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'l NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20555 b,
ggy 131983 MEMORANDUM FOR:
Jesse L. Funches, Director Planning and Program Analysis Staff, NRR FROM:
Richard H. Vollmer, Director Division of Engineering, NRR
SUBJECT:
REVISION TO DE FIN PLAN In accordance with the procedures for processing modifications to approved FIN plans, I am providing justification for adding a new program to the DE technical assistance plan (FIN A3721).
This technical assistance is needed so that under this program, BNL can develop a computer program which can be used to quickly determine the definition of site specific power spectral densities, (based on acceleration values and other hazard parameters defined by seismological investigation, for further use in the structural analysis). These power spectral densities will be developed in such a manner that they account for local site conditions in a generic way, such as, soft, medium and rock sites. This power density function will then be used in the existing probabilistic structural code (RAS), which has been developed at BNL, to generate the response statistics with non-exceedance probabilities.
The results of this probabilistic analysis will be used as a supplementary basis to make licensing decisions.
RAS capabilities will also be enhanced to compute structural fragilities useful in PRA applications.
The FY-83 funds for this program should be reprogrammed from the NRR operating reserve.
Attached is a revised PID to document the action.
If you have any questions regarding this procurement request, please contact Mr. E.
Frigillana on X28377.
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! Richard H. Vollmer, Director Division of Engineering
Attachment:
Revised PID promded EoK b% OpeSnAewNR 8505230426 841002 PDR FDIA SHOLLYB4-243 PDR
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'LICAT'C" (RELATE THE PF0 JECT T0 A SPECIFI C PLANNED ACCOMPLISHPENT).
~ia :ny :7. cats,1:2 need rc cvaluate c::isting nuclecr p=.;cr plc:t structures to a redefined eis.mic hsaard. Tnis situatica is ccrenca in SEP plc.its l..,.e. :..e.%. :A,.,
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MPLICl.TIO:: (El!.TED TrE iCJ2CT TO A SP. CIFIC F?.'JED.'.CCG?I.Isic'S,'T) fashica (-:._.c th. une of daccnvelutica atf
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Since th ctru:te.rcs are already built, tea are interested in eva se n plants luating the actural safety 1.urgins existing in the design to revised seicmic hazard. Probabilistic analysis of structures provide excellent.tcol for. evaluating these safety nr.rgins in the qu:ntitative fo =.
For.any caalytical scheme of structural probabilistic calculations, rather than the Mcate Carlo optica, the seis-ic hazard needs to be defined in.the pcwar. spectral density (PSD) form. Tnis PSD is then further used in the structural analysis as discussed belo:7.
In additica, recent P?J.s have emphasized the i=ortance of scismic risk analysis. Tne cc puter cada develepad in this program.ull1.be used to trde ind2pandent analysis, particularly, in the crea of structral fragility..
Tne use of probabilistic structural analysis is reccz. ended,to supple ent the dete=inistic basis,in IIT2G/CR-0098xhich provides the guidelinas cn tiu accertsncs critdria for SEP. plants evaluation. Further, the results frca the effcit.to resolve USI A-40 also recomend the censideratica of the probabilistic._
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st:uctural analysis t.ith the critarica of 34% nonexcecdance. probability.. Tna pro:osed revisica of.SRP 3.7.2 endorses this.cencent as a supple entary basis.
Tne':.?R operating plan for FY S3, S4 and 85 also highli:; hts I'"EP and rid cssessr m t studies Tne EEP pcper discusses the need to incorporate exten'.al events in the probabilistic risk assessments,in the nes:t cne to tuo y.2:rs.
Thus, this project :.411 have direct applicatice in P.us.
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BROOXHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INd.
Upton. Long Island. New York 11973 (516) 282s 3317 Office of the Director FTS 666,.
March 9, 1983 Mr. David.Schweller, Manager Brookhaven Area Office U. S. Department of Energy Upton,~New York 11973 Daar Mr. Schweller:
Enclosed is one copy of a proposal to the Nuclear Regulatory Commission entitledr "Probabilist-ieResponse-and-Response-Spectra for Category I Struc tures,"
FIN A-3721,- being submitted for your review and approval.
The proposal is being submitted in response to a request from NRC dated January 26, 1983. Two copies have been sent to Mr. J. Maher, Department of Energy, one copy has been sent to Mr. B. L. Grenier, Nuclear Regulatory Commission, and two copies have
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been sent to:
Mr. Chester Poslusny, Program Assistant Office of Nuclear Reactor Regulation Mail Stop P-202 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 If there are any questions regarding the document, please call the prin-cipal investigator or Mr. A. J. Romano, FTS 666-4024, Department Administrator for the Department of Nuclear Energy.
Sincerely yours, bj H. C. Grahn l
Assistant Director for Financial Planning Enclosures cc:
C. Poslusny (2)
B.~L. Grenier #
'J. - Maher (2)-
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3 NRC PMM tes US. NUCLE AN HEGULATCAY COvlMISSION C AT E O P '8$o*oS A 6
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Ma.rCh 2, 1983
) PROJECT AND BUDGET PROPOSAL FOR NRC WORK Q NEn O atvi$io% %o
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- Pi;OJECT TITLE i 88N NUYSE m Probabilistic Response and Response Spectra for A-3721 Category I StruCeures
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NRC OFFICE Nuclear Reactor Regulation 20-19-50-53-2 CONT R ACTOR ACCQuNT coE CoNTaaCToa Associated Universities, Inc.
NuM8ER Brookhaven National Laboratorv New-4 site coE san muueEn Upton, New York d
COGNIZANT PE RSONN E L 08WANIZATION l
FTS PHONE NUMBER PE RIOO O F PE R F OR MANCE NRC PROJECT M AN AGER STARTING OATE G. Lear DE/EQB 492-8085 04/01/83 OTHER NFtC TECHNICAL STAFF COMPLETION OATE 04/01/85 Est.
OCE PROJECT M AN AGER Brookhaven
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David Schweller Area Office 666-3424
.i s 1l.7F.'.". $O CONTRACTOR-PROJECT MAN AGER H. J. C. Koutd 666-2815
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STAFF YEARS OF EFFORT (Round to nearest renrh of a years UFY Igg 3 lFY 1984 jFY 1985 fY iFY i
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Oirret Scientific /Tecnn css
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TOTAL DIRECT STAFP YEARS l
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COST PROPOSAL l
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i Probabilistic Response and Response Spectra for
'D Project
Title:
Category I Structuras P.3 PROJECT DESCRIPTION-a.
OBJECTIVE OF PROPOSED WORK (1) Background
' In many events, it is necessary for NRC to evaluate nuclear power plant s truc-tures to a redefined seismic hazard. For example, SEP plants and some recent OL plants,~ whose design basis was changed from original CP stage, fall into this category.
Since the structures are already built, it is in NRC's interest to evaluate the actual safety margins existing in the design to the revised seismic haza rd.
Probabilistic analyses of structures provides an excellent tool for evaluating these safety margins in a quantitative form. For any analytical scheme of structural probabilistic calculations, rather than the Monte Carlo Option, the seismic hazard needs to be defined in ths power spectral density (PSD) form. This PSD is then further used in the structural analysis as will be discussed below.
In addition, recent PRA's have emphasized the importance of seismic risk analysis. The computer code developed under this program will be used to make independent analysis, particularly, in the area of structural f rag 111ty.
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(2) Objective I
Under this' program, BNL will develop a computer program which can be used to quickly determine the definition of site specific power spectral densities (g values and other hazard parameters to be defined by GSB) for further use in the structural analysis. These power spectral densities will be developed in such a manner that they account for local site conditions in a generic way, such as, soft, medium and rock sites. This power density function will then be used in the existing probabilistic structural code (RAS), which has been developed at l
BNL, to generate the response statistics with non-exceedance probabilities. The results of this probabilistic analysis will be used as a supplementary basis to make licensing decisions.- - RAS capabilities will also be enhanced to compute structural fragilities useful in PRA applications.
b.
SUMMARY
OF PRIOR EFFORTS The RAS code has been developed in previous work carried out for NRC.
It will be updated to achieve the goal described in the objective above.
c.
WORK REQUIREMENTS Three major task areas are envisioned. The first involves the determination of seismic site specific power spectral densities; the second deals with the upgrading of the RAS computer code; while the third task concentrates on
. demonstration and application of the developed methodology to a nuclear power plant structure. The tasks are specifically as follows:
(See Continuation Sheet)
J b.
' ' ' - - - - - - ' ' ^ - ^
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o Probabilistic Response and Response Spectra for Project
Title:
Category I Structures P.5 c.
WORK REQUIREMENTS (Cont'd) j Subtask e.
Modify existing RAS program manuals to include a i
summary of the new theoreti?.a1 development and an updated user manual with pertinent information.
Subtask f.
Impletsent this program into the NRC/BNL systen and provide adequate training to NRC staff using this program.
Task 3: Demonstration and Verification of Methodology (two years from initiation of work).
Under this task, BNL will carry out a demonstration of the RAS code by applying the developed methodology to a nuclear power plant structure and thus demon-strate that the methodology can be used in an appropriate manner. A report will be written at the end of this task detailing all results of the application.
Level of Effort and Period of Performance The estimated level of effort for the work is 2.2 staff years, ending two years af ter initiation of work.
d.
REPORTING REQUIREMENTS BNL shall prepare the follow).ng:
1.
Af ter completing Task 1, 2, and 3, reports will be prepared as described
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earlier under work requirements. Reports will be due within 4 to 5 months ~
i af ter completion of the tasks.
- 2. - Original or legible copies of all notes, letters, codes, papers, books, and written or printed material gathered for the purpose of completing these tasks will be saved and sent to NRC if requested.
t Monthly Business Letter Report l
A monthly business letter report will be submitted by the 20th of the month to the NRR Project Manager with copies provided to the Director, Division of Engtaaering, ATTN: ?roject Assistant, Branch Chief, SGEB and B.L. Grenier, NRR.
These reports will insatify the title of the project, the FIN, the Principal Investigator, the period of performance, ac.J the reporting period and will '
t.
contain 2 _ sections as follows:
(See Continuation Sheet)
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Probabilistic Reponse and Response Spectra for Project
Title:
Category I Structures P.7 d.
REPORIING REOUIREMENTS (Cont'd) 3.
Provide the total amount of funds expended (costed) during the period and cumulative to date for each task.
1/ If the recommended resolution involves a Work Order modification, i.e, change in work requirements, level of ef fort (costs), or period of performance, a separate letter should be prepared and submitted to the Director, Division of Engineering, ATTN:
Program Assistant, and a copy provided to the NRR Project Manager and B.L. Grenier, NRR.
2/ Provide percentage agairist total funds obligated to date.
e.
MEETINGS AND TRAVEL Approximately, three meetings (involving three to four BNL employees) of one/two day de ation each are anticipated in Bethesda during the contract period of perfo rmance. One will be held at project initiation to discuss the scope of the of fo rt.
In addition, one trip to one plant site may be required.
f.
NRC FURNISHED MATERIALS NRC will provide to BNL copies of topical reports, portions of SAR's details and drawings of selected plant on an as-required basis.
g.
DESCRIPTION OF ANY FOLLOW-ON EFFORTS Not applicable.
h.
RELATIONSHIP TO OTHER PROJECT This work is somewhat related to probability-based load combinations for design of category I structures work currently being carried out by BNL. for Nuclear Reactor Research.
1.
SUBCONTACTOR INFORMATION Two subcontracts are envisioned, one of these will be with Prof. M. Shinozuka of Columbia University and the other with Prof. A. Ang of the University of Illinois. The exact amounts are as yet undetermined.
l (See Continuation Sheet) j l
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