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[ ],". <,' ?si NUCLEAR REGULATORY COMMISSION UNITED STATES
(.l f j ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 October 14, 1976 M. S. Plesset, Chairman Ad Hoc Working Group on Reactor Pressure Vessel Loadings AD HOC WORKING GROUP ON REACTOR PRESSURE VESSEL LOADINGS, SUBCOMMITTEE MEETING, AUGUST 5,1976, TORONTO, ONTARIO I have attached a copy of the minutes of the subject meeting I
would appreciate your review and corrections as soon as possible.
Copies of these minutes are being distributed to other ACRS members for their information.
P1pase note that the morning meeting and the slides presented therein contain Westinghouse Proprietary information.
A corrected version of the minutes, after receipt of your comments, will be transmitted to you for certification as to accuracy in ac-cordance with the requirements of Section 10(c) of the Federal Advisory Committee Act (P.L.-92-463).
Af ter being certified by you, the minutes will become the official record of the August 5, 1976, meeting of the Working Group.
OSh RagnwakMuller Senior, Staff Assistant Attachments:
As Stated cc: ACRS ACRS Technical Staff T. Theofanous Z. Zudans
'THIS DOCUEENT INCLUDES PROPRIETARY I. Catton 0' Tim ~ mS ONL7,- UNCLEIED 1:
Unsaft proper classification) 8707070662 870623 PDR FOIA PDR THOMASB7-40
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[M plIS DOCUMENI INCLUDES PROFRIEIARY IN W
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10/12/76
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f MEETING DAGE:
8/5/76 u
b a 6E2 DATE ISSUED:
10 - l i 'l b ACRS AD HOC WORKING GROUP ON REACTOR PRESSURE VESSEL LOADINGS Regency Room West Hyatt Regency Hotel 21 Avenue Road Toronto, Ontario, Canada M5R2G1 August 5, 1976 1
The ACRS Ad Hoc Working Group on Reactor Pressure Vessel Loadings met
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in Toronto, Ontario on August 5, 1976, to review the status of Westinghouse j
calculations of Reactor Pressure vessel Loadings by the Multiflex Code and to review the applications of the calculations to a typical reactor pressure vessel structure such as that at North Anna. The notice of the meeting appeared in the Federal Register, Vol. 41, No 139, Monday, July 19, 1976.
The proposed agenda for the meeting and a copy of the tentative detailed schedule are attached (Attachments A & B)
A list of attendees is included (Attachment C).
Slides used by T. C. Esselman, K Takeuchi and P. J.
Dosherty of Westinghouse, are included (Attachments D, E, & F).
Proprietary data are contained therein.
Slides used in the open session by Mssrs.
Throm (NRC Staf f), Esselman (Westinghouse), and Goldstein (Stone & Webster),
are attached (G, H, & I).
No public requests for oral or written statements were received and no such statements were made.
EXECUTIVE SESSION (CLOSED)
Dr. M. S. Plesset, Working Group Chairman Mr. J. C. Ebersole, Member ACRS Dr. I. Catton, ACRS Consultant Dr. T. Theofanous, ACRS Consultant Dr. Z. Zudans, ACRS Consultant Mr. Ragnwald Muller, Designated Federal Employee The meeting was called to order at 8:35 a.m..
Dr. Plesset reviewed the agenda.
Dr. Catton explained that the fluid mechanics and the structural modeling raise separate questions with respect to the Multiflex results.
Dr. Theofanous reviewed his concerns over the non-equilibrium effects.
Dr. Zudans was interested in the method of modeling the core barrel load.
The meeting ended at 8:55 a.m..
OFFHCHAL USE ONLY
I OFhdEAL USE ONLf MEETING WITH WESTINGHOUSE AND NRC STAFF (OPEN)
The Working Group Chairman, Dr. M.S. Plesset, called the meeting to order at 1:35 P.M. and made an opening statement explaining the purpose of the. meeting, the procedures for conducting the meeting, and noting the presence of Mr. Ragnwald Muller, the Designated Federal Employee.
He noted that no requests to make oral statements had been received.
He then called on Mr. Zoltan Rosztoczy of the NRC Staff to discuss the Staff review of the hydraulic loads.
Mr. Rosztoczy introduced Mr. Ed Throm and Mr. Paul Norian of the Staff and two consultants, Mr. Bernie Saffell, INEL and Randy Cole, Sandia.
Mr. Throm used Slides G-1 and G-2 to outline his presentation.
Dr.
Theofanous asked about the break flow model and why the Staff agreed not to consider a cold leg break at the nozzle greate,r than one square foot.
Mr. Knight explained that comes as the result of the restraints built into the biological shield in the region of the penetration of the pipe-line, as well as the natural stiffness of the system.
Mr. Knight j
, explained the assumed failure was a complete circumferential crack.
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Asked about the actual movements for the pipe, Mr. Esselman stated that the horizontal movement of the pipe attached to the reactor coolant pump moved approximately 0.5-0.6 inch. The vessel moved 0.072 in.
In response to a question about non-equilibrium effects from Dr. Theofanous, Mr. Throm indicated that the Staff would look at the LOFT semi-scale data.
Dr. Catton pointed out that this would not reveal much because of the paucity of pressure transducers.
Mr. Throm indicated that he had not previously understood Dr. Theof anous' concerns about non-equilbrium forces but he did now.
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Mr. Throm returned to slide G-3.
He explained the iterative computation
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of pressures with the inclusion of the moving wall.
He pointed out that Westinghouse still had to supply a detailed analysis of the fluid -
structure interaction, j
Dr. Theofanous asked how it would be judged.
Mr. Throm pahted out the tests at Bettis and at KAPL.
Later,. additional data will be available from Los Alamos.
Dr. Rosztoczy stated that with satisfactory results from the Bettis and KAPL tests in terms of both amplitude and frequency the Staff would feel confident the calculations are appropriate.
Dr. Theofanous was concerned about the complexity of the real system and the possible effect of the gap between the system and the coupling.
Mr. Cole stated he thought it possible to evaluate separately the flexible wall and the hydrodynamic aspects of the Multiflex code.
Mr, Ebersole asked about the change in flexibility with prolonged neutron radiation.
Mr. Knight stated that all he had seen involved normal moduli of elasticity.
Mr. Esselman indicated that in his judgment, though radiation would change the fracture and strength properties, there would be little. change in the elastic properties affecting the response of the barrel.
In response to a question from Mr. Ebersole, Mr. Esselman explairied that the flexibility was inherent and not designed into the structure.
Dr. Zudans suggested that the barrel be considered rigid.
Mr. Esselman pointed out that if the barrel is assumed rigid, the motion will be reduced about one-half, which he considered unrealistic.
Mr. Throm then continued to slide G-4.
He pointed out that Westinghouse had been asked to look at differences in spatial detail and at different i
plant classes, those with thermal shields, those with neutron pads, those with 2, 3, and 4 loops.
This information has been presented to the Staff and is under review.
He then discussed treatment of multi-dimensional regions (Slide G-5).
In response to a question from Dr. Zudans, Mr. Esselman explained that Multiflex was put into a structural code that Stone & Webster would explain later.
The stresses on the core barrel within the reactor are within limits.
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OFL.JEAL USE OEI Mr. Throm covered the tests performed to verify the code with Slide G-6, and then concluded his presentation with Slide G-7, comparing the calculations with experimental data.
Dr. Plesset asked Dr. Rosztoczy about the schedule for Staff completion of the analysis.
Dr. Rosztoczy explained that the Staff would complete its SER on Multiflex 60 days af ter receiving the data, now expected in September.
In response to Dr. Zudans, Mr. Knight indicated that the Staff would i
independently evaluate the modelling of the core barrel.
Mr. Knight,in response to Mr. Ebersole, indicated that the design may be more than adequate and therefore would not require more detailed analysis.
Next, Mr. Marburger, Westinghouse, called on Mr Esselman to discuss the way the loads are factored into the structural analysis. The Model for the internal was shown in slide H-1.
The curved line represents a spring to give rotary restraint.
The flange can rotate but not lift up.
The vertical response model was shown in Slide H-2.
The vertical response is affected by the core barrel flange. The more detailed representation of the fuel allows fuel lift off. Westinghouse pointed out that the two models were coupled at the intersection of vessel vertical and nozzle center line.
Dr. Zudans pointed out that one can move horizontally or rotate, but not move vertically with the code.
Mr. Esselmar. insisted the code was adequate because it was conservative.
Westinghouse is developing new codes to take care of Dr. Zudans' concerns for future analysis.
The Staff pointed out the models were developed a number of years ago.
The Staff's independent evaluation model includes horizontal-vertical coupling. The staff will verify whether or not the Westinghouse analysis is conservative.
Mr. Esselman discussed Cavity Pressure Horizontal Load (Slide #3), Vertical Load (H-4) and Cavity Pressure Movement Load (Slide H-5),
and loop loads (H-7, H-8), showing Loop Movement (Slide H-9).
The horizontal displacement is shown in Slide H-12.
Mr. Esselman indicated it had a peak ofM70 mills at about 1/10 second. The vertical motion was about.1 inch upward and.15 inch downward (H-13).
The rotation history was shown (Slide H-14).
The average break area was 58 square inches although the displacements were based on a 144 square inch break.
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l Dr. Esselman pdnted out that both models have a common zero point in
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time, but Dr. Zudans was not satisfied they were adequately coupled.
1 Dr. Esselman stated that his results were used by Stone & Webster in analyzing the RPV support.
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Norman Goldstein of S&W next explained the support structure with Slides I-1, 2, 3, & 4.
He explained the LIMITA code used for i
inelastic analysis of the support system.
He explained some tests f
measuring responses of beam ends having impulses imparted to them i
with plastic explosives (I-6).
His next series of slides showed the analysis of beam motion at critical times derived from the Westinghouse 1
load analysis. His final slide showed that the deformation capability i
of the reactor vessel support was a good deal larger than the imposed
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displacements deduced from the Westinghouse evaluation of reactor vessel motion.
(Maximum tolerable vertical displacement exceeds 6 inches and
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horizontal exceeds.5 inches, but actual results show displacements on the order of 7 mils. His conclusion was that the supports can sustain j
without failure, but a little deformation, the loads imposed by the J
Westinghouse analysis.
There were six supports.
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j Dr. Zudans asked how the load was distributed equally among the six I
supports.
Mr. Goldstein explained that the shims and gapping are quite close. The threaded ball provides for levelling.
Mr. Ebersole noted the vessel movement was not much but wondered about the free end of the pipe.
Mr. Goldstein explained that for the cold leg break for instance, there is only a free gap on the order of a half-inch.
I In response to Mr. Knight 's query, Mr. Goldstein stated that all six i
supports were active.
Next, Mr. Saffell, INEL, gave a brief overview of the confirmatory j
analysis being performed on behalf of the Staff. Results were expected about September 1.
Analysis paralleled that performed for LOFT.
l In response to Dr. Zudanh question, Mr. Saffell stated INEL was doing linear elastic analysis and not considering gaps between different point i
The loading history came from the WHAM model. The cavity loads came from RELAP.
In closing, Dr. Plesset reminded the participants of the North Anna Subcommittee meeting scheduled for the following week.
The meeting adjourned at 4:00 pm.
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l ADVISORY COMMITTEE ON REACTOR SAFEGUARDS AD HOC WORKING GROUP ON RPV LOADINGS
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HYATT REGENCY HOTEL, 21 AVENUE ROAD, l
TORONTO, ONT., CANADA MSR2G1 AUGUST 5,1976 l
AM PROPRIETARY SESSION I
ACRS Dr. M. S. Plesset (Chairman)
Mr. J. C. Ebersole, Member Dr.
I. Catton, Consultant Dr. T. G. Theofenous, Consultant Dr. Z. Zudans, Consultant Mr. R. Muller, ACRS Staff (Designated Fed. Employee)
Westinghouse NRC Staff Vincent J. Esposito Edward D. Throm Arthur C. Spencer Zoltan R. Rosztoczy David C. Marburger Paul Norian Kenji Takencho James P. Knight T. C. Esselman Vincent S. Noonan J. Larry Vota Walter J. Pike W. Terry Bogard Pei-Ying Chen B. F. Maurer S. Fabic D. J. Kowalski L. Shotkin P. J. Docherty Southern Conpany Services VEPCO Anees A. Farruk W. F. Bennett F. C. Prince TVA Stone & Webster Robert F. Christie C. B, Miczek Aerojet Nuclear Norman A. Goldstein R. B. Bradbury Bernard F. Saffell, Jr.
LASL Sandia Labs C. W. Hirt Randall K. Cole, Jr.
I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS AD HOC WORKING GROUP ON RPV LOADINGS i
HYATT REGENCY HOTEL, 21 AVENUE ROAD, J
TORONTO, ONT., CANADA M5R2G1 AUGUST 5,1976 AFTERNOON SESSION D. A. Peck, Combustion Engineering F. T. Pfeif fer, Cour t Reporter, Ace Federal T. Winkler, Kraftwerk Union, W. Germany M. B. Muller, self K. B. Bennett, self 4
I i
t AD HOC WORKING GROUP ON RPV LOADINGS AUGUST 5, 1976 Hyatt Regency Hotel 21 Avenue Road Toronto, Ont., Canada MSR2G1 m.__________
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C-O ma encas Class Advisory Committee Meeungs. ADVISORY GROUP ON CONTRIBUTIONS Agenda: To rettsw and evaluate researcJs dated August 13.1973,I have determined OF TECNNOLOGY TO ECONOMAC proposala and projects as part of the selee.
Stas the tneetr.g would fall within ex.
STRENGTH tion procew for awards.
en:Mions (4s and (6) of 5 USC. 552(M MeetM 3*88on '
,,,, het g ed[c1u P
and that it is essential to close the Eneet-In accordance wtth the Federal Adri-f a proprietary or conadenttaa aneure to.
ing to protect the free exchange of in-sory Committee Act. Pub. 1.93-463, the etuding teem informauon: ananetna ter.al views and to avoid interference Nations! Science Foundation annotnices data, such as satartes; and personal infor.
s.th operation of the Committee.
the following Enecting; anauon concernlas todir& duals awated 1: ts suggestet that those desirmg more with the proposals and projects. nese Nam: Adetsory Omp on Contributions of STenSc informa!Jon Contact the Advisory Cc:::Dittee Management Of5cer, Mr Technology to Economic Strength
- matters are within exemptions (4) and (8) of 8 U3 C; SS2(bh Freedoar of In.
Jo!.n W. Jordan. 80615th Street. NW.'
Date: August 6.1976.
Ttme: 9 a.m. to 4 p m.
formation Act. The rendering of advtee Waahington. D C 20506, or call area Ptaae: International &teetag Room. Ryatt by the panel ts considered to be a part of code 202-382-2031.
House (formerly in ternauona11on h inter
- tas Foundauon's douberative proceum and Jourk W. Jonom.
nat. tonal A&rport. Ima Angeles California h thus subject to enesopuon (5) et the Aeg oC045-Adtd. tory Committet Type of mecung: Open.
Authortty to close meeting: This determina.
Mariagement Ogeer.
Contact person: Mr. wtutam Montgornery.
tion was made by the Committee Man-
{FE Dcc.76-20622 Filed 7-16-76.8 A5 am)
Specta! Amststant to the Director of Opm*
stement Omer pursuant to provtstons of tions. National 5dence Foundstlen. Wash
Inittee Managespont OfBeer was delegated NATIONA1. SCIENCE FOUNDATION Aaron* planning to attend *be =ttor ttfe authority to make detertninations by
)
should contact Atr. nsontgomery by July ta. Director. Rsr. ma rebruary u, me.
ADWSORY CROUP ON ANTICIPATED AD.
26,1976.
E Resteca Wonctrir, VANCES IN SCIENCE AND TECHNOL. summary minutes: May be obtained from Acttng Committee l
g the Committee Management Coordination Meetirtg stas. Dtv. of Personnet & Management. Rm Ng7tageme7tt OSect".'
- In secordance with the Federal Ad*
212. National Science Fbundation. Wash.
.!ULY 14.1976.
ington. DC 2055o.
TiscrF Committee Act. Pub. L.92-463, Purpose of advisory group: To provide Isrues l FR Doc.75-20745 Filed 7-14-76:9:44 am J th) National Scfence Foundation an.
that may lead to polley supporting an tm.
naimcas the foUowing meeting:
proved stiuzation of technology and foa.
NUCLEAR REGULATORY Eame: Advisory Group on Anticipated Ad*
taring economie attength. This group wu!
enness in Scien s and Tecbcology.
consider these subjects in a manner which COMMISSION,
will faenitate the planning for the new ADVISORY COMMITTEE ON REACTOR Dass: August 5.1976.,
OtBee of Science and Technology Poucy.
SAFEGUARDS AD HOC WORKING Flass: tornado Meeung Room. Hyatt 09 Convent Chairman's remarks.
P REACTOR PRESSURE *VES.
Nouse (formerly International Innh In*
0010 Bevisw of Issues @ ration of ter_ationa!. Airport. Ims Angeles California OEFIP, Energy. Regulation-Health Meeting q
$,,Dfcjo",*,*'** "'**I Type meeting: open.
In accordance with the' purposes of Con act, person: Mr. wu m m Montgomery, uoo I,unah.
sections 29 and 1&2b. of the Atomic Enw Special Asststaat to the Director of Op*
1300 Continue issue review. Economic ef.
ergy Act (42 U.S.C. 20M. 2.232b.J. the a auons. Natiosa! Scie nce Foundation, facts, space. Information. Ctril ACRS Ad Hoc Working Group on Re-waitington, DC 2c530. telephone 202/632-4eet AnTone pMntng to attend the meet-R&D, vulnerabtury of comptez actor Pressure Vessel Loadings wul hqld t
a d contact Mr. Montgomery bT rystems.
a meeting on August 5,1976 at the Hyau 1800 Adjourn.
Regency Hotel. 21 Avenue Road. Toron, Sc=.: nary mifutes: May be obtatned from '
E Rasseca WznxLrn, to. Ontario. Canada M5R2Gl. The pur.
i the Cornmittee Management Coordination Sta3, Div. of Personne! & mnagement, deffnp Committee pose of th!S IDeeting is to Continue the I
a En:. St2 Nat!?nal Science Foundation.
ygygageryggygg oggg7' Committee's review of the caieuiations j
Washington. DC 20550.
Jtr1.7 14,1976.
of landines on reactor pressure vessels Purpose of a$rist.ry group: To provide ad.
and their supports un( ct severe &cf.ident e':e en develep=.e.nta that may take place
[FR Doc.76.-20746 Filed 7-16-76;8:45 am)
Co.DdiUOD8-in zience and engineertog and examine Ibe agenda for the stibject fnetting shall be as follows:
the nasonal pot.acy imputations of these INTERNATIONAL DECADE OF OCEAN Thursday, Anoust 5, IS76, 8:30 a.m.
. ene:opments. This group wiu consider EXPLORATION PROPOSAL REVIEW PANE 1. The Working Grotrp wiu meet in closed j
eham cubjvets in a manner which wel eaccrests fte p;ennlog for the new Of*
Meeting litrecutive Session with any of its con-are of Setene, and 'rectnology Potf:y.
In secorda.nce with the Federal Ad-sultants wbo may be present. to escht.nge visory Committee Act. Pub. L.82-463, 'and recommendations relating to cal.
opinist and discu.ss preHminary views Agenea.
the National Science Fcundation an*
eses convene Chairman'sremarks.
este Bersaw at Isrues-opersuon of nounces the follotving meeting:
culations of the loadings on reactor pres-sure vessels and their supports under cer17.
Energy.
Regulation Name: Internauc.nal Decade of Ocean Ex. severe accident conditions.
NonJth & Safety. International pioration Propmal Rettew Fwl.
S&T. nealth of science.
Det* and Ume: August im Ins-o a.m.
9 a.m. until appro.timately 113a p m.
E b48A The Worklog Group win meet in closed i
Pla e: Am.
3 tt'ocaJ Scienae Foundation, aession to hear presentations of propri.
&ggs Contlaua lasue review. Food. Re-1800 0 Street. NW Washington, D.C.
etary informstlon by representatives of notareas. Climate. Oceana, niemeda Type of meeting Closed.
the NRC StaH the Westinghouse C]ec.
Sant R&D.
Contact person: Mr. 74enan D. Jennings, tric Corporation, and their consultants.
lege Adjourn.
Read. Ostee for the Internauonal Decade 1:30 p.m. until conclusion of business.
K hascC& WDm!.ta.
of Ocean Erptoration. Room 605. Nationag The Working Group wiU meet in open Sciense Foundation. Wasaineton. D C.
session to hear pre entations by repre.
Acting Committee sosao, telephone 902) sawasa-mentatives of Stone and Webster En.
Managemc7&J OAcer'.
Purpose of panet: To provide adrice and sincering Corporatjan and the NHC 8 tag JCLT 14.1976.
'"-=ndauona meerntag support, of researth by programs of the once for the and to hold discussions with these groupe (FR Doc 38-20742 Pued 7-Is-7s;s:45 aml Internauonal Decade of ocean crploranon. on the ruhjeet of application of the above e
.,e
.=
-,s m m,. A _. _,.,,,.
-e
29764 NO UCES calculations to pressurized water reac-(d) Questions may be propounded postponed or canceded since the last l tcts, such as the North Anna Power Sta-only by members of the Working Group of proposed meetings published in h' o
tion reactors, and its consultant 4.
Vol. 41. Monday. June 14,1976, pf i
7 At the conclusion of the open session.
(e) The use of still, motion picture. 24007. Those meetings that are definW.
i
)
the Working Group may caucus in a and television cameras. the physical in-scheduled have had. or will have. an t.
brief. closed seuion to determme whether stauntion and presence of which wiu not dividual notice published in the Pread the matters identified L'1 the initial closed interfere with the conduct of the meet-Rectsun approximately 15 days o
session have been adequately covered. Ing, wul be permitted both before and mores prior to the meeting. Those %
During the session, Working G roup. Ef ter the meeting and during any re-committee and Working Group meette.
members and consultants w1H discuss cess. The use of such equipment wiu not. for which it is anticipated that there E their opinions and recommendations on however, be allowed while the meeting be a portion or all of the meeting on[.
these matters. Upon conclusion of this Ls in session.
to the pubile are indicated by an aster.
.I l
caucus. the Working Group will meet (f) Persons with agreements or orders
(*). It is expected that the sessions < >
agMn in brief open session to announce permitting access to proprietary infor-the full Committee meeting designated t its determination, mation may attend portions of ACRS an asterisk ( *) will be open in whole or '-
I have determined, in accordance with meetings where this material is being part to the pubuc. Information u t l'
subsection 10(d) of Pub. L.92-463, that discussed upon confirmation that such whether a meetm; has been firn-11 is necessary to conduct the above agreements are effective and relate to scheduled, cancelled. or rescheduled 1 l
ched sessions to protect the free inter. the material being discussed.
whether changes have been made in il I change of internal views in the final The Executive Director of the ACRS agenda for the August 12-14.1976 ACrh stages of the Working Group's delibera. should be informed of such an agreement full Committee meeting can be obtame -
tive process (5 U.S.C. 552(b)(5)) and to at least three worklng days prior to the by a prepaid telephone call to the OfS i
protect confidential proprietary infor. meeting so that the agreement can be of the Executive Director of the Commi'.
mat. ton (5 U.S C. 552(b)(4)). Separation confirmed and a determination can be tee (telephone 202/634-1406, Attn: Ma~
l of factual material from individuals' ad. made regarding the appucabluty of the E. Vanderholt) between 8:15 a.m. and 5
~
vice, opinions, and recommendations agreetnent to the material that will be p.m. e.d.t.
- while closed Executive Sessions are in discussed duriny the meeting. Minimum progress is considered impractical.
Information provided should include in.
8 ""'"d*,'"8 0**
j Practical considerations may dictate formation regarding the date of the I
alterations in the above agenda or sched-agreement, the scope of material in.
, Peah.np rectors, July 21, resebeduH j
ule. The Chairman of the Working Group cluded in the agreement, the project or fr m Juif 19. 1976. Washington. DC to co:..
]
b empowered to conduct the meeting in {rojects involved, and the names and p,,",',
$,*,' g,me gtgasu l
es o the persons signing the agree-
. O manner that, in his judgment. will fa-bare been fabriented by combusuon Er.r.
cilitate the orderly conduct of business. Inent. Additionalinformation may be re-nering. Inc. Nouce hu been pubitsbed e including provisions to carry over an quested to identify the specific agreement PR vol. 41. July 1.1976. page 27140, and e.
Uncompleted open session from one day involved. A copy of the executed agree-ra Vol. 41. Julr 12.1976, page 28s99.
tnent should be provided to Mr. R.
- 3hfPpmpport atomic Power Stacton. Juw to the next'pect to public participation in Muun of the ACRS Of5ce, prior to the 21, 1976. corsopons. PA (announced in rn With res the open portion of the meeting, the f ol-beginning of the meeting-vot 41. June 14.1976, page 24008, as "t.trr lowing requirements shall apply:
copy og e transcript of the Water Breeder Rasetor." July 20,1976. Pit 9 burgh. PA) to mscuss matters related to t; *
(a) Persons wishing to submit written open portion of the meeting will be avail
- deretepnaent of the Light water breeder re.
statements regarding the agenda items able for inspection on or after August 12. actor to be tarta11ed in the shippinrpe 1976 at the NRC Pubbe Document Room. Nue!est Plant. Notice has been pubbsbed t.
may do so by providing a readily re-producible copy to the Working Group 1"17 E St., NW.. Washington. DC 20555. PR vot 41, July 1.1976. page 27138.
-t the beginning of the meetag. Com. at the Louisa County Courthouse, Ofnce
- Knerrency Core Coolme SF8 tem. IECC$'
'ments should be lunited o safety related of the County Administrator. Board of July 21,22. aac 2J.1976. Rictdand, W A m.
areas within the Cc Attee's purview. Supervisors. Lonisa. VA 23093, and at the '$d"$$5 gg,,yo yl {
rd *A Persons desiring to mail written corn. Aldertnan Library. Manuscripts Depart
- riew bule resesrrb concerning ECCS. Nout-gnents Insy do so by sending a readily ment. Univenity of Virginia. Charlottes-have t>een puttLsbed to FR Vol. 41, Jun.
reproducible copy the cof in time for v11:e. VA 22901.
1976, pages 27131 and 27138, and in rn v~
I consideration at this meeting. Com.
Copies of the ininutes of it.e'eneeting
- 41. July 12.1976. page 2assa.
ments postmarked no later than Ju!y 29, will be rnade avattsble for inspection at
- Waste Monacement, July 22 and 23. F 1978 to Mr. R. Muller ACRS, NRC, the NRC Public Document Rootn,1717 Washingwn. DC w new neent Nuew
]
Washington. DC 20555 will normally be H St.. NW. Washingtcn. DC 2C555 after,",f[' [3,
,[g fm*f.d l
e R
received in time to be considered at this November 5,1976. Copies may oc ob-wu:* * *"rement documents and plans N
- meeting, tained upon payment of appropriate tiee hu been pubitsbed to PR vol. 41 July.
I (b) These persons wishing to nwke an charges.
1976. pa.n 27139.
I eral statement at the meeting should Dated : July 15*1976*
July 29 and 30,"1976, " Idaho TaJ1s.' #
- 3' # #
"# D'#"#
ID a re-make a written request to do so,ident!.
fying the topics and desired presenta.
Jozrx C Hont, scheduled from July 28,29, and So.1976) t tion time so that appropriate arrange.
' Adtisory Committee
" * '(* * ^[,'*
I g,
ge
,d in art ments can be made. The Working Group Xanagement Oficer.
development and experimental programs N l
grill receive oral statements on topics
[rR Doc."6-20022 rued 7-16-76.8:45 ami
- t. lee bu been published in FR vot 41. JO relevant to the Committee's purview at 12.1976. pmCe 28595.
an appropriate time chosen by the Chair-
- Diablo Canyon Nucteer Power $fsf" man of the Working Group.
ADVISORY COMMITTEE ON REACTOR units J end t. rescheduled from August -
(c) Further information regarding SAFEGUARDS 1976 to etentattvely) August at and Sept
- topics to be discussed, whether the meet.
Preposed MeetinES
+44 noe worHar Group on Jteactor N j
i ing has been cancelled or rescheduled, the Chairman's ruling on requests for In order to provide advance informa. rure vessel Loadings. August 861976. Tore.
the opportunity to present oral state-tion regarding proposed meetings of Ottarlo. canada to conunue the revie; ments and the time allotted therefor can ACRS Subcommittees. Working Groups.
'[I
[%.
"1" D
be obtained by a prepaid telephone call and the full Committee, the following accident condittarts. Nouce.or this n#'
on August 4.1976 to the Of:ce of the preliminary schedule is being published. appears elsewhere in tats issue.
~
Executive Director of the Committee This preliminary schedule reflects the
.rcohna rectors, rescheduled froni o (telephone 202/634-1413. Attn: Mr. R.
current attuatior, taking into account ad-gust 6,1976 to August to.1976. WashhW Muller) betm een 8:15 a.m. and 5 p.m..
d1tional meetings which have been Dc to cor.unue alaeuuton or rnetho* '
e.d.t, scheduled and meetings which have been meuurtng power distribuuon in r#
I
. pgostAt ticistit. VOL 41. No.139 #0NDaf. NtY 19. MTe j
T, ggcewur B l
ACRS AD HOC WORV.ING GROUP ON REACTOR PRESSURE VESSEL SUPPORT LOADING - AUGUST 5,1976 RECEivto 9:00 Closed Meeting I
A.
Introduction 26 JU' 30 PM 4 35 9:15 B.
Background
U.S. N MShl,t;g,fgtri j 1.
Goals of Analysis 2.
Source of Loadings 3.
Description of Design Basis 4.
Interfaces 5.
Order ~of Technical Presentation 9:45 C.
Internals Forces - Multiflex Review 1.
Formulation of Equations and Verification of Code 1.1 Structural Modeling 1.2 MULTIFLEX 1.3 Blowdown Phenomena 1.4 Pressure Differentials ---- Structure 1 Effects 1.5 Usage of MULTIFLEX 2.
Mathematical Description 2.1 Overall Mathematic Model 2.2 Physical Meaning
- P-Wave Propagation
- Hydro-Elastic Interaction s.
2.3 Structural Equation ---- Model Technique 3.
Code Verification 3.1 'l-d p-wave Propagation 3.2 2-d p-wave Propagation 3.2.1 2-d Sheet 3.2.2 Inlet-nozzle /Downcomer Jont Y
I ^ Pa'ge #2 o
3.3 Bettis Test l
- Frequency & Amplitude 3.4 Simple Shaker-
- In-water Frequency & Amplitude 3.5 Fritz and Kiss Shaker
- In-water. Frequency 3.6 Barrel - Oscilla tion 3.7 CSE Analysis 11:00 QUESTION AND ANSWERLPERIOD 12:00-d Non-equilibrium Pressures 12:30 L U N C 11 1:30 Open Meeting j
E..
Reactor Vessel and Internals Structural Analysis 2:00 F.
Support Evaluation
,3:00 G.
NRC Staff Review of RPV Forces 4:30 H.
Executive Session (CLOSF.D) 5:00 Adjourn i
=;-
l I
k 4
9 0
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6-I.
fN cnw Mrs) wctosuae cp i
SUMMARY
OF NRC REVIEW PR0 CESS 1
'F0R THE ANALYSIS.
0F SUBCOOLED-DECOMPRESSION 4
l ANALYTICAL DEVELOPMENT APPLICATION AND SYSTEM MODELING CODE VERIFICATION s.
+
i l
08-05-76
- -.)
b~
ANALYTICAL DEVEL0PMENT BASIC CONSERVATION EQUATIONS CONSERVATION OF MASS CONSERVATION OF M0 MENTUM CONSERVATION OF ENERGY (EQUATIONOFSTATE)
REDUCED FORM 0F BASIC. CONSERVATION EQUATIONS ASSUMPTIONS USED TO REDUCE EQUATIONS NON-EQUILIBRIUM EFFECTS METHOD OF CHARACTERISTICS SOLUTION INCLUSION OF FLUID-STRUCTURE INTERACTIONS DESCRIPTION OF SYS1EM COMPONENTS HEAT TRANSFER - REACTOR CORE AND STEAM GENERATORS PRESSURIZER i
REACTOR COOLANT PUMPS NON-REC 0VERABLE ENERGY LOSSES
)
BREAK MODEL i
BREAK FLOW MODEL DISCHARGE COEFFICIENT
2 4-3 A N A L Y.T I C A L DEVEL0PMENT METHOD OF SOLUTION SOLUTION CONVERGENCE TIME STEP SENSITIVITY ITERATION SCHEMES DVERALL CONSERVATION MAINTAINED STEADY STATE CONDITIONS 4
4
_._,_________2_--
~
APPLICATION AND SYSTEM MODELING APPLICATION SUBC00 LED DEPRESSURIZATION ASYMMETRIC LOADS ON CORE SUPPORT BARREL RESULTING LOADS ON REACTOR PRESSURE VESSEL SUPPORTS VERTICAL LOADING 0F CORE ASSEMBLY SYSTEM COMPONENT LOADS REACTOR COOLANT PUMP STEAM GENERATOR PRESSURIZER 4
SYSTEM MODELING SENSITIVITYTON0 DING (SPACIALREPRESENTATION)
TREATMENT OF GE0 METRY LENGTH AREA VOLUME TREATMENT OF MULTI-DIMENSIONAL RE'GIONS
( CURRENT GENERATION OF CODES ARE 1 - DIMENSIONAL )
EQUIVALENT MULTI-DIMENSIONAL REPRESENTATION 2-DIMENSIONAL PWR 00WNCOMER ANNULUS OTHER MULTI-DIMENSIONAL REGIONS
. a..
hp - b>
C0DE VERIFICATI0N TREATMENT OF MULTI-DIMENSIONAL REGIONS I
EVALUATION OF EQUIVALENT REPRESENTATION
- SET OF 4 SAMPLE PROBLEMS - SIMPLE GE0 METRY ANALYZED WITH 2-DIMENSIONAL' CODES PERFORMED BY SANDIA CSQ AND T00DY RESULTS COMPARED WITH VENDOR CODES PROBLEM 1:
2-DIMENSIONAL SHEET PROBLEM 2:
2-DIMENSIONAL SHEET WITH OBSTRUCTION l
(HOTLEGPENETRATIONS)
PROBLEM 3:
N0ZZLE PENETRATION INTO DOWNCOMER REGION 1
PROBLEM 4: THERMAL SHIELD AND ORIFICE OBSTRUCTIONS ASSIST THE NRC IN ESTABLISHING GUIDE LINES FOR THE USE OF 1 - DIMENSIONAL CODES IN MODELING MULTI-DIMENSIONAL REGIONS 4
)
i
.y.
h C00E VERIFICATION COMPARISON WITH EXPERIMENTAL DATA PREDICT SUBC00 LED DECOMPRESSION EVALUATE MODELING IDENTIFY SIGNIFICANT MODELING FEATURES SELECTED TESTS CONTAINMENTSYSTEMEXPERIMENT(CSE)
TEST B - 63 TEST B - 75 SEMISCALE
. TEST S 6 TEST S 8 LOFT:
TEST L1 - 2 MODELED WITH PROPOSED PWR N0 DING CONFIGURATION 1
NRC ANA' LYSIS OF SELECTED TESTS INDUSTRY WIDE COMPARIS0N OF RESULTS i
4 NRC AUDIT CALCULATION USING GENERIC PLANT 1
ANY OTHER DATA APPLICABLE TO SUBC00 LED DECOMPRESSIOI i
t '-
_.______________________.J
L G-7 CODE VERIFICATION l
COMPARIS0N WITH EXPERIMENTAL DATA FLUID - STRUCTURE INTERACTION 1
l AMPLITUDE OF MOTION FREQUENCY OF RESPONSE AVAILABLE TEST DATA "THE VIBRATIONAL RESPONSE OF A CANTILEVERED CYLINDER SURROUNDED BY AN ANNULAR FLUID,"
R.J. FRITZ AND E. KISS, KAPL-M-6539, FEB. 1966
" HYDRAULIC PRESSURE PULSES WITH STRUCTURAL FLEXIBILITY: TEST AND ANALYSIS,"
D. A. PRELEWICZ, WARD-TM-1227, APRIL 1976 j
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