justified such an expanded scope. * -
opportunity to present oral statements in the matter of philadelphia Electric Either hearing would focus on Company, (Limerick Generating Station, r
and the time allotted therefor can be whether the following four concerns. . .
r;btained by a prepaid telephone call to Units 1 and 2). ngarding Mr. Husted are true, and, if so, '
the coenfrant ACRS staff member, Mr. Noticeis herebyg! van ehm, u, whether they requirs that he not be L Elpidio G. Igne (telephone 202/634-1414 accordance with the AppeaIEard's employed in the jobs in question:
between 8:15 a.m. and 5:00 p.m. Persons) order of August 29,1985, oral argument (1) Re alleged solicitation of an '
planning to attend this meeting are on the appeals of Limerick Ecology answer to an exam question from
. urged to contact the above named Action and Robert L Anthony / Friends -
" another operator during the April t.1981 of the Earth from the Licensing Board's '
ule m o ldsed any May 2,1985, third partial Initial decision NRC written examination; -
changes in schedules, etc., which may - a fisite emergency planning (LBP45- (2) ne lack of Forthrightness o'f his have occurnd. 14) will be heard at 1. top.m. on Friday, testimony before the Special Master; .
Dem: Sepueber 8, tees. October 11,1985, in the NRCPublic 3 His poor attitude toward the Hearing Room. Fifth Floor. East. West
- he(ar)ing on the ches ting Ircidents; 7and ksartem w.tJberian.
Towers Building,4350 East-West UE ** ***E*'* * -
Assistant
' a,vj,,,. - becutin DirectorforPwfect Highway, Bethesda, Maryland. I"* *
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I [FR Doc. 46-21733 %d 9-W85; 448 am) ' 3- nerefore, the Commission agrees that ?
M. Loss ooot rgss ebef al the expanded scope he has requested i
' C. Jean ahammat er' S E
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Advloory Committee on Reactoe Mr. Husted also noted the existence of Sofeguards, Subcommittee River Bend same W Doc. caosSW732 mSewEd . 9-1W 845 am) a July 6,1983 Stipulation between GPU $
station;Revleione 2 I
Nuclear and the Commonwealth of f
%e Federal Register published on ~ Pennsylvania in which CPU Nuclear a,
[ Docket,No; 50-289 (CH)] agreed not to utilize Mr. Husted to Tuesday, August 20,1985 (50 F1t 33657) 4 operate 30-1 or to train operating
[ [n'Ri General hublic UtWties Nucieer (Three Mle slend Nuclear Station, Unit No 1); license holders or trainees. Mr. Husted St; tion scheduled for Wednesday. stated that the licensee has no objection September it.1965, and the time has been changed to 3:45 p.m. In Room 1046, Thi Appeal Board as part ofits
'B th the NRC staff and nroe Mile taland Alert
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' 1717 H Street, NW, Washington, DC. To decialon on management-related issues ~ $$ ",*
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""j'4, cop,"t the extent practical the meeting will be in the Bree Mile Island, Unit 1 (30-1) -
restart proceeding required that "Mr. req =ted by Mr. Haud For b maana est fare open to public attendance. However. - to this order. the commaaion disasme with the portions of the meeting may be closed to Husted have no supervisory 85*E discuss the results of ongoing NRC. responsibilities insofar as the training of *^' *'***Pecdyins nadly what mhdH b -
dy' '
intsetigations.
- non-licensed personnelis concerned." '"
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'e'r50emuse ALAB-772,19 NRC 1193,1224 (1364). tr -
l Further Information regarding topics dedded in the no-1 restart procadtas and that i
to be discussed, whether the meeting ne Commission upon reviewing that latar"nor* to the restart proceedina have e d e
- decision decided to offer Mr. Husted "an ymem intemt a nashey ddecama.
has been cancelled or rescheduled. the -
opportunity to request a hearing on , " " '
- i Chairman's ruling on requests for the i opportunity topresent oral statements whether the Appeal Board's condition barring him from supervisory cE,'a*,3*'"",,'",fa*,"$l, wparere from the mtart procn
= be Dairn held ie
'. .and the time anotted therefor can be Mr. Husted, who was not siven notice and an
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- 5"d" I" ** *'' P*"dM6 insofar as obtained by a prepaid telephone call to
- non-licensed personnelis concernedresponsibilities the cognizant ACRS staff member Dr.
should be vacated." CLI-65-2,21 NRC E'a',#*'",c',d,, d ss e* '"'"END"h Richard Sevio (telephone 202/634-1414) hen hun resolved for the purpoem of that between 8:15 aJa. and 5:00 psm. Persons 282,317 (1965). He Commission in C1J. proceeding womar.naA.ttit amte the planr.ing to attend this meeting are 85-2 further stated that it would assign ***da'd' '" I" *'""'5'* "7 8"*'""*
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arped to contact the above named the matter to an ArfrninIstrative !aw
> t <,.s a.v..:.; e...r .. e, w judge if Mr. Husted requested a hearing. **P,',",,',*j,y 7,,,,,",,","g*., N,, M,* h
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f g law ATTACHMENT B
" TENTATIVE SCHEDULE COMBINED MEETING OF ACRS SUBCOMMITTEES ON STRUCTURAL ENGINEERING, SEISMIC DESIGN OF PIPING, AND METAL COMPONE SEPTEMBER 23 AND 24, 1985 ROOM 1046, 1717 H STREET, N.W., WASHINGTON, DC -
sWW w w-W Lok . G.t h GI y
V m nday, September 23, 1985 u > y %vte %
8:30-9:00AM Overview rb O Richardson l MSEB Seismic Research Program 9:00-10:30AM iLle (o t tro -) oll S NRC Seismic Design Margins Program b Guzy/Budnitz '
10:30-10:45AM Break e.;; _ v, .w ActPF bb W :45-+ M 5AM -EPRI-SeismWgira Ngram
\wso - W. t v G4 01- W - 0** W9 $aw)k h.4ERi y:15-12:00tioon
- Validation of Seismic Methods % M3% -
5 yL Costello V k ,
th00rM00PM Lunch 6 yqu c.o
<2.15. oi s
.h00-1:30PM i.er r.s e Component Fragilities d = 0'Brien # g c
' 4 4:30 2:15PM Category I Structures 1:ry -tas- Eow/4 Kenneally /
2:15 2:30PM 2:2 5- 3: s o Structural Load Combinations Arndt #
. -2:4 25 5:'5PM r - Structural Computer Code BenchmarksG hq,% raves -
. -3:00PM Break
- to - v 2.5 ,
MSEB Piping Research Program ras- 5::LO 3:00-3.4;PM NRC/EPRI Piping Program Guzy [
-&45-4r15- Other-EP113 4 ping Researc k O :; = :, CPRi 4:lS-5.-00PM Other NRC Piping Research
,, M owtM a BGCgf A
Guzy o
Tuesday, September 24, 1985 MSEB Containment Integrity Program
- 30-9:00AM so .sv Overview bM'om Costello ,
v 9:00-9-30AM Concrete Model Experiments \
io.cd o: %g Ashar i
-9:30-WOOAM Pre and Post Test Analyses
- Costello t
-4 0:00-10:30- -EPRI-Containment -Research-i Fusawara, ERR 1 to.ig-to.50 ;
__10.3v40:45AM Break l l
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,, : / 5TRUCTURAL ENGINEERING /
SEISMIC DESIGN OF PIPING /
METAL COMPONENTS 2 Tuesday. September 24,1985 (Continued)
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40:454M0AM- Penetrations [ ( w r q % Q ) Ashar 11:30-12:00 Noon Costello Un a ym.
SeismicPerformance$fContainments d- @ -R.
, ir43 1.w ih00<h0GPM Lunch Leak-Before-Break in Balance-of-Plant Piping Proposal 1 :00-1 :30PM iiRC Conrcents Bosnak 1:30-3:30PM LBB in BOP Piping Cloud 3:30-4:00PM Subctr.mittee Discussion and Adjournment 4
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ATTACHMENT C LIST OF HANDOUT MATERIALS SEPTEMBER 23-24, 1985 MEETING ACRS SUBCOMMITTEES ON STRUCTURAL ENGINEERING /
SEISMIC DESIGN OF PIPING / METAL COMP 0NENTS
- 1. Mechanical-Structural Engineering Branch Presentation to ACRS Subcommittees on Structural Engineering, Seismic Design
-of Piping, and Metal Components - J. Richardson, Branch Chief. NRC
- 2. Expert Panel on Quantification of Seismic Margins - R. Budnitz, Future Resources Associates, Inc.
- 3. Whipjet Program for Beaver Valley Nuclear Power Station, Unit 2, R. Cloud, Robert L. Cloud Associates, Inc.
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METAL COMPONENTS ACPS SUBCOMMITTEE MEETING ON STRUCTURAL ENGINEERING / SEISMIC LCCATION ROOM 1046 DATE SEPTEf1BE r24,1985 v
ATTENDANCE LIST PLEASE PRINT:
NAME AFFILI ATION 5A A W&
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METAL COMPONENTS ACRS SUBCOMMITTEE MEETING ON STRUCTURAL ENGINEERING / SEISMIC LOCATION ROOM 1046 DATE SEPTEMBER 24, 1985 ATTENDANCE LIST PLEASE PRINT:NAME AFFILIATION C - W ,L in b& f/ Q llokr< ,
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I METAL COMPONENTS ACPS SUBCOMMITTEE MEETING ON STRUCTURAL ENGINEERING / SEISMIC
-LOCATION ROOM 1046 DATE SEPTEf1BE8 24, 1985 ATTENDANCE LIST PLEASE PRINT:
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- - METAL COMPONENTS ACPS SUBCOMMITTEE MEETING ON STRUCTURAL ENGINEERING / SEISMIC LOCATION ROOM 1046 DATE SEPTEliBER 23 1985 ATTENDANCE LIST PLEASE PRINT:
NAME AFFILIATION C.? bu %
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1 NAME BADGE NO. AFFILIATION i
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- n .4(101: ROOM 1046 DATE:, SEPTEMBER 24, 1985 ATTENDANCE LIST PLEASEPRINT$
NAME BADGE ii0. AFFILIATION lY b/m nr (5 -D 95b. hSOL-E dPd W + A 'u f %
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ACPS SUBCOMMITTEE MEETING ON STRUCTURAL ENGINEERING / SEISMIC DES LOCATION ROOM 1046 DATE SEPTEMBER 23-24, 1985 ATTENDANCE LIST PLEASE PRINT:NAME AFFILI ATION bsf/7 / 8Aar MH* Stand f asfas7M fx.MA* t; A Raro.i f~ E E.4 u n o w >?cBe T 4. Ctoun >fSsoc .
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