ML20102A788

Regulatory and Technical Reports (Abstract Index Journal). Compilation for First Quarter 1992,January-March

ML20102A788
Person / Time
Issue date:	06/30/1992
From:	NRC OFFICE OF ADMINISTRATION (ADM)
To:
References
NUREG-0304, NUREG-0304-V17-N01, NUREG-304, NUREG-304-V17-N1, NUDOCS 9207270307
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NU REG-0304 Vol.17, No.1

__r-Regula~ory anc Technical Reaor"s

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Available from Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, D.C. 20013-7082 A yuar's subscription consists of 4 issues for this publication.

Single copies of this publicatics

- are available from National Technical Information Service, Springfield, VA 22161

NUREG-0304 Vol.17, No.1 Regulatory and Technical Reports (Abstract Index Journal)

Compilation for First Quarter 1992 January - March Date Published: June 1992 Regulatory Publications llranch Division of Freedom ofInformation and Publications Services Omce of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555 f - g,

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CONTENTS Preface.......

,........................... v index-Tab Main Citations and Abstracts................

.......'1

• Staff Reports -

'

• Conference Proceedings

• Contractor Reports -

• International Agreement Reports

.... 2 Secondary Report Number index...

Personal Author inde x.................,.......

'3 S u bject ind ex..................................

.. 4 NRC Originating Organization index (Staff Reports).......

............... 5 NRC Originating Organization Index (International Agreements)...,,....

6 NRC Contract Sponsor Index (Contractor Reports).

7 Contractor index......

.... 8 International Organization index.

.9 Ucensed Facility lndex,.....................

....... 10 iii

PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commiwion (NRC) Staff and its centractors it is NRC's intention to publist this compilation quarterly and to cumulate it annually. Your comments will be ap-preciated. Please send them to:

Technical Publications Section Regulatory Publications Branch Division of Freedom of Information and Publications Services P-223 U.S. Nuclear Regulatory Commission Washington, O.C. 20555 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG XXXX, NUREG/CP-XXXX, NUREG/CRWXXX, and NUREG/lA-XXXX. These precede the following indexes:

Secondar'/ rwo t Number index Personal A. thor index Subject index NRC Originating Organization index (Staff Reports)

NRC Originating Organization Index (International Agreemente)

NRC Contract Sponsor Ir.dex (Contractor Reports)

Contractor Index International Organization Index e

Licensed Facility Index A detailed explanation of the entrias precedes each iridex.

TM bibliographic elements of the main citations are the following:

~

Staff Report NUREG-0808: MARK ll CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA.

ANDERSON, C.J. Dividon of Safety Technology. August 1981. 90 pp. S109140048. 09570:200.

Who;e the entries are (1) report number, (2) report title, (3) report author, (4) organizational uait of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the micretiche address (for internal NRC use).

Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABILITY ENGINEERING IN NUCLEAR REGULATION. JANERP, J.S. Argonne National Laboratory. May 1981.141 pp. 8105280299. ANL-813. 08632:070.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Docu-ment Control System accession number, (8) the report number of the originating organization, (9) the microfiche address (for NRC intemal use).

Contractor Report NUREG/CR-1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R.

Sandia Laboratories, f'ay 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.

Where the entries are (1) report number, (2) report title, (3) report authors, (4) organizational unit of authm or DJblisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC internal use).

v

l International Agreement Report

/

NU REG /l A-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL D ATA. NEUMANN, U. Kraf twerk Union. Augus.

66. 223 pp. 8608270424. 37659:138.

Where the entries are (1) report number, (2) report e, (3) report author, ( 4) organizational unit of author, (5) date report was published (6) number of prps in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization hf givenl, and (9) the microfiche oddress (for NRC internal use).

The following abbreviations are used to identify the document status of a report:

ADD addendum APP

- appendix DRFT - draf t ERR errata N - number R

revision S - supplement V

volume Availabihty of NRC Publications Copies of NRC staff and contractor reports may be purchased mther from the Govemment Ponting Office (GPol or frorn the National Technical information Service, Spnngfield, Virginia 22161. To purchasa documents from the GPO, send a check or money order, payable to the Supenntendent of Documents, to the following address:

Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCaro charge card, or VIS A charge card by calling the GPO on (2021275-2060 or (202)275-2171. Non U.S. customers must make payment in advance either by International Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.

NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff generated report. Contractor-prepared formal NRC reports carry the report code NUREG/CR XXXX. This type of identification replaces contractor-established codes such as ORNL/NUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship of the work being reported.

In addition to the NUREG and NUREG/CR codes NUREG/CP is used for NRC-sponsored conference proceedings and NUREG/lA is ' med for international agreement reports.

All these report codes are controlled and assigned by the staff of the Publishing and Translations Section of the NRC Division of Publicationn Services.

vi

Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG XXXX is an NRC staff originated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CR XXXX is an NRC contractor-prepared report and NUREG/lA XXXX is an inter-i national agreement report. The bibliographic information (see Preface for details) is followed by a brief abstract of this report.

NUREG-0020 V16: UCENSED OPERATING REACTORS STATUS tons informaton in this report includes inventory difference

SUMMARY

REPORT. Data As Of December 31, 1991 (Gray data for active fuel fabncaton facilities possess'ng more than Book 1) HARTF' ELD.R A. Divis.on of Computer & Telecommuni-one effecbve kilogram of high enriched uranium low ennched cations Services (Post 890205L Merch 1992. 350pp.

uranium, plutonium, or uranium 233 9204 % 0300.61230:308.

NUREG-0540 V13 N11: TITLE UST OF DOCUMENTS MADE The Nuclear Regulatory Commission's annual summary of b.

PUBUCLY AVA'LABLE. November 1 30, 1991.

• Dvmon of censed nuclear power reactor data is besod pnmanly on the Freedom of Information & Pubhcadons Services (Post 890205) report of operating data submitted by heensees for each unit for January 1992. 296pp 9202110288 60541284 the month of Decembet because that report contains data for This document is a monthly putAcation containing descrip-the month of Decembor, the year to date (in this case calendar tons of informaton received and generated by the U S Nuclear year 1991) and cumutabve data, usually from the date of com.

Regulatory Commiss on (NRC) This inf~rmon +ncludes (1) morcial operation. The data rs not independent?y venfied, but doce matena! associated with cne num.awer piants vanous computer checks are made. The report is dmded into and other uses of radcactive mWlats, a o (2i nondocketed n

two sections. The first contains summary highhghts and the matenal reemvod and generated by NRC portnant to its role as second contDns data on each individual unit in commercial op.

a regulatory agency. The following indenes are included. Per-eration. Section 1 capacity and availabihty factors are simple sonal Author, Corporate Source, Report Number, and Cross enthmetic averages Section 2 iter 7 in the cumulative column Reference of Enclosures to Poncipal Documents are generalty as reported by the licensee and notes as to the use of weighted averages and starting datos other than com-NUREG-0540 V13 N12: TITLE LIST OF DOCUMENTS MADE mercial operation are provided.

PUDUCLY AVAILABLE. December 1-31, 1991.

• Dmsson of NUREG-0040 V15 N04: LICENSEE CONTRACTnR AND Freedom et Infamation & PutAcatons Services &ost 890205)

VENDOR INSPECTION STATUS REPORT. Quarter 1y February 1992. 335pp 9202270144. 60716.287.

Report, October December 1991.(White Book)

• Division of Re-See NUREG-0540.Vt3.N11 abstract actor inspection & SPeguards (Post 870411). January 1992.

NUREG-0540 V14 N01: TITLE LIST OF DOCUMENTS MADL 331pp 9202120151. 60555:002.

PUBLICLY AVAILABLE. January 1 31, 1992.

• Dmston of Infor.

This penodical covers the results of inspecbons performed by mahon Support Services IPost 890205) March 1992. 307pp.

the NRC's Vendor Inspection Branch that have been distnbutod 9204060305 61230 00).

to the inspected organi2 m dunng the ponod from October See NUREG.0540N13 N11 abstract through Decembor 1991.

NUREG 0750 V34101: INDEXES TO NUCLEAR REGULATORY NUREG-0325 R15: U.S, NUCLEAR REGULATORY COMMISS:ON COMM!SSION ISSUANCES J4 September 1991,

• Divmon of FUNCTIONAL ORGANIZATION CHARTS. January 31, 1992,

• Freedom of Information & Pubiications Services (Post 890205).

Otc of Personnel (Post 070413). February 1992. 65pp.

January 1992. 5 !pp. 9202060417. 60494 001.

9204100058. 61288.306 Digests and indenes for issuances of the Commission. the Functional organization charts for the U S. Nuclear Regulatory Atomic Safety and Ucensing Board Panel, the Admintstrative Comrnission offices, divisions, and branches are presented.

NUREG-0386 D06 Rot; UN'TED STATES NUCLEAR REGUL4 t n u a ae r nte TORY COMM:SSION STAFF PRACTICE AND PROCEDURE DIGEST Commission, Appeal Board And Ucensing NUREG-0750 V34 N05: NUCLEAR REGULATORY COMM:SSION Decisions. July 1972 March 1991.

• Offico of the General ISSUANCES FOR NOVEMBER 1991 Pages P61295

• Dyson Counsel (Post 860701). February 1992. 728pp 9203250316.

of Freedom of Inicrmation & PutAcahons Servces (Post 61088:232.

890205) January 1992 42pp 9202060465. 60494 032.

This revision of the SMh edition of the NRC Practice and Pro-Legalissuances of the Commisson, the Atomic Safety and U-cedure Digest contains a digest of a number of Commission.

Censing Board Panel, the Admin.strative Law Judges, and NRC Atomic Safety and Ucensing Appeal Board, and Atomic Safety Program Officos are presented.

and Ucensing Board decisions tssued during the period of Jufy NUREG-0750 V34 N06: NUCLEAR REGULATORY COMMISS!ON 1.1972, to Marr'h 31, 1991, interpenting the NRC's Rules of ISSUANCE $ FOR DECEMBER 1991 Pages 297 376

• Dwson Practice in 10 CFR Part 2.

of Freedom of Information & Pubhcat;ons Services (Post NUREG-0430 V11: LICENSED FUEL FACILITY STATUS 890205) February 1992. 87pp. 9203270098. 61102135.

REPORT. Inventory Difference Data. July 1, 1990 June 30, ge, gyggg,0750V34 N05 abstract 1991.(Gray Book II) JOY,0.: BROWN.C. Office of Nuclear Mate-NUREG 0750 V35 N01: NULLEAR REGULATORY COMM!$SION nal Safety & Safeguards March 1992. 18pp 9203250277.

ISSUANCES FOR JANUARY 1992 Pages 1-40.

• Dmsicn of 61087:154.

NRC is committed to the pe'iod'c pubhcation of bcensed fuel Freedom of informaton & Pubhcabons Services (Post 890205) facihtes inventory difference data. following agency rewew of March 1992. 52pp 9204130029 6t315 020.

the information and completion of any related NRC investiga-See NUREG 0750N34.N05 abstract 1

.__.~ _

2 Main Citations and Abstracts NUREG-0847 S08: SAFETY EVALUATION REPORT RELATED NUREG 1214 RC9: HISTOR! CAL DATA

SUMMARY

OF fHE SYS-TO THE OPERATION OF WATTS BAR NUCLEAR TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE.

PLANT, UNITS 1 AND 2 Docket Nos 50490 And 50 391(Ten-ALLENSPACH.F. Divison of Licensee Performance & Quality nesse Vailey Authonty) TAM.P S. Division of Reactor Protects -

Evaluation (Post 870411) February 1992 123pp 9203170266.

1 / 11 (Post 870411). January 1992. 84pp. 9201310311.

60947:010.

60442:129.

The Histonca! Data Summary of the Systematic \\ssessment Supplement No. 8 to the Sately Evaluation Report for the ap.

of Licensee Performance (SALP) is produced penodica!Iy by the phcation filed by the Tennessee Valley Authonty for license to US Nuclear Regulatory Comrmssion This summary provides operate Watts Bar Nuclear Plant, Units 1 and 2. Docket Nos the results of the assessment for each facihty by NRC region 50 390 and 50-391, located in Rhea County, Tennessee, has and is further deded into the following sections. Secton 1 pre-been prepared by the Office of Nuclear Reactor Regulation of sents the most recent SALP report ratings for facilities in oper.

tne Nuclear Regulatory Cornmisson,.The purpose of this bup-aton and under construct 6on; Section 2 presents a chronologo piement is to update the Safety Evaluaton of (1) additional in_

cal listing of an SALP report ratings for each operating facihty; formaton submitted by the applicant since Supplement No 7 Section 3 presents a chronologica! hsting of al1 SALP repo i rat-was issued, and (2) matters that the staff had under review ings for each facihty under construction. For histoncal purposes, when Supplement No. 7 was issued.

past constructon rabngs for facihties that recently have beon b-censed also are listed in Section 3 HUREG-0936 V10 N04: NRC REGULATORY AGENDAOuarterly Report, October-December 1991.

• Dmsson of Freedom of Infor.

NUREG 1324: PROPOSED METHOD FOR REGULAllNG MAJOR maton & Pubkations Services (Post 890205). February %92.

MATERIALS LICENSEES HAUGHNEY C.J.;

BROWN.W D ;

128pp. 9202240156. 60669155 ROTH.J.; et al Othce of Nuclear Matenal Safety & Safeguards.

The NRC Regulatory Agenda is a comodaten of all rules on February 1992. 67pp. 9202240161. 60669.283 which the NRC has recently completed action, or has proposed The Director. Othce of Nuclear Matenaf Safety and Safe-actioq, or is considenng action, and all petitions for rulemaking guards. U.S Nuclear Regulatory Commission, appointed a Ma-which have been received by the Commission and are pendeng tenals Regulatory Review Task Force to conduct a broad-based dispositen by the Commission. The Regulatory Agenda is up-review of the Commission's current hcensing and oversight pro-dated and issued each quarter.

grams for fuel cycle and large materials plants. The task force, as requested, defined tne components and subcomponents of NUREG-0940 V10 N04: ENrORCEMENT ACTIONS: SIGNIFI, an ideal reguiatory evaluaton system for those types of li-CANT ACTIONS RESOLVED.Ouarterly Progress consed plants and compared tnem to the components and sub-Report. October December 1991.

• Ofc of Enforcement (Post components of the existing regulatory eva!uation system This 870413). March 1992. 325pp. 9204060293. 61232:051.

report discusses findings from this companson and pronosed This compilation summanzes significant enforcement actions recommendatons on the basis of these find.ngs that have been resolved dunng one quarterfy penod (October

• December 1991) and incksdes copies of letters, Notices, and NUREG 1449 DRFT FC: SHUTDOWN AND LOW-POWER OPER-ATION AT NUCLEAR POWER Pl. ANTS tN THE UNITED Orde's sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that STATES Draft Report For Comment.

• Dmson of Systems the information in this publicaten will be widely disseminated to Technology (Post 890827). February 1992.225pp 9202260237.

60707:143 managers and employees engaged in actmties licensed by the NRC, so that actions can be taken to improve safety by avosd-The report contains the resutts of the NRC staff's evaluation ing future violations smiar to those desenbed in this pubhca-of shutdown and low power operatens at commercial nuclear ower plants in the United States. The report descnbes studies conducted by the sta'! in the following areas: operating expen-NUREG-1100 V08: BUDGET ESTIMATES Fiscal Year 1993.

• De ence related to shutdown and low-power operatens, probabiks-vision of Budget & Analysis (Post 890205). January 1992.

tic nsk assessment of shutdown and low. power conditions and 185pp. 9202180162. 60644.275 utthty programs for planning and conducting actNities dunng pe-This report contains the fiscal year budget justification to Con.

"O gress The budget provides estimates for salanes and expenses and for the Office of the inspector General for fiscal year 1993.

low-power operations performed by the staff, including the pnn-cipal findings and conclusions. Potential new regulatory require-NUREG-1135 S01: SAFETY EVALUATION REPORT RELATED rnents am discusse, as am ptental chap in E po TO THE CONSTRUCTION PERMIT AND OPERATING LI-gm is cunenW a &au W M ts cm CENSE FOR THE RESEARCH REACTOO AT THE UNIVERSI-

' **#8 "" " "E

• • *W" TY OF TEXAS. Docket No. 50-602(The Lntversity Of Texas)

• Dvsion of Advanced Reactors & Special Projects (901216-020516). January 1992. 80pp. 9202120148. 60548.178-NUREG/Cp-0121: AGING RESEARCH INFORMATION CONFER-The Office of Nuclear Reactor Regulation of the U.S. Nuclear ENCE - ABSTRACTS OF PAPERS. BERANEK,A. Division of Regulatory Commission (NAC; has prepared Supplement 1 to Engineenng (Post 870413t March 1992. 87pp. 9203250301.

NUREG-1135. " Safety Evaluation Report Related to the Con-61086:162.

struction Permit and Operaton License for the Research Reac-This report contains abstracts of papers to be presented at tor at the University of Texas" (SER) May 1985. The reactor fa-the Ageng Research Informaten Conference to be held at the cility is owned by The University of Texas at Austin (UT. the ap-Hohday Inn Crowne Plaza in Rockville. Maryland, on March 24-pbcant) and is located at the University's Balcones Research 27,1992. This conference is held to d!sseminate research re.

Center in Austin. Texas This supplement to the SER (SSER) suits in the area of nuclear po-cr plant aging from programs descnbes the changes to the reactor facihty design from the de-sponsored by the Office of Nuclear Regulatory Research, U S senption in the SER. The SER and SSER together reflect the Naciecr Regulatory Commission. The conference wdi also pro-facihty as built The SSER also documents the reviews that the vide an opportuntty for engineers and scler.tists from around the NRC has completed regarding the appiscant's emergency pian, wond to exchange technical information and discuss future secunty plan. and techntcal specificatons that were identif'ed as international cooperation. The abstracts appear in the order in open in the SER.

which they wdl be presented at the conference, and they are

Main Citations and Abstracts 3

grouped by technical session. The full papers and the agenda fractu e-prevent on marg:ns in commercial nuclear reactor pres-for the conference will be published as separate documents sure vessels Reorgan;2ation cd the ongms! HSST Program into separate programs with emphasis on fracture-mechanics tech-NUMEG/CR 2000 V10N12: LIC"NSL FVENT REPORT (LER) nology (HSST) and matenalsarraiation effects (HSSI) was pre-COMPILATIOtt.For Month Of teecamber 1991.

• Oak RiJge Na-vlously completed The reviseu HSST Program is orgamzed in tonal Laboratory. Janua y 1992. 69pp 920212013V ORNL/

10 tasks: (1) prograrn management (2) fracture methodology NSiC-200 60548:107.

and analysis. (3) matenal charactenzation and properties. (4)

This montnly report contains Ucensee Event Report (LER) speoat technical assistance. (5) crack-arrest technology, (6) operational informaton that was processed into the LER data cleavage crack initiaton, (7) cladding evaluatons (8) oressur-fde of the Nuclear Safety Informaton Center (NSIC) dunng the ired thermal-shock technology, (9) analysis methods vahdat on, one month penod identified on the cover of the document. The and (10) fracture evaluaton tests The piomam tasks have LERs, from which this informahon is denved, are submitted to been structured to place emphasis on the resolution fracture the Nuclear Regutatory Comrnission (N9C) by nuclear power issues mth near term bcensing sign!ficance. Resources to ene-plant heensees in accordance with federal regutatens Proce, cute the research tasks are drawn from ORNL wth subcontract dures for LER reporting for revisions to those events occurnng support from univers: ties and other research laboratones Close prior to 1984 are described in NRC Regulatory Guide 116 and contact is maintained *:th reiated research programs both in NUREG-0161, "Instrucbons for F aparation of Data Entry the Uruted States and abroad Shots for Licensee Event Repov.

• Por thase events occumng on and after January 1,1984, LERS are being subruted in ac.

NUREG/CR 4551 V2R1P3: EVALUATION OF SEVERE ACCI-cordance with the revised rule contained in Title 10 Part 50.73 DENT RISKS. QUANTIFICATION OF MAJOR INPUT of the Code of Federal Regulations (10 CFR 50.73 - Licensee PAR AMETERS Experts' Determinaton Of Structural Response Event Report System) wNch was pubhshed in the Federal Reg-tssues. BREEDING.Rl; HARPER,F.T, BROWN.T D.; et al ister (Vol 48 No.144) on July 26,1983. NUREG 1022. "LF Sandia Natonal Laboratones March 1992.282pp 9204060038 consee Event Report System Desenption of Systems and SAND 861309. 61233 016 Guidehaes for Reporting." provides supporting guidanco and in.

in support of the NA war Regulatory Commisson's (NRC's) formation on the revised LER rule, The LER summanes in this assessment of the nsk from severe accidents at commercial nu-report are arranged alphabetically by facihty name and then clear power plants in the U.S reported in NUREG 1150, the chronologically by event oate for each fadity Coenponent, Severe Accident Risk Reducten Program (SAAPP) has com-system, keyword, and component vendor indexes follow the pleted a revised calculation of the nsk to the general pubhc summa ies Vendors are those identfod by the utshty when the from severe acodents at five nuclear power plants Surry, Se-LER form is initiated, the keywords for the component, system, quoyah, Zion, Peach Bottom, and Grand Gulf. The emphasis in and general keyword indexes are assigned by the computer this risk analysis was nt on determining a "so-called" point es.

using correlation tables from the Sequence Crr%o and Search timate of nsk, Rather. It was to determine the distribution of risk.

System, NUREG/CR 2000 V11 N1+ UCENSFE EVENT REPORT (LER) this distnbution. Off-site nsk irut ation by events, both internal to COMPILATION For Month Of Ja mary. 92.

• 1ak Ridge Na-the power staton and erternal to the power staton were as-tional Laboratory. February 1992. 62pp 92031wo99 ORNL/

sessed Much of the important input to the logic models was NSIC-200. 60906 070 generated by expert panels. This document presents the distn-See NUREG/CR 2000,V10,N12 abstract.

butons and the rationale supporting the distnbutions for the NUREG/CR 2850 V10: POPULATION DOSE COMMITMENTS questions posed to the Structural Response Panet.

DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER HUREG/CR 4554 V01 R1; SCANS (SHIPPING CASK ANALYSIS PLANT SITES IN 1968. BAKER,0.A. Battelle Memonal Institute l SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM Pacific Northwest Laboratory, January 1492 184pp FOR SHIPPING CASK DESIGN REVIEW User's Manua; To Ver-9202120150 PNL 4221. 60548:249 son 2a (Including Prograrn Reference) GERHARD,M A,;

Populaton radiaton dose commitments have been estimated TRUMMER,DJ; JOHNSON G L.; et al. Lawrence Uvermore Na-from reported ladionuctide releases from commercial power re.

tional Laboratory. February 1992. 207pp 9203250286. UDO-actors operating dunng 1988 Fifty-year dose commitments from 20674. 61088-025.

a one-year exposure were calculated from both hquid and at, SCANS (Shipping Cask ANatysis System) is a rrucrocomputer-mosphenc releases for four population groups (infant, child, based system of computer programs and databases developed teenager and aduft) residing between 2 and 80 km from each of at the Lawrence Livermore Nabonal Laboratory (LLNL) for eval-71 sites. This report tabulates the results of these calculations, uating safety analysis reports on spent fuel shipping casks.

showing the dose commitments for both hquid and airborne SCANS is an easy-to-use system that caicutates the global re-pathways for each age group and organ. Also included for each soonse to impact loads, pressure loads and thermal conditions, of the sites is a histogram showing the fracion of the total pop, providing reviewers with an independent check on analyses u!aton within 2 to 80 lim around each site receiving varous av.

submitted by hcensees. SCANS is based on microcomputers erage dose commitments from the airtome pathways. The total compatiole with the IBM-PC family of computert The system is dose comrnitments (from both liquid and airborne pathways) for composed of a series of rrienus, input programs. cask analysis each site ranged from a high of 16 person-rem to a low of programs. and output display programs All data is entered 0.001 person rem for the sites with plants operating throughout tnrough fill-in-the-blank input screens that contain descnptive the year with an anthmetic mean of 1.1 person-rem. The totaf data requests. Analysis options are based on regulatory cases population dose for all sites was est. mated at 75 person-rem desenbed in the Code of Federal Regulations (1983) and Regu-for the 150 milhon people considered at nsk.

latory Guides pubhshed by the U S. Nuclear Regulatory C;m-NUREG/CR-4219 V08 N1: HEAVY-SECTION STEEL TECHNOL-misson in 1977 and 1978 OGY PROGRAM Semiannual Progress Report For October 1990 March 1991, PENNELL,W E. Oak Ridge National Labora-NUREG/CR 4554 V03 Rt: SCANS (SHIPPING CASK ANALYSIS tory. February 1992 82pp. 920221034L ORNL/TM-9593 SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM 60659 005.

FOR SHIPPING CASK DESIGN REVIEW Theory Manual (Lead The Heavy Section Steel Technology (HSST) Program is con-Slump in impact Analysis And Venfication Of impact Analysis?

ducted for the Nuclear Regulatory Commesson (NRC) by Oak CHUN.R.C ; LO T; MOK.G C.; et 81 Lawrence Uvermore Na-R.dge National Laborato y (ORNL) The program focus is on the tional Laboratory Februa y 1992 103pp 9203250288 UCID-development and vahdation of technoicgy for the assessment of 20674 61087.174

1 i

4

- Maln Citations and Abstracts A computer system caHed SCANS (Shipping Cask Analysis reactor (PWR) water, and an air. Crack growth rates (CGRs) of I

System) has been developed for the staff of the U S Nuclear composite specimens of A533-Gr B/inconeL192/Inconel-600 Regulatory Commission to perform confirmatory licensng review (plated with n ekel) and homogeneous specimens of A533-Gr B analyses SCANS can handle probleus associated with impact were determined under small-amphtude cyche loading m HP heat transfer, thermal stress, and pressure. A new methodology water with = 300 ppb dissoNed oxygen. CGR tests on sensi-was developed to p"ow SCANS to anatyre the lead slump be-tized Type 304 SS ind.cate that low chromate concentrabons in havior of lead-shielded Casks dunng a postulated impact with an BWE water (25 35 pg,, may actualty have a benehcial effect on unyielding surface. The methodology is an expansion of the ex-SCC If the sulfate concentration is below a cntical level Micro-isting lumped-parameter impact analysis method. In the new ChemCal and microstructural Changes in HP and commercial-i methodology, it is assumed that the lead and the steel cyhnders punty Type 304 SS specimens from controt. blade absorber are not bonded as opposed to the existing bonded-lead as-tubes used in two oporating BWRs were studied by Auger elec-sumpton. The lead shield is allowed to shde freely relative to tron spectroscopy and scanning electron microscopy, and slow-the steel cylinders and interact with the steel cyhnders on!Yh strain rate-tensile tests were conducted on tubular speciment in the radial direction of the shipping cask. The lead slump meth-air and it simulated BWR water at 289 degrees C.

odology des,nbed in this revision (Rev.1) of the report is an improved verson of the method documented in the original NUREG/CR-5229 V04: FIELD LYSIMETER INVESTIGATIONS:

- report. The main 4mprovement is in the modeling of the lead be-LOW LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM havior. To minimize mathematical difficulty and development FOR FISCAL YEAR 1991. Annual Report. MCCONNELL.)W.;

cost, the lead was formorfy treated as an elastic matenat with ROGERS.R.D.; JASTROW.J D.; et al. EG&G Idaho. Inc. January an effective modulus which was tuned to account for the eNect 1992. 62pp. 9202t 10294. EGG-2577. 60540 247.

of plastic deformation occurnng in a cask drop. Although this The Field Lysimeter investgations= Low. Level Waste Data method gave satisfactory resuus for 30-ft accident drops, it pro-Base Development Program, funded by the U.S Nuclear Regu-duced overconservattve predictions tot 1-to 4 ft normal drops.

latory Commission, is (a) studyttw *he degradation effects in Thus, the present revision of the method was undertaken to im-EPICOR il organic iork exchange resins caused by radiation (b) prove the range of applicability of the method. In the improved examining the adequacy of test procedures recommended 6n method desenbod in this report, the lead is treated as an elas-the Branch Technical Positen on Waste Forms to meet the re-

' > plastic matonal and the actual elastic plast:C properties of quirements of 10 CFR 61 using soMfied EPICOR-Il resins, (c) eead are used instead obtaining performance information on Sohdified EPICOR-It sorw NUREG/CR-4627 R02: GENERIC COST ESTIMATES. Abstracts exchange resins in a disposal environment, and (d) determining the conditon of EPICOR-il kners Results of the sixth year of From Generic Studies For Use in Prepanng Regulatory impact Anatyses. SCIACCA,F Science & Engineenng Associates, Inc.

data acquisition from the field testing are presented and dis-February 1992.

41pp. 9203250297, SEA 87-25308-A:P_

costed. During the continuing field testing, both Portland Type t-61087:338.

11 cement and Dow vinyl ester. styrene waste forms are being tested in fysimeter arrays located at Argonne Natonal Laborato-The Nuclear Regulatory Commisseon has sponsored a number of generic cost estimating studies. These studies were ry (ANL-E) in lihnois and Oak Ridge Natonal Laboratory prepared to aid NRC analysts in prepanng Regulatory impact (ORNL). The study is designed to provide continuous data on Analyses (RIA's). These genene studies provide cost estimates nuchde release and movement, as well as environmental condi-that would have wide apphcation to a large number of Requia.

tions, over a 20-year penod.

tory Analyses being performed throughout the NRC and deal NUREG/CR-5303 vot: SYSTEM ANALYSIS AND RISK ASSESS-(.

pnmanly with repair and modification activities that may be im-MENT SYSTEM (SARA) VERSION 4 0. Reference Manual posed on nuclear plants as a result of regulatory actions. Ab-RUSSELL,K.D; SATTISON,M.B4 SKINNER,N.L4 et al. EG&G stracts of each of the gonenc cost estimating studies have been Idaho, Inc. February 1992. 248Pp. 9203170293. EGG.2628.

prepared and assembled in this catalog. These abstracts 60 present the results of the more detailed studies in a compact, ument is the reference manual for the System Analy-easdy understood and readily useable format. Individual ab-sis and Risk Assessment (SARA) System Verson 4 0, a micro-

~ stracts have been developed to treat the main-hne top:cs of the P

Y g

g g

g, genene studies. In addition, abstracts have been prepared cov-famdy [ie., a power plant, a manufactunng facihty, any facihty on enng irr:portant sub-topics or " stand-alones" which are of broad which a probabilist:c nsk assessment (PRA) might be per-interest in RfA preparation This abstract catalog updates and formed). The SARA data base contains PRA data for the domi-revises informaton presented in NUREG/CR-4627, Rev.1. The nant accident r,equences of a family and desenptive information catalog will be expanded and modified as additional genenc cost studies are completed and as abstracts are modified to re, about the famdy includmg event trees, fault trees. and system model diarams. The number of facihty data bases that can be

. flect updated conditions.

accessed is hmited only by the amount of disk storage avail-l

NUREG/CR 4667 V13

. ENVIRONMENTALLY ASSISTED CRACK-able. To simulate changes to famdy systems SARA users j

ING IN LIGHT WATER REACTORS. Semiannual Report Apnb change the failure rates of initiating and basic events and/or September 1991. KASSNER,T.F4 RUTHER.W E4 CHUNG H.M4 modify the structure of the cut sets that make up the event et al. Argonne National Laboratory. March 1992. 48pp.

trees, fault trees, and systems. The user then evaluates the ef-9203270025. ANL 92/6. 6110f:161.

fects of these changes through the recalculaton of the resultant This report summanzes work performed by Argonne National accident sequence probabilities and importance measures. The Laboratory on fatigue and environmentally assisted cracking in results are displayed in tables and graphs.

hght water reactors during the grx months from Apnl 1991 through September 1991. Topics that have been investigated NUREG/CR-5303 V02: SYSTEM ANALYSIS AND RISK ASSESS-dunng this penod include: (1) f atigue and stress corrosion crack.

MENT SYSTEM (SARA)

VERSION 4.0.Tutonal.

ing (SCC) of low-allo / steel used in piping and in steam genera-SATTISON MLB.; RUSSELL,K.D.; SKINNER N L EG&G Idaho, tor and reactor pressure vessels; (2) role of chromate and sul-Inc. January 1992.101pp. 9202110301. EGG-2628. 60540.146.

fate in simulated boshng water reactor (BWR) water on SCC of This document is the tutonal for the System Analysis and sensitized Type 304 SS, and (3) radiatiorHnduCed segregation Risk Assessment System (SARA) Verson 4 0, a microcomputer-(RIS) and irradiaton-assisted SCC of Type 304 S-S after accu-based system used to analyze the safety issues of a family [i.e,

mutation of relatively high fluence. Fatigue data were otstained a power plant, a manufacturing facility, any facdity on which a l

on medium-S-content A533-Gr 8 and A106-Gr B steels in high-probabihstic risk assessment (pHA) might be performed] A purity (HP) deorygenated water, in simulated pressurized water senes of lessons are provided that walk the user through some

Main Citations and Abstracts 5

t asic steps common to rnost analyses pedormed enh SAR A in the embryo'ietus. and the conespondmg talabon dMe rates The example protdems presanted in the kssons b Ad on one and doses a'e presented these amoaches yed ra%aton ats another, and in comtunation, lead the user throup's all aspects sort ed doses and muthpkation tw Qualty factor (Q! converts them to dose equwaent Th1s is the most common auct/y for of SARA sensitety analysis

1. N ##

1. # * "#W NUREG/CR4444: INST RUMEN T AVAILABillTY DURING I waw wm Our WwW 6 m% ind SEVERE ACCIDENTS FOR A BO,.ING W ATER RE ACTOR mam to waoant be uw d Wh N maw v e WITH A MARK I CONT AtNMENT. ARCIERI W C2 HANSON D J

• • d EG&G Idaho, Inc Fetiruary 1992 126pp 3203130127 EGG 2661 60906 297.

NUREG/CR 5643: IN StGhT S GAWED FROM AQNG RE-In support of the U S Nuclear Regu!atary Commsson Ace' SEARCH DL AHNik.D E, CASADA D A, EDSON j L. et at dent Management Research Program, the avadabety of instru Brockhm en Nabona: L aboratory. Myth 1942 14co ments to supply accident management informaton dunng a 0204130001, BNL-NUREG52323 61314 047.

broad range of severe accidents is evaluated for a Domng T he USNRC Othce of Nudear Regatatary Research has im.

Water Reactor with a Mark l containment. Resuits from tNs WemenW hWeemmMd engwenng rmch prog <ams to evaluation include tal the edentrhcation of plant conditions that iden*:ty and resolve technical issues re:ated to the ayng of sys-would impact instrument periormance and information needs tems structure, and componen4 (SSCW in operatng nucmar dunng severe accidents (t" the definition of envelopes of pa-ma em TM report We a wmmary of those resemch rameters that would be important in assessing the performance re9utts *Nch have tween cempiled and puthhed in NUREGs of plant instrumentation for a broad range of severe accident and re!ated technical reports The Systems components and sequences. and (c) assessment of the avadabaty o' plant mbtru-structures that have been stud >ed are organaed by a:phabetical mentation dunng severe accidents. A simdar evaluation for a g, der TN reseau

>sulti summry on the SSCs is tonowed pressunzod water reactor with a large dry containment des:gn h e ammer Ae to eghasce inspect.on techniques is presented in NUREG/CR 5691-which rnay be usetut for cetectna aging deg'amon in nuclear NUREG/CR 5535 V0k RELAPS/ MOD 3 CODE MANUALuser s p*er p: ants This report wui be updated peruxtica y to rehect n

new researen results on these or other SSCs Guidelines FLETCHER.C D. SCHULTZ,R R. EG&G idaho, Inc January t992. 375pp 9203270007. EGG-2596 61100146 NUREG/CR 5650: EXTRAPOL AllON OF THE J-R CURVE FOR The RELAPS code has been develooed for best estimate PREDICTING RE AClOR VESSEL INTEGRIT'y LANDES J D tr ansient simulation of light water reactor coolant systems hnnessee. Univ of Knouvme. TN ' Oaii Rage National Labo-dunng a severe accident The code models the courmd behas ratory January 1992 10tpp 9202060478 ORNL SUBd7997321 ior of the reactor coolant system and the core dunng a severe MM N-accident transient, as well as large end sma!! break loss of-ccol The work in thm report was condated in support of the ant accidents and operational transients, such as anticiDated es swd h the U S Nuclear RegJatory Comm%on transients without sciam, loss of offsite power, loss of feet JpWp Nrms Goup dunng the penod 1987-1989 The water, and loss of flow A genonc modeling approach is used n'apr inues studied were the J R curve eitrapo;aten tech-that perm ts as much of a particufar system to be modded as nques for usng sma't-specimen test results to predict duct te in-necessary, Control system and secondary system components SWV 'n lager structu es where the extent of crack mienson r

are included to permit modeling of plant controls, turtenes, con-hom the smahpecmen led was M Mwt An addittoral densers, and secondary feedwater conditioning systems isme was ra W dunng tM couw of tNs work by tne testng et RELAPt YOO3 code documentatiori is divided into five voi.

a lo* upper snett A 302 steet The resuits from these tests were umes %olume 1 desenbes modehng theor) and associated nu.

not typical of ductle fracture m many steels and suggested that mencal schomes: Volume 2 contains deta4d instructions for no< pre &ct the t+hawar of sman specimen J R curves may code apphcato and mput data preparaten; Volume 3 provides large structures in some Cases The cause of tnis behaaor was the results of developmental assessment cases that demon.

• d'ed as wen as the consequences of using the SR curve re-strate and venty the models used in the code. and Volume 4 suns from sman specimens of tNs Mod of matenal Finaby, a presents a detatted d;scussion of RELAP5 models and correta.

dacusson and recommendations are g:ven relating to the use tions Volumes 14 are in varying stages of development This d extrapo!ated J-R curves documsnt, Volume S. conta,ns guidehnes that have evolved over the past several years through use of the RELAP5 code NUREG/CR-5674: E VMU ATION OF BEH AVIOR AND THE NUREG/CR-6631 R0t CONTR$UTION OF MATERNAL PACIO-RADIAL SHEAR STRENGTH OF A Rett #0RCED CONCRETE NUCLIDE DURDENS TO PREFATAL RAD!ATION CONT AINMENT STRUCTURE W ALTHER H P. luincis. Univ of.

DOGES Intern i Recommendationi 3tkOV,M Ra TRAUB,R J ;

Urbana, IL January 1932 161pp 920 t 310319 S AND917058 HUI.T E, et at eattene Memona! inst;tute, Pacific Northwest 60442 213 Laboratory March 1992. 179pp G204100139 PNL 7445 This study is on the behavior and suength of the 14scNe reinforced concrete containment model tested at Sandia Nation-61289 230.

This rtpart descnbes approaches for caiculating and express, at Laboratones The containment model was pre %un ed to ing radiaton doses to the embryo / fetus from intemai f adionu-more inan three tmes its design pressure untd a tear in the liner chdes Information was obtwned for se!ected, occupatcnady terminated the test Deformation data from the test was used to signibcant radionuclides to provide metaboite and dosimetnc interpret behacor and to estimate the intema! torces at the charactenst:cs Fractional placentai transfer and ratios of con-waobasemat connecton. A poss tfe mode of structural faJure centration in the embryo / fetus to tnat in the woman were ca!cu-of centsnments sulyected ta hgh pressures is by radtai shear lated Th,9 mformation was integrated wtth data from bmionetic f atture at tne wnbasemat connection A though the conta,n-transfer models to estimate the levels of radioact.vity in the ment model showed no mqn tnat such a fa Wre was imminent embryo' fetus as a function of stage of pregnancy and time amer when the test was stcpped, if it had ' en pass ble to increase entry The MIRD methodologies wnre evended to deschbe de-the inte na: pressure an abrupt snear fMure was powbie A tails for calculating radiation doses to the embryo / fetus To ac method based on the convessive force due to f%u e at the r

commodate the stage depenGance of geometnc rehttionsh!ps wan base was deveioped to (_waiuate the radw sNar st ength and biological behaviors, catulations were performed fo' a rep-of the 1/64cn v containmer i U9ng the developed metnodolo-rosentam $tualan of an int'ortuction o' I pC inta a woman's gy an est, mate is made of tne pressure that wouh.! :ntbate a transfer Compftment (blWad) at successrw months of pregun-

@er f aAre at the walbaWr~'at junct.on of the mode This es cy Dewed 1.101e% of the n! ai an j ret &ned 'ract,ons of anv6 temate is based on a promction ct tre ot;serM strengin of mme

t-6 Main Citations and Abstracts lar 1/12 Scale wall basemat cormecteorg. %ch have failed in onde layers Hysteresis in CPP tests may riot always t.e indica-saest.

tive of prttirig Pit-propagaton studies with Attoy CDA 102 NUREQ/CR 6708: 101ENTIODYNAMIC POLARIZATION STUD-W*ed that, if pris truttate, their propagation may be limited by IES ON CANDIDATE CONTAINER ALLOYS FOR THE TUFF the correntraton of ometing spedes such as hydrogen peron-RE POSITORY. (HOMPSON.N G.; DE AVERS J Aa DUAR CL W N2,0(2n Therm 0 galvanic ettects on corrosion were found Cortest Colurnbus Technoscvos, Inc. Formerly Cortest Colum.

m te in ynerat anor in companson to the %I terous eHect bus, toc ) Janer 1992 2%pp 9202210366. 60703.321.

of mereasm temperam on conomion rate. In borehole liner-Niest Columbus Technotcves. Inc. (CC Technoic9es) is in.

wmaw interaction studies. performed with Alicy 304L C1010 7 the long term performance of container matenals and Alloy 625 Alloy 334L gaivanic coupes, the active member I

uN eur h*gh levet radcactwo waste packages This information of N co#3 consisWy empenenced accelerated co.rMn is tiemg devebped for the Nuclear Regulatory Comm$$on to Long term, boil-down studies showed negl.gible general curro-aid th their assesamont of the Department of Ericrgy's appkca-8'on rates for Alloys 825, 304L and CDA 7t$ follow ng eighty ton to construct a geolo7C repWtory fof dispoka! cf hoh-level

• Ws of esposure in Concentrated simulated 113 well water at

~

radosctive waste. This report summantes the resutta of cyche.

90 degwa C. Al60y CDA 102 capenenced a general corrosion potentrxtynamic polamation (CPP) stod,es performed on candy rate of 0 45 emlyr in

• 3 environment No SCC of U t'end I

datu contamer matonals for the Tuff Reoository 1he CPP tech.

Specimrms of any of th. four alloys occurred Alicy 304L and n6que w-s used to provKle an understanding of how specific ANy b enhibited 40 evidence of kscalired cortovon but some a

vanables such as environmental composition, tempotature, alloy kicalmd corroraon was edent on specimens r f Alloy CDA 102 composition, and weiding effect both the general-and local 4ed.

and Alcy CDA 7t$

corrosion behavior of two coppbase and two Fe-Cr-Ni a!bys NUREG/GR 6725: PROGRESS REPCai ON HOT PARTICLE i

in simn ated repowtory envwonmeriti A satisticatty designed

(

test solution matna was formutated, based on an erterrsve STUDIES BAUM,J Wa KAURIN.D.G; WAltGORSKLMa et at-Drookhaven National Laboratory. February 1992 49pp Search of the)teratur.- ;o evaluate the possit41e range of env>

tonmental J pecies (M/ may occur ln the repository over the life 9203W114 BNL NUREG $22BL 60906137 of the canister. Fortywo CPP t.urves were performed with each NCAP Report 106 on the effects of hot particles on the skin afloy and the results indicated that several different types of Of D'98a monkeys, and humans was certically reviewed and feat-(

corrosion were posSble. The copper base alloys ethitutod un.

sessed The analybis of the data of Forbes and Mikhail on the usual CPP behavior in that hysteresis was not always associal, effects from act'vated UC(2) particles, ranging in diameter from ed with pdtang The effects of tempef ature on the corroson be.

m W b 328 % N O ve WWaton of a new mW to pre havior were evaluated in two types of tests, rsothermal tests at dict both the threshold for acute uceration and for ulcer d4ame-n temperatures from 60 degrees C to 90 degrees C and heat.

ter. In this moctol, a point dose of 21 Gy at a depth of t.33 mm transfer tests whs e the soluton was maintainod at 60 dogrees in tissue will cause an ulcer with a diameter determined by the C and the sper1 men was internally heated to 90 degrees C. In radius to wtuch tnis (Ase extends Apphcation of the fnodel to the isothermal test, CPP curves were obtained with each alloy the f orbes and Mikhail data obtained with maed tission prom m remulated environments at 60 degrees C,75 doDrees C, and beta parteles yielded a " threshold" ($% probability) r4 S 107.,

DU degroet C. The results of these CPP experimen6s indecated beta particles from a point source of high r,ergy (2E MeV that no systematic trends worn evident for the environments maximum) Deta particles on skin The above modd was used to tested Iri the boat-transfer test. CPP tests woro portormed with predict that appronimately 1,2 = 1000) teta parbetes from SrM a spectmen internally heated to 90 degrees C while maintairung 90 would produce similar effects, since few 57 90 beta padicles the test soluton at 50 degrees C. The results of these expen-reach 1.33 mm depth. These em>$ sons correspond to deses at ments indicated that in simulated 113 well water, heat transfer 70 lm depth in tissue of approximately 5.3 to 5 5 Gy averaged appeared to have an effect on the corrosen tr hacor of each over 1 cm(2), respectively.

of the four alQys. Heat transfer did not appear,i have a major effect 6n more aggressive simulated environm..ts. Lastly, thw NUREG/CR 5747 DRF FC: E.*tiMATE OF RADIONUCLtDE RE-effects of welding on the corrosion t+haviur of tf 4 alloys in sim.

LE ASE CHARACTERISTICS INTO CONTAINMENT UNDER ulated environments were examtned Rod matenal was welded SEVERE ACCIDENT CONDITIONS Draft Report For Comment into a 4thaped grove in plate matonal lhe weld was machined NOURBAkh5H.H P. Drookhaven National Laboratory. January and evaluated by the CPP technique. These studies showud 1992.122pp 9202240339 DNL MUREG-52289 60682 213.

that welding had relativel, P effect on the CPP behavtor of A detailed tenew of the avaltable light water reactvr source r Cr Ni alloys in the _,ormments that were selected term information is presented as a technical basis for develop-t the e

Welding was found to be detqmental to the periormance of the ment of updated sourc' terms hto the cCntainment Under f

copper-base alloys in both simulated groundwater and in a solg.

Severe accident conditions Stmplihed estir% of radionuchde con shown to promote pttting of the wrought copper-base release and fransport Charactefistic8 die specifCl for each alloys _

unique combinaten of the reactor.oolant and cotainment system combinations A quantitative ancertainty ariatysis in the NUREG/%5709: PITTINGA1ALVANIC, AND LONG-TERM COR' release tc 'he containr*ent using ajREG 1150 methodology is ROSIGN STUDIES ON CANDIDATE CONTAINER ALLOYS also presented.

FOR THE TUFF REPOSITORY, BEAVERS.J A; THOMPSON,N G4 DUF:R.C t.. Cortest Columbus Technologies, NUREG/CR 5762: COMPREHENSIVE AGING ASSESSMENT OF fnc. (formerty Codest Columbus, inc) January 1992. 219pp circuli EREAKERS AND RELAYS GLEASON J F. Wyle tab-9202240328. 60683 001 oratories March 1992 204pp 9203270017. Wn.E 60$01.

Cortest wiumbus Technologies,11c. (CC Technologies) in-61101.2114

- vest!gatv3 she long term performar ce of container matenals for As part of ite NRC Nucicar Plant Agird Research (NPAR) highlevel radioactrve waste packages for the Tutt Repository.

Program, a compreheneve aging JssestNnt was made of This renort summantes the resutto of Task 4 (Peting Studies).

relays and circuit breakers Reisys and circust breakers are im-Task 6 (Other Failure Modes) and Task 7 (Long Term Expo-portant nuclear power piant equipment which are suscoprtie to sures) of the program. Fe-Cr Ni alloys (Alloy 304L and Alloy degradation with tin,e. Thirt is a Phase il NpAR repor1 which fol.

825) and coppertase alloys (CDA 102 and CDA 715) were iba NPAR strategy. Tests on naturally aged and cegraded s

evaluated in a simulated 413 well water and in solutions select.

rey e Osrcutt breakers were performe in4du measure-od from Tas' 2 of the program. Pit initiat on studies of O ment

• made and current and Improved metk,s for inspecten, copper base alloys conbrmed that standard toterpretatons vf surveillance and monitoring evaluated. 59 whcant results de-CPP tests are not atways appropriate in the presence of thick scribed in this report were the identsfcaton of inspecton, sur-

-i-

I 4

Main Citations and Abstracts 7

i veillanca and monitanng n+thods which provide a hqi er level 6mpact of survedlance testing p) nd impact of tet,1 caused l

h of assurance that aging will be detected and rmtgated The po' hips. and (2) usk intact of tal cauwd eampment wear Us'ng tential entsts that smplementahon of the imp oved methsda in ce methodokyy presented tnese t'egahe ntA impacts are l

nuclear plants would trunimtre the empact of aging and result in evaluated foi a selected set of s.ur edlance tests for demonstra-v more cost etteetive maintenance on relays and circuit treders.

tion esamses lhe res/ts of the nsk efixtwr ness ovaluatton NUREQ/CR4769: NATURAL CIRCULATION COOUNG IN U S a'e proed abng wah the eghts hom the t.onwvity anaiy-PRESSURf2ED WATER RE AC10RS, MOHUGH,P R ;

• • 8 HENTZEN.R D.

EG&G ida% inc. January 1 4 165pp 9201310306 EGG 2653 60441.324 NUREG/CR4787 DM FC: TIMING ANALY$!$ Of PAR I Uf L I'iN F AILURE S Drsft Repo*1 For Comment JONE S K R ;

i This document is a synthesis of data and ana'ys s cor+9tning rsatural circulaton coohng in U S. Pressunred Watet 1.. actors WM U KmW R ; d at (N Ma% W Mad M.

during off-norr%i operation and accident transients its ot9echve mpp 9204060046 EGG M$t 612?fi16L is tbt integraari c' tmportant research firrd4ngs concormng Nes*8'ch has been conducted to devWop and demonstrate a j

PW"4 natural cartc dabon phenon 9na into a single reference doc, methodology for calculahng the t'me enterval tetwet. tr*ce'pt of UmeN Neces of information includs the Nuclear Regalatory conta'nment inciatson segnais and the fsst fuel pm failure for i

Commission. nactor VWtors. utAty sponsore research g'oups, loss-of<oolant accidents (LOCAM Demonsbation calculations utihties, national laboratones,1ewac't repon.,

eting papers, were performod for a Babcock and Wilcos deugn (Oconee) arid 1

arctvva! lite. iture, and foreign sources. Three incvjon of natural a Westinghouse 4-ioop design (Seabrook) Senotivity studies Newlabon ero discussed, single-phase, two-phase, and YUt/

assessed the impact of fuel pin burnup, mulai peakog factor, bonhtg ca. dnaation. General characte"stics, analytical erpretr breM sve, emergency core coohng sysicm availateirty, and Mons, noncondensible gas effects, secondary effects. And non.

m*n comet pump tr p on these times The analysis tised uniform ficn are described wn regard to each of the natural ACDAP/RF LAP 54 MOD 3 and TRAC-Pf1/MOut to catet ate re-d circulaQn modes. Plant operational data, tests in scaled expen.

actor system transant theinal hydrauhc cordtions and FRAD.

i mentel facibts.A and anat sis with thermal hydraulic system CON-2 and FRAp TO to calculate steah state and transient k

/

codes have demostrated the effectNeness of single-phase nal-fuel behavior. This ardysis aho provsden a MMonon of j

utal circulabon as a cochng rnechanisrrt Evidence suggests that SCDAP/RELAPS/ MOD 3 and 1R AC-Pr t / MODI resu?s for two-phase natural circulation and seflus/boshng condensation large b.eak LOCA anaiysis uung SCDAP/RELAP5/ MOD 3 ther.

can also be effectwo methods of t.itomate core cooling Nien-mal hydtsul4 data, the shor1est tirne intervals calculated be-mental Met factkty data and analys:s are the pomary compo-tween containment molabon and fuel pin faduro are 10 4 sec.

nents of the feo phase and reflun/bclhng condensation natural onds aM 1916econds for the D&W and W plants respreuve'y circulation knowledge base.

Usmg data generated by TRAC Pit / MOD 1 the shorient inter.

NLREG/CR4774: ELASilC PLASitC CHARACTERIZATION OF val for the W reactar is P91 wconds These intervats a e for a l

A CAS1 STAINL ESS STFEL PIPE ELBOW M AT ERIAL doub'e ended offset f. bear cold leg tneM, uung maximum

. JOYCE.J A U S.

Naval Academy, - Annapohs, M D.

peah mg facmr appW m fuel with manmurn burnup HACKETT.E Ma RC+E,C. David Taylor Rosearch Centor. January 1092. 2t tpp 9202240346. 60602 001.

NUREO/CR 5760; A COMPARISON OF WElBULL AND 00C)

Tests conducted in Japan as part of the High level Vibration ANALVSIS OF TRANSITION RANGC FRACTURE TOUGR 3

Test (HLVT) program for reactor piping systems revealed fa, NESS DATA RAGE.D E. Oak Ridge National tahorntory tigue crack growth in a cast stainless stuel pipe elbow. T he ma.

January IN

.40pp.

m 2240 M ORNL/ N 1 W tonal tested was equivalent to ASM SA-35tCF8M. The David M9112-Taylor Research Center (DTRC) was tasked to develop the ap-Charactertsbcs of entromE statisbes that are_ uwd to predict propnate matonal property data to charactenre cycito defoima.

We effects on cleavage tracture toughness in the transition tion, cyche elastic plasto crack growth and ductila teanng resist, range wore explored A 533 grPde U stool base and weid ance in the pipe elbow material.11 was found that the cast stain, meta's were tested using compact specimons ianging in site less steel was very resiblant to ductile crad entendon J.R from 1/?TQT) to BTC(T) and with sufhcsont replicabon m some curves crsentially followed a blunting behavior to,ery high J cases to provide good fits to Weibulf d<stnbutions The clanical 1

levels. Lo* cycle fatiguo crack growth rate data obtainod on specimen site effect on data scatter and rnedian K, tough-this matenal using a cychC J integral approach was consistent ness at a given test temperature was observed m the low to with the high cycle fatigue crack growth tate and with a stand.

mid-transibon range Theso effects were well pred eted with ce afd testbook corretation equahon typical for this type of materi-tremal st%stics Houever, ti.e same model is not applicable on al. Eva'uation of crack closure effects was essential to accu-the lower shelf and si also becomes exuen'ely wen and unreh-rately deterrnene the cf ack dnving force for cyche elastic-plastic able n the mid. Io high-transition range The Irw n @pg crack growth in this matenaL SEM examination of several of the relationstup was also espioted as a model and was found to cyche J test fracture surfaces indics!cd that fatigue was the pri.

predict simiiar stie effects lhe predictive charactenstics of the rnary mode of fracture with ductile crack catonsion intervening.

latter seemed better suited to deal with the dimmuhon of site only dunng the last few cycles of loading.

effects in the near, in low-shelf toughness range in the rmng NUREG/CR 6775: OUANTITATIVE EVALUATION OF SURyElt, toughness part of the transit on. the predicbve character;sbcs LANCE TEST INTERVALS INCLUDING TEST CAUSED RISKS.

were about the same as tae statistical model up to where KIM.LS; MARTORELL.S4 VESELY,W Ea et at Broc+. haven Na-de WA m this study) of the baselme (smati specimen) data tonal Laboratory, February 1992, 7/pp. 920325030S. BNL.

were : cr less This work could be used in thn establishment

- NUREG 52296 61086 251.

of a framewntk for trans.oon temperatu e test entena Upper-r Concerns have been tamed regarding the adverse safety and tower bouna 6 cntena could be used to dehne opbmum empact of surveillance testing and generally overburdensome condstions for the apphcat on of either of the uforomentioned i

SJrycillance requiroments To evaluate those concems the tsb models f or survedlance programs, sensible rules should bt$

l effectNeness of surverliance tests has been studied with eupheit specihed at to specimen sue requoements and numbers of

(

consideration of t.he negative Nsk impact, in conjunction with the specimens to be tested in order to appiy these analytical positNe risk impact This r~ port dehnes the negative effects of mode's. Another need would be the definiton of a procedure for Aurveit!ance testing from a tisk perspective. and then presents the Weibull. distnbution Otting The present report suggests the methodology by which the negative nsk Impa:t can be ttems to be conssterett for rooviremems in apphcation of these quanbfied, focusing on two important bods of negative risk predictive techn: ques a-

-c

- -.,, a _. - - - --. u.,.

I 8

Main Citations and Abstracts t

i NUREO/CR4799. DEVIEW OF RE ACTOR PRI SSURE VE SSEl deugnated IRR AS 4 0 and is the sutwct of tro Refemnce EV AL U ATION REPORT fOR YANKt E ROM NUCI E AR Manuel Vmsion 4 0 of IRR AS proos the same ca; atees as l

POW ER ST ATION (Y AEC NO i?3M CHE VE RTON R D.

Verson i D and adds a tNat.onal dMa base fatiHy for manag DICA 50N.T L.; MERhtLJ G ; et a! 04 Adge Natonal Latiora-ing the data. empoved tun bonaMy. and improved opnthm pet.

{

torr Marc h 1992 149pp 920413 E 4 ORNLM M 119H2 formance I

61315 073 The Yanhe Atom < [lecinc Company (Y Af C) hAs pMormed NUREQ/CR48t$. EVALUA140t6 OF 1990 PH;SM D[ SIGN 90-l an inteurated Preuunted Thenral Shoch OPTS) type evaluaton VISIONS VAfd TUYLE G J. SLOVAG C. CHAN,D a et al of the Yanbec Rowe reactor prouvre vesselin accordance eth thoc4 haven Nabonal L atestory Maech 1992 2150p I

tte P1S Rule 110 Cf R 9 01) nnd U S Rovatory Guide 1154 920413T73 DNUNUREG 52311 H3141f4 Anal ses of the 19@ version of the pHibM Advaved lvd 1he Oak RdJo National Latcatory (ORNu veviewed the V Af C y

document and performed ar independent prohbute tincte Meta! Hoactor (ALMR) desgo see peewted and d+cuswd i

mechanics anays$ The teven inclu3cd a compenson of tno Most of :Sc calcu'abons we'c performed using litJt. :ompvint PcSc Northwat labo atory and the OHNL probatuhtitic frac codet Orlicutady SSC and MINET in many cases todepend-r ture mochano codes (V!5A Il and OCA P. vespectrvety) The ont DNL talcutagons were compared apmt ana%es prewnt-review identaed mmor errors and ono Mnrhcant ddference m ed by General Electne when they satomrtted the pntSV d t+gn phdosophy Aito. the two codeti have a few da similar penphora!

rev+ons for eva!uaton t'y the flacicar Rogu!atory CommSton featu+es Asde from these detterences, VISA It and OCA P hre (NRC) Ibt current PRISM demgn utAns the rnetalbc fuel de-very similar and with erfots corrected and when adpste<1 for the vuopod by Argonno Nabonal Laboratsy (ANL ) which lac Matos ddforence en the treatment of trattare toughness d stobotion the passve/7r.herent" shutduan mechanam that acts to that

. j thrDugh the wall yield essentiatty the same value of the condo down fearlot powef prpduchon whether the Syrfem Ovetheats tional probabAty of failure The ORNL independunt evaloalen There are a ten vulneratabes in the panNe shuidown. with the indicated R1(NDT) values conwderat/y greater '.han thoko cot-nost worrisome being the posatr e feedback from sodium densh v

1. esporeg to the PTSJ4ule screenmg cotona and a tregaency tv decreases of tWum vodng Vanous postulated un-of f adu'o substanbatly greater than that cor npon$ng to tne

s. crammed events were osamined by GE andr r BNI, arri moch r

o "pomary acceptance cntenon" in U S Regulatory Gude 1154 of the analyws dscussed in thm report is focused on ttus cale.

Time constrain's, however. prevented as ngorous a treatment gory of uvents For the must p4rl IBO UNL evaluabons cont f m i

as the s;tuation deserves Thus. these results are very pr hrnF the information submitted by Generai tinctne The pnncepal e

nary.

areas of concern are reisted to the portormance of the tomary metal foot. and may te tetor ed e ANL continues w4th its fuel v

NUREG/CR4802: 4DENTIF ICATION AND A$5ESSMENT Of CONTAINME4f' AND RELEASE MANAGEMENT STRATEGIES developrnent and tesing proyn FOR A BWR MARK lti CONT AINHENT LtttC C ; LLHNER.J F1 NURE0/CR48th HE" ORT ON RESE ARCH AC11VITIES FOR Drookhaven National Laboratory VANDENrJEDOOM Michigan' CALENDAR TEAR 1WO ABABOU.H, CHOWDHURY, A H ;

CRAGNOUNO,G ; et at Center tor Nuclear Waste Regubtory D

$2 6 D6 Analyses Decembet SW1 32tpp 9K.22f;02 t B CNWRA E ThG report 6dentfes and a%enos amdent management 0,

I strategies which cDuld ($ Mortant for prevenhng containment ar nual status toport on the tenults of f ewarch con.

f ailure and/or neligating the teleer.;e of fistoon producta donng a ducted on behalf of the NRC by the Centet for Nuclear Waste severo accdont in a BWR plint with 1 Vatk fit type of contain, gJaWy AnaWs m soppcct of achvities under the Nucleaf ment. Based on informatton wadable from prehabilstic n!J as-Waste W Act as Amended Eight spoohc projects are un-sessments and other enstn9 seve'e eccdent renarth, and hay N &4Wmm pmW m uW Wey Me uking mmplihed containmont and telease event trees, the irr(irt and compmer calculations to aueu key geochemical con +

dentihos the challenges a Mark.Il containment could face straints and to evaluate sorptrve properbes of Mohte present at during the course of a wvore accdont, the mhanisms behind the proposed repomtory site. The Thermohyd* ology project has these challenges. and the strateges that could tie used to mib.

as its focus improved understanding cl heat and flu d flow in un-gate the chaftengos The strategies Pro knked to the general saturated med.a taboratory, field, and calculat onet studies are safety objectwes which apply for coniaenment and release man-CO*l*" d 'n the Seisme Rock Mechanics protect to examine agement by means of a safety otWtwo tree The strategies the ettects of repeated soismic loadings on the rock mmhane were assessed by appiying them to certain severe accdent so.

tal and hydrologal responses of rock manos The integrated quence categones deemed important for a Mark 111 containment WaW Pa3ap @nmmM have Wn inmaH to WaMam because of one of more of tty + following charamstics high degradahon modos of candidam aaste container stloys Toree-probabaty of core damage, h 1h consequences, itad to a dimensonal computer anaWs techniques are being used in in-numt er of chailonges, and invoi 'o the fMu e of mu!!pe sys.

vestigate spatial variao&ty of flow and trarrport in vanably natu.

r tems.

rated fractured porous media in the Stochastt ibw and Trans-NUREG/CR4813 ' V01: INTEGRATJD REUABluTY AND RISK port project The recently initiated Geochemical Analoqs propct ANALYSIS SYSTEM (!RRAS) vel StON 4 0 Reference Manual ss.Ms to investgate the role of such amaings in the licensing RUSSEL LK D-. MCK AY.M Ka Sa tilSON.M B : et al EG&G process, and is curvnt'y focused or nxahng and eva!ust ng a tdaho. Inc January 1992. 334p 9202110290 EGGPSM potenhai site la mvesbgaton ' %e Perforrmnce Anessment 60$W 310 pfciott a dxeted tow ard dev%oping and evaluabng methodoto-lhe Integrated Rehability and Fbsk Analysis System (IRR AS) ges for evaluaton 01 the tong term performance of the p o-is a sta%ot-the-art mictocomputenbased probabashe r$k aS-posed repo9 tory 6eument (PRA) modol deve'opment and anaNs4s tool to al

'dreu key nuclear plant safety isnies IRRAS is an integrated NU6EQlCR484 t: VERWICATION Gr NONUNEAR PIP!NG RE4 software tool that gives the user the ab#y to create and ana-SPONSE CALCULAllON WITH DAl A f ROM Sf tSMIC lEST-lyn f ault bees and accident sequences wng a rmerocomputer ING OF AN IN PLANT PIPING SYSTEM SHI4tV ASAN M G ;

This program provides functions that range from graphical fau!t JOJT AHED M : VOT.C A Argonno Nabonal Laboratory March tree construction to cut ut generat:on and quantittat on Ver.

19V 215pp 4204100152 ANL-92/4 012e9 015 son 't 0 of tha IRR AS ptogram was rGeased in Fetvuary of The nonhnear piping analyse code NONPIPE was evaluakd 19BT Since that Ume. many user commenh and enhancements by modreng and performing postiest ca!culahons far a high have been incorporated into the program ptoviding a much levoi ummic test pertarmed on an in plant pirung system at the more powertal and usentnend'y setem This veryon has been HDR tem taNty in Germany The pong uW wn y r9d struts i

i r

e-

+

ww w,

wer e.c

.we

<-w sevm* v-v%,...-em-e-4,r e +ess,n wr-t e.w-e we e wm '= <

-.me semw-wee eri-y-%----n--.--w-u-rrw+sm--m~-remew-w v -w www-mw-w-wwem---w-,--as,,e-

l Main Citations and Abstracts 9

for dyriame supports and espenenced sgnAcant nonhoeur se-HUREG/GR-0005 V01: 6%k B AM D IN9 I C110N - DEVE LCC sponse and plastic deformation in the test The calcutt t ee-ME NT Of GUOEL INE S General Dos enent

• Amen; an M elv spcmes v general had the tome bmo trends as the menvu'e-of Mechancel i neer s F etir,aq-t '. ia? iPop 97t W'N t o ments but we'e qu:te var etde in estimating peak values Peak (RfDVOLP31 010P0 32 7 tirains woe overestrmaied the shear strains to a gu ate' insewe inspection r pW a 1gn h:n tem in muvy degree th&n bendAg $ Pains Peak strut torces were undef e6 tb etcpment and si9ctat., faveg i or man, in:1Aina! appM 1 mated as a Voup On the amage the d$a:ements were esto tions teamrements Im % we mpec ton a'e tauJ upon poor me%d ems to the me*su ements and the aa eleratons we'e evenence or enyneenna 17.ent or ve nonomtent ht r

overestn ated Spettal car sster<y in d:spia;ement and strut rea.mreme nts or gedet>nes br tt ne inspec tom we t-ateJ on forco 0916 males was better than for acceterabens Quattative'y engmetos cuaMatve 1 pent and oniy tr5W1y te e inte ac the anatytical predections are omv r to e=penmenta' observa-cnunt the Pot atmy of failu'e of a compwnt under its oper a

tions and they prowde Quant:tabve estcmt,tes that are ut.e'ul fM at.on and ioalog c onJtent. and the t onseauen:e et rathfM pract< al purposes The modehng aspects that contbute to utrn if it et cars lhis doc ument recommens appionnaie meth-large JscrepavAs are identif+d Both the espenments arvi c af cm for estspisimg a to t,aw1 mpechon pmyam f or any to-cJattens (leerly Indtale th41 pipmg is all but immunt 10 Gross Utt/ or struc1Jeaf system The prom invoyes lour major fadure even when sutyetted to otreme se+mic loaing g.tepg oc# n,ng ine sgtem per.orming a qvM tabve nu aut o i

NUREG/CR4842; G AST ROINT E STIN AL ADSOhPTION Or me% wng this to da a quanttabvc

• an% a an;t devrop-PLUTCNIUM. URANIUM. AND NE PT LNiUM IN ffD AND mg an inspotton prop 91 componenn and structural ete-F AST E D ADULT 6ABDONS APPLICATION TO HisMANS rnents uung probabmsbc ena'neenng trietho1s A congwwsn OHATT ACHARYYA, LARSEN.H P ; OL DHaM R D ; et al Ar.

dMument WW detM spepbc nu-tased imhnqm for the m-aonne Nationa! Laboratory March 1W2 50 0 92032502ft2 spnten of sponents of LM nAar power pnts opMm 0

AN142/B 010!!7 277 rethodology set out in Votume 1 Gastromtestinal (GI) at'sospion values of plutonium, uqin.um.

NUREG/lA 0040. BD!L OFF ( tW NMENTS WITH THE I in r;nd neptunium were determined in fed and fasted a;fuit ba-M mN F A n y m4M e mM AW WM N1 boons A dual isotopo method of determitung G1 absorption.

OVEHviEW M PORT AKSAN S N, STi[HLi f AN AL' tlSD T which does not require animal satnfice, was vahdaied and Iaul Scherrer insttute Mrch 1942 50 0 9?O41DTM l $t 0

%hown to compare well *lth the sacnfice tnethod (%ummetion of oral isotupe 6n unne with that in tissues at kachlice) f or plutonb DERICHT 029 612 % 255 um, GI absorpbon values in taboons were almost idtmtectil to A S0"+5 0' 0'penments was peibnnd in me M N W those in rn<e (ca 0 2*

in f asted animais. 0 0t *. m fed ani facibty con 9 sting of ten tol-ott (core uncover,) and one ah rnals). and the values for fed animak nyeed with e% mates for batc heat up tests in these tistt rod power setem prenure.

humans F or uransum, Gl absorption values a fed (0 5%) and and initial coolant subcochng were vaned The repeatd% of tasted (4%) baboons agreed well with those in fed and f asted the capenments was am demonstrated some of the tel off humans and were 6-7 times higher than thow in mice f or nep.

data ot,tained from the NLPtDN test taphry are used for the tunium, Gl absorpbon values in fed baboons were lower to, anessment of the thermal hydraX transmnt computer codes small amounts of (239)Np (0 03%) than for much targe, These calculatons were periormed olenovely uung the trolen amou 9s of (237)Np (0 3%) Neptunium GI absorpton valv in ver9en of TRAC 001/ MOD 1 (verwon 22) A hm&d numlier of r

lasted baboons (1.5%) were independent of amounts ingested assessment calculatons were also done with PL L APL/MDD2 and wore considerably higher than those in fed anima!s The GI (ve' son '16 0?) In this report the ma,n resuits and conduvons absorption of (239)Np an led animals was et.sertally the same of these calcuiatons ve oresented with the identAcatan of in mice, baboons, and humans in fasted anima!s. mice ab.

Problem areas in relation to the mode 4 relevant to toil ett phe-sorbed 4 bmen 9ss (233)Np than d.d liaboons F ' ;* for nomena humans are not availabie) f or one baboon that was not given WMMA*# AE%MUN @ D#'N '#M ##

its morning maal. both plutonium and neptunium GI absorpton AN INADVERTENT STE AM LINE ISOLATION VAlvt E LO.

alWs at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />. 2 h after the usual mealtimo (14 h ovc.

aight fast, baboon "without breakfast"), were the same as those SURE IN THE foNGHALS 2 POWER PLANT PELAYOJ Con.

solo do Segundad Nuclear (Spain) SJOBE RG.A Stut.vA E rer-in baboons fasted for 24 h. In contrast, for baboons thh te.

ceived a morrung meal, plutonium and neptunium ebsorptions gM nA AB March 1992 pp p204100075 ICSP R2MSIV-T did not rise to the value found in 24-h f asted baboons even 8 h O'M N A TRAC PF t / MOD 1 Beulation has been conduc ted to after the meal The authors conclude that GI absorpbon values for Nutonium, uranium, and neptunium in adu!t baboons are assest the capately of the code to predet a steam hoe isola-tion val") closure trdnment. Esten9ve use of results from good est. mates of the values in humans (and bettet than those in mice) and that the values for the f asted condmon need to be Ringhals 2 data acauston system was made to dove the in+al con @ bons and some of the necenary twundary cond+ons Trr taken into account when standards are f.et for oral esposures in msults of the simulation revealed the importance of pr oper environmental and workplace setbngs A latonal way of doing this for plutonium is discussed

• C^Mmg of steam genmator,nternam as wM e the mWg of pressurger wat's and spray noMes in order to reasonataly NUREQ/Cfb5656: IDENTiftCATION AND LVALUATION OF PWR predict the condensation phenomena

~

IN VESSEL SEVERE ACCIDE NT MANAGEMENT STRATE.

(

GiE S DUKELOW,J S. Dattelt Memonal inst:tute, Paafic North.

NUREG/lA 0047: ASSESSVENT Of RELAP5/ MOD 2 Ch west laboratory HARHISON O G Jasch Associates 36 04 AGAINST T HE i.OVIISA-? STUCi -OPE N TUR0tNE Do MORGENSTERN M Datale Nman Attairs Research Centers PASS VALVE T R ANSIEN T ON SEPTEMBER 1.

19St Match 199?,10lpp D?03270010 PNL41022 61115111 N RJOLA V Technical Reserch CerPe of FinMnd (VTT) March This report dxuments work performed for the NRC/RES Ac-1992 11epp 9204060315 61229 076 ciderit Managenx nt Guidance Program to eva uate posseie DLLAPS/ MOD 2 mmutations have t+en conducted far an strate @es for mitigabng the Con %equnnCes of PWR f.evere acci overcookng type transient that occuned at the LOVitSA Un.12 dents lhe seleChon anff evWuWon Of strategies Was hmded tc The code a%( ssment work in the feport Wah liased on the the in ve%el pha!,e of thn severe accident,10, af er the inito avadable plant data that were r,3ved through the normal piant t

abon of cose degraditor$ and pnOr to teactor preMuf e Ve%el instTument3tCn into memory of the POni CC'mputer lhe ladure A parallel project at BrocAhaven Natonal laloratory has RELAP5 results mawhed weit the m4n measured prameten t,een conudenng strateg;es apphcable ta the emesse8 phase in part cular, if the general trends were esamined The tnnest of PWR sevne accidents cuantutve d tferences were found t+ tween rMcuiated and

10 Main Citations and Abstracts measured vales o' the pomary prenure and p'euunter water TR AC PFD MODI pre.Rtons of LOCA Reh!! l openments car-level The importance of the rnadelung of the prenunted venel tied out on a 1/10 sme majed are com;weJ apenst empen wall was demonstrated when condensation on tne wall aiune ments measuvenets and vdeo oteceveons Sewtwdy stud was able to stop anu tu'n dawn the pressu e inutase ses have teen t a nei oJ to adermine the eMMt et Hv.taunc r

Dameter and nodahnaten A simphf+d AWyvs of totM fonetta-NUREG/l A 0051: ASSESSMENT STUDY OF RF L Ak5 / MOD 2 bon (cnd tons revea!n tnat the haud head 1 ansfer coemc ont CYCLE 36 05 BASED ON THE DOEL 4 RE AC10R TRtp OF ounng condensaton m sut,staway gwater than swaestod tiy NOVLVDER 22. 1965 DE VL AMiNC(V. DE SCHUTTER P ;

the re:txton of the erpenmental tneswremen's V ANHOE N ACHE R L.

TRACTEBEL March 1992 63pp gg g g g gp 9qgg, gggg 9204100097. 61288 133 UcMi STR ATHCl YDE 1'10 SCA! F MODL L hl hit TE STS As part of the first ryr'e testing program for the Drag <sm ggg g y, pp gg y, ggg g y, g g i

2 DOEL 4 plant a turbine tr p on hgh swam generator level fol' StepWA tm R UnM ho@ M e W92 %

1 lowo1 by a reactor tnp was pedormed on Novemte 22,19M g, g,93g g pp,99, Nine assessment runs were rnade using RE L APOMOD2 Cycle TRAC PFt/ MODI predst ons of LOC A A h!! E spmments cat-30 OS wdh the output compared to N data acchmed donng in*

nd out on a 1/10 MW mdM P AH wW M prewried The test i

pre $ctons vhow that TRAC undorprodcts tyran far the test

• • I""'"'*

V"""

NUFIE0/lA 0052: AN ANALYSIS OF SEMtSCALE MOD 2C S f 4 cuned Smple sensitiv4y eneyn of the inte'taoal drag rtotein 1 STEAM LINE BREAK TEST USING REL APb/ MOD 2.

" # P* * "' # d '" "' #

'O " **" " P

• • '#

• U' ROGERSJ M United Mngdom Atomic Ene py Autaonty March 1992 4Bpp. 9204060323 ALEW R2476 61232 001.

RELAP5/ MOD? is teng uwd by CEGD to asmt in an indo.

NUREG/iA 0050; ASSESSMENT OF THE SUB COOtID DOlv pondent assessment of the strewell B POSR As part of tne ING MODLL USED IN AL L AP$/ MOD 2 (CYCLE ?6 05 VER proceu of valdahon of the code for that assessment perform SiON E03) AG AINST l WE RiMENT AL DAT A BR A!N C A Cen.

ance of the todo was venfied by apptying the results of Sem+

tr al Elec toc 4 Gener ating Board fM h 1992 3dpp cale. MD 2 and LODI This report prescutt the resu!ts of the 9204000?L3 GD/PE N/729 01226132 code assenment of RELAP5/ MOD 2 using sommale S FS 1 in Order to test the at4ty of REL APS/MDD2 to dacobe sub-steam kne break test cooled nucleato boding under condibons tamibit to thow antici pated dunng intact circut fault bcenanos in preuunted water NURE' Olla-0053: AN ASSESSVENT OF TRAC PF t/ MOD 1 reactors the codo has been assened apnst resuts of high USING ST R ATCHCLYDE 1/10 SCALE MODE L RE F 'L L pressure sub cooled tobng e<penmonts reported in hterature 11 j

TESTS 2ND RE PORT DEMPSTER.W.M ; DRAD"OROA 1.

e concluded that RELAP5/MODP can be apohed w:th reasona j

CALLANDER T M ; et at Strathdyde. Univ of, United + g 1m tdo conhJence to the prod <t on of bub coated boihng ved trac-March 1992 09pp 9204000332. 61226 062.

tion for cond tcom tunected donng PWR intact orcwt f asts 1

n.

. - - ~.

~.. -... _ _ -. _ - -

Secondary Report Number index 1

This index lists, in alphabobcat ordot the performing organization issued report codes for the i

NRC contractor and international agrooment reports in this compilation. Each code is cross.

referenced to the NUREG number for the report and to the 10 digit NRC Document Controt System acces3lon number, MCONDARY Mt PORT NUUDt.R hlP("If NUMIO

$(Cl*NDAMV StiPDHT NUuttiR Rf PORT NUWtitR Ali W h?470 NUHf G 'lA [052 ua.t+1 Nuf 4 G ( H f 44i ANL42/4 NifRf GdLH Sfp4 t 60 cf44 Nuhl ORCH 41? VD9 MH1079 NL

• G 4 A Md' i

A NI -91/6 tuant arch 4%r V13

('S fi N*

N#

4 I A ##"

ANbp?/8 Nuht G/C4 t642 NUki G/CR ! F?$, nn, rc hih,,h,t,3 hh,y h*y,h, V,, N,

gpy,p HNL NUME G t?tti?

Naniwon $74 onNo c Nv

,<n, nNoNUnuum9 DNblJURI a-b22%

NUPI G/CR 617$

OHNUTM t 19"W

.NuH( 4U t ' des SNL NUHIG $230$

NUHf' GiCR-0FK2 DONI /-1M t t M; Nun ( G T.H 07 pia DNLNunt G $?311 NUPtG/C4 0916 OhN1/ TM 9*C Ndul G4. H d?19 VM bt CNL NUREG $23?3 Nan (u/CH %43 DANL FunevnT*1? t NU4f us( n 8460 04WRA 90 014 NUDE G/GR f.61F PNl d?d NU4I M04 PPSD V10 I'NL #485 P UNI O'l" %3 ' HU' CHID-VOL 201 NtJREG'GH V 15 VD1 N M??

NW M. H W IOG PS77 NUR( G/cH. /9 V04 f GG #596 NUht G/G3 f536 VDS kh h

bl AP7.;?,t:tds A 2 NU4[ O /CH 4tq7 HD?

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( GG 2(176 NUPf Gt04 LM) y01 IGGPn3 Nuntoeca$r09 o00 r%74 Nurg arcs 4s4 yoi at (ctg ?6$/

huh [G/CL)f87 DRf f C Wi t L e,0101 NUH(G/C4$4,7 t

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I Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by the author, if further information is needed, refer to the main cita-tion by the NUREG number.

DRADf ORD.A M AB ABOU R.

NUht G/CH tet7, IllPO41 DN DE 5f ARCH ACTIVit a 100 Call 4 N#l G/iA 0%3 AN A%l bSMf N1 Of IR AC Pf 1, MD 1 UWs STn ATC6ct yN 1/10 bCAL( M@F L Mf F iLL II %1S ?ND HLIURY DAR YL AR 1930 NUni G U A 40% AN A%E 55MI NT Up f R AC PI 1/ MDD1 UYNO

• • U ' M ' ' D E

l

1. ul II b VI 1 A&40 Boil Of r (*Pt h Mlev15 Wif H THE t in Ni riuN F ACILITY, AN At YLl$ AND f,ODL A%( MMt NT OVt H V!E W DR AIN.C H.

Ul W '

Huhr G 4 A 0%fi A55.I SEMt NT Of THE SUB UNil i D BD4 ING MOUR UM U N HI L AM'WW N E AM dHM (W alt t NSP ACHf.

AGAINST L )PI h4ML Ni AL DAT A NUHL G-iF14 H% hi$10RFAL DAT A SUVMARY OF Thl SYtTI M At.

IC A$SLSf. VENT Of LIC[NLil PE nronMANCE AMOS.C.li.

NJhtG/CH 4%1 v /41P') [ y At UAT ION Of Si vt 41 ACCIDt NT NUHl G/CH 4Mt V?R1P2 [VALUAllON Or St Vt HE ACc!Dt N T sup y Oy ANty scAtiON os M Ajon Nout r AqsMi t t nS t,pos TUSKS (/JANTi" CATION Of M AJOH INPUT PARAMLil RS E WW hter.witen Of Stre twas fwMW Mas Delorminatm Of Strutten! H+sponne Istag DRt Y,R R.

AN ALYTIS,0 T*

NahtG%n t??9 VM F 4 W t v biM( 1t h iN sf 5 T m A t oN'>

LOW WASIL DATA DAM LAVilOPVENT P4fMRAM IO4 NUHL G /l A-0040 BOIL Of f E tPin'ME Nf 8 WITH THE [iR Nt PTUN l,i vi l i ACitt1Y. Af 4 ALY SIS AND COD ( A%l SSMI N1 DVt 4vil W jgggt3tgq9999g g g g,p,g h( POf t f.

DRO W N.C.

ARCif fil,W,C.

NUHEG/C115444 lNsinUMt NT AvAiLAnitiTy DuqiN3 61 Vf Hf AG.

NUhf G O4 M Vit UCfNSID T Ul l F ACallT Y STATUS DL PO411nantwy LWe'm o Data JuN 1.19 0 June n 1W1 (3'sy CIDf NTS f 04 A DOttitdG W All D 4EhC10H Wi1H A MARA I CON fhk 11 i AINME NT.

BRO W N.1.D.

ARONSONAL NUNI G/LH SBB EVALUA10NS Of 160 0 Pf0SM D[$tGN hlV' NUsq[G;;n 4%1 y?RtP3 [ v At u AllON Of S[hth( AGCiDEN T SiONS r0%s OUANTillCAllON OF MMOH INPUT FAnAMf TE 5G E wn Determanahon Of 5truct/at Hew on!+ tswes NUHcC/CH5n42 G AS1 HOiNT E STIN AL Ah504P1 tDN Of DROWNED.

PLUTOf#)M URANtUM. AND th PTUNIUM N f LD AND I ASli D Nunt G 13?4 PROPOSE D Mi THOD f 04 klGULAf tNG MAJOH M4 ADULT DADOONS APPUCAltDN TO HUM ANS 1[f 0 Al S LICI NSEt S l

D AkE R.D A CALLANEdh,TM.

NUREG!CH 20$0 V10 POPULAT ON DOSE COMMITV[NTS DUE 10 NJRE G/tAoM3 AN A%E $%Mf NT Of T P AC Pr 1 < M3D1 USINu, RADIOAC11YE hEtt ASES f ADM NUCtI AR POWfil PLANT SITE S STRATCHCl YDE 1/10 ST Att: MDDLL D1iIll TESTS PND hf f0HT j

in a NURE G/tA 00% AN A5M S5Mt N1 Of Tit AC Pf t /MDDt U'iiNG STRA1HCLYDL tito SCAL E MODE L DE F il.L TI 5TS BAUM,J W.

NUREG/CH 57?5 PROGRESS HEPOhi ON HOT PART#CLC $1UDrt S C A3 ADA.D A.

BLAVER$,J A NUhE G/Ch %43 INS!GHT S G AINE D f HOM AGINO 40SE ARCH NUREG/CH 5700 POTE NitODiN AMIC POLARG ATION STUDIE S ON CANDUAff' CONT AINFR At LOvS FOR THE TUFF DEPOSIWY CHAN.BC.

NUhlu!CH $709 PtiitNG GAW AN6C, AND LONG-il RM CORHOSiON NunE G /CR ',815 i V ALU ATONS Of-1 Vit0 Ph6M DC S!GN PC VI-STUDIES ON CANDIDA1L CONT AINER AllOv $ f OR THE 1UT f' 01' blONS DOS:109(

CHE VI RTON R D.

DER ant K,A.

NUMEG/CR 5799 hlVi{ W Or OL ACTOH Ph[$5Ubi V[ SS{ L E V At-NUHiG/CP.0121. AGtNG Hest'AHCH INI ORMA10N CONF LRE NCE,

UATION A[ PORT 004 Y AN>[ L ROWL NUGE AA POMH $1 AllON ABSTR ACT S OF PAPL RS D AE C NO 17P)

BHAT'1ACHARYYA NuhEGICRtS4?.

GASTROINT E ST 6N AL A050nP TION Or CHOWOHURY,A H PLUTONtVM UH AN!UM. AND Nf rYUNIUM IN FED AND F AS1EO NuREG/CR Mt ? RE PORT DN Af 5E AhCH ACTIVITIES F OR C3.LIN ADU(1 C ADOONS APPUCATION 10 HUM ANS DAq Y[a.n 19n NURE'G/CR $725 PROGntSS n[PDqi ON H3T PAnitCLE STUDIES CHUN.R[C RD,R NUHE CR 4%4 V?3 R1 SCAN 3 (SHiPPNG CA% AN AL Y b6 SY ST E M) A MCD3 COMPUTER DA5LD ANALYS:S SYSTLM FOR BLAHNIK D E SHPPNG CAM DEStGN RE CEW Thew Mans h ead Sump in NUhlG'CR %43 IN5tGHT S GAINED i hvM AG%G RESE ARCH

' nPact Analyn And ver Scron Of Imret AnaNu)

NURI G/CH 5799 REVIEW OF RL ACT09 Pnt SSURE vt SSEL LVAL, CHUNG.H M UATION REPO";f 5 04 Y ANkl0 ROWE NUCLE AR POWLH ST ATION NuntGrCa 400.7 vt3 (NanoNVENT ALLv Ass;sTLo (RACMNG IN UGHT W ATER Cf ACTOGS SemianNa! hemrtAm c.er9mter 1911 (Y ALC NO 17351 13

14 Personal Author index COHEN N HACKET1.E M NURE GICR 5642 G ASTROIN1ESTIN AL ABSORPitON OF NUREGICR 5774 ELASTOMASitC CHARACTE R:ZA h0N or A CAST PLUTON'UM URANIUM. AND NEPTUNIUM IN FED AND F ASTED STAINLESS S1EL L hPE E LDOW MATERIAL ADULT BABOONS APPLICA10N 10 HUMANS HANSON.D.J.

CRAGNOEINO 0 NUREGICR 5444 IMTRUMENT N Si @UTY DURING SEVE RE AC-NUREG/CR 5817 REPORT ON RESEARCH AC11VITIES FOR CALE N-RAR YEAR 1990 DDENTS FOR A DOiuNU W ATE w P ACTOR WtTH A MARK i CON 1 ArNMENT.

DE VLAMINCK.M.

H ARPE RJ.T.

NURI G/tA-0Dt1 ASSL SSMENT STUDY OF RELAP5. MOD 2 CYCLE NURE G 'CR.4551 v2 RIP 3 E V AL UATON OF SE VE RE ACCIDENT 36 05 BASED ON THE DOEL 4 M ACTOR TRIP OF NOVEMDER ??,

19M Ri%$ OVAN1181CATON OF M AJOR INPUT PARAMETERS Esterts' Deletminaton Of Structsal Apposse issues DE MPST ER.W,M.

H ARRISON,0.0.

NUbEG/lA4353 AN ASSESSMENT OF 1RAOPF1/MODt UMN3 S1RAlCHCLYDE 1/10 SCALE MODEL REFILL TE S15 2ND MPORT.

sgqEG,cp pse toEgy,FICAllON A':D EVALVATON Or PWR tN NUREG/lA.0055 AN ASSESSMENT OF T RAC.PF 1/ MOD 1 USING VESSE L SEVERE ACCIDENT MANAGE MENT $1RATEGiCB STRATHCLYDE 1/10 SCALE MODEL F;E FILL TESTS HAntrig Eng A, DESCHU1TER#

NURFG-00?O Vi6 LICENSED OPERATWG M AC10RS STATUS SUM NURE Gli A.0061 ACSEF4 MENT STUDY 08 RELAP5/ MOD 2 CYCLE MARY MPOM Data At Of NnM R p Day M 4 36 05 BASED ON THE DOEL 4 RE ACTOR 1 RIP Of NOVEMDER 22.

ggggggg y,gy NUREG 1324 PROPOSED METHOD f OR REGULATING MAJOR MA-picggoy,y,L TERIALS LICE NSEES NUREGICR 5799 MVIEW Or RE ACTOR PRES 5URE VE SSEL EVAL.

UATI E

FOR YANKE E ROWE NUCLEAR POWER STATION I

RE sk 5643 INSIGHTS GAINED FROM AGING RESE ARCH DODGEJ.T.

PE NTIENJ4 D.

NUMG!CR 8617 MPORT ON RESEARCH ACTIVITit S FOR CALEN-NUREG/CR $T69 NATURAL CIRCULATON COOUNG IN U S PMS, 2

DAR YEAR 1990 SURt2ED WATER REACTORS DUKELOWAS.

HICKS.P.O.

NUR9G/CR $0$0 DLNTWICATION AND EVALUATION OF PWR IN.

NUREG/CR467 V13 ENVIRONMENT ALLY ASSIS1ED CRACAING IN VESSEL JEVERE ACCIDENT MANAGEMENT STRATEG;Eg LIGHT WATER REACTORS. Semearn.al Roset.Apul Septemte 1961 DURR.C.L HINS,A.G.

NUnEG/CR 6708 POf ENTIODYNAMIC POLARf2ATON STUDIES ON NURLG/Cd-4f.67 V13 ENVIRONVENT ALLY ASSISTED CRACP.ING IN CANDIDATE ECNTA!NER ALLOYS F0F. THE tuf f MPOSITORy.

LIGHT WATER RE ACTORS Se'n6 annual Report.Apnl Septemtor 1991.

NUREG'CR 6709 PlT11NG GALV ANIC. AND LONG TERM CORROSON STUDILS ON CANDIDATE CONTAINER ALLOYS FOR THE TURF RE.

HOOPINGARNER.K.

POstTORY.

NUREG/CR ttA3 INSIGHIS GAINED FROM AGING RESEARCH E DSON,J L HStVNG,8 M.

NURF.0/CR 5643 INSIGHTS GAINFD FROM AGlNG RESE ARCH NUREG/CR4817: REPORT CN RLSEARCH ACTIVilltS f'OR CALEN,

' FINEMAN.D.L NUREGICR 6643. INSIGHTS GAINED FROM AGWG RESEARCH Hut,TL FLE TCHE R C.D.

NUREG/CR S631 R0t: CONTRIBUTION OF MATERNAL RADONU.

NUREG/CR 5536 VOS RELAPS/ MOD 3 CODE MANUAL User s Gude.

8 I"*"* ""

ging mendatone J ACODUS.M.J.

NUREG/C 5554 V01 At SCANS (SHIPPING CASK ANAEYSIS "

SYSTEMI A MICf40 COMPUTER DA5ED ANALYSIS SYS1EM FOR JARRELLD B.

SHIPPING CASK _ DE SIGN REVIEW Vser's Manual to Vermon 2a (I*

clu$rrg Program Reference).

NUREG/CR $643. INSIGHTS GAINED FROM AGING RESE ARCH OLE ASON,J F.

J ASTROW.J D.

NUREG/CR $762: COMPREHENSIVE AGtNG ASSESSMENT OF. CIA.

NUREG/CR 5229 V04: FlELD LYSIMETER NVESTIGATIONS LOM Culi DREAKERS AND F(LAYS-LEVEL WA$TE DATA BASE DEC DPMENT PROGRAM fOH Fl SCAL YE AR 1991. Annual Report GORMAMJ.D.

JOHNSON.G.L NUREGICR 4551 V2R1P3 EVALUATION OF SEVERE ACCIDE NT RISAS' OUANTIFICATON OF MAJOR INPUT PARAMETERS Experts' NUREO/CR 4t54 V01 R1 SCANS (SHIPPING CASK ANALYSIS Determination Of Structural Response issues SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR SHIPPING CASK DESIGN REVIEW User a Manual To Venon te On-

. gRigNAT.

ciudng Pro 7am Ro'erenre)

NUREG/CR-6817 REaORT ON RESEARCH ACTlvlTIES FOR CALEN, DAR VE AR 1990 JOJT AHE D.M.

NUREG/CR 584); VERIFICATION OF NONLINE AR PtPtNG AESPONSE GRE.GORYAT.

CALCULATON wiTH DATA FROM SEtSMIC TESTIMA OF AN IN-NURE SCR 4551 V2R1P3. EVALUATION OF SEVERE ACCMENT

. PLANT PIPING SYSTEM.

RISKS QUANTFICATON OF MAJOR tNPUT PARAMETERS Experts' Determmation Of Strxtu*al Response issues JO NUR d CR-5707 DRF FC: TIMING ANALYSIS OF PWR FUEL PIN QUNTHER,W.E.

F AILURES Draft fieport For Commerd NUREG/CR 5643 INSIGHTS GAINED FROM AGING RESEARCH JO Y,D.

GUREGHIAN.A B.

NUREG-0430 Vit:

LtCENSED FUEL F ACILITY STATUS NUREGrCR $817 REPORT ON RESEARCH ACTivtTIEC FOR CALEN-REPORT inventory Difference Da*a JWy 1.1990 Jure 30,1991 (Grey DAR NEAR 1990 -

Boos li)

Personal Author index 15 ME ZN AR.CH.H K.

NUREG/CR 5774 ELASTC PL ASTIC CHAR ACTE RttATON OF A CAST NUREG/CR W1 401 CONTR)DUTON OF M ATl HN AL RADONU-JOTCEJA CUDE SURDLNS TO PRENAT Al RADIATON DOSESInter Hean ST AINit SS STE L L PIPE E LDOW M ATERI AL.

K ASSNE R.T.f.

NUREG/U4 4667 Vl3 (NVIRONMLNT ALLY ASSISTED CRACt lNG IN plNARICgJ W, ilGHT W ATE R 84EaCTORS SemanNa; ReportMil Septemt.ee 1991 NURE G/CR 57W RE VIEW Or RE AclOR PRE SSURE VE SSE L EV AL.

UATION RE PORT FOR Y ANKEE RDWE NUCLE AR POWt R S1 ATION KAT EMA.K.R.

gyggg,g 3 7jg)

NUREG/CR $787 D"'T FC TIM:NG ANALYSl$ OF PWR FUEL PIN F A! LURES Dratt Report F of Comment M OK,G C.

t4URE G /CR-45$4 V01 At_ SCANS (SHIPPING LASK AN Ali SIS KAURIN.D Q SYSTIMJ A MICROCOMPUTER BASED ANALYSIS SYSTEM MR NUREG/CR4725 PROGRESS REPORT ON HDT PAR 16CLE STUDIES SHWING CASK DESIGN REVIEW User s Manual To Verson Fa On-thdng PICyam Referente)

RENNET 7,RJ.

NURE G/CR 4554 VDJ R1-SCANS (SHIPhN3 CASK ANALYbtS NURE G/CR 4616 EVALUATONS Or 1990 PRISM DESIGN REVI.

SYSTEM) A MICF 3 COMPUTER BAhED ANALYSIS SYSTEM f OR goyg.

SHIPPING CASK DESIGN REVIEW TNory Manual (lead Wmp in Impact Analysis And Vwife.abon Of impact Analysis).

MIMJ 8.

NUREG/CR $775 OUANTITATivE EVALUATON OF SURViiLLANCE MORETT118.

TEST INTERVALS INCLUDING T EST CAUSED RISAS NUREGICR4842 G AS1ROtNT E STINAL ADSORPTION OF PLUTONIUM, URANIUM. AND NEPTUNIUM IN F E D AND F ASTED NUREG/CRM41; VE AltlCATION OF NON1.NEAR PtPING RESPONSE ADULT BABOONS APPLICATION TO UUMANS KOT CA CALCULATION WITH DATA f ROM SEISMIC TESTIN3 OF AN "J MORGENST E RN.M.

PLANT pipit,G SYSTE M NURE G/CR $856 IDENitrtCATION AND EVALUATON OF PWR IN.

VESSEL SEVEf4E ACCIDENT M ANAGEMENT STRATEGIES RR TTE R,R C.

NUREG'CR 6643. INSIGHTS GAINED FROM AGING RESEARCH MURFIN,W.

NMM E NUREG/CR4551 V2H1P3 EV AL U AT ON OF SEVE RE ACCIDE NT NUREG/CR $650 EXTRAPOLATtON OF THE JM CURVE FOR PRE.

R!SKS. QUANTIFICATON OF MAJOR INPUT PAR AMETERS Experts

• DICTING REACTOR VES$[L INTEGRITY, Deternwnal in Of Structwal Response tsoues LARSEN.RP.

MURPHY OA idVREG/CR $642 G ASTROINT E STINAL ABSORPTION OF~

NUREG/CR 5643 INSIGHTS GAINED FROM AGING RESEARCH.

PLUTONIUM UR AN10:4 AND NEPTUNIUM IN F ED AND F ASTED AWAT BADOONS APPtlCATON TO HUMANS gyppgy g g.

NUREG/CR 6617. REPORT ON RESE ARCH ACTIVITIES FOR CALLN-LEHNER,J R.

DAR YEAR 197J NURLGICR 5802. IDENTIFICATON AND ASSESSMENT OF CONTAIN.

MENT AND RELEASE MANAGEMENT STRATEGIES iOR A BWR NSTA

$799 REVIEW OF RE ACTOR PHESSURE VESSEL EVAL-MARK 111 CONT AINMf NT.

gUgtG VATON REIORT FOR YANKEE ROWE NUCLE AR POWER STATION UN.C.C.

(YAEC NO 1735)

NUREGICR4002: IDr_NTIFICATION AND ASSE SSVENT OF CONT AIN.

MENT AND RELEASE. MANAGEMENT STRATEGIEC FOR A BWR NOUR B AKHSH.H.P.

MARK lit CONT AINMENT.

NUREGICA $747 DAF FC ESilMATE OF RADONUCLIDE RELE ASE CHARACTERISTtCS IN1" CONTAINMENT UNDER SEVERE ACC4-EO,T.

DENT CONDITICv4S Draf1 Fepw1 For Commert NURE G/CR-4554 V03 R1: GCANS (SHIPPING CASK ANALYSIS SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR ADHAM.R.D.

SHIPPIN3 CASK DES 4GN REVIEW Theory Marmal (Land %mp in NUREG/CR4642 GASTROINTESTINAL ADSORPTON OF Impact AnsWs And Vanheation Of Irfcact Analysis),

PLUTONIUM. URANIUM. A*10 NEPTUN1UM IN FED AND F ASTED ADut.T BADOONS APPUCATION TO HUMANS.

MAGELBYJEL NUREG/CR 6041 INSIGHTS GAINED FROM AGtNG RESE ARCH PASALAN,R.T.

NUREG/CR4817; REPCsRT ON RESEARCH ACTIVITIES FOR CALEN-MARTORELL,5*

NUREGICF44776. QUANTITATIVE EV ALUATICN Oc SURVEILLANCE DAR YEAR 1990 TEST INTERVALS INCLUDING TEST. CAUSED RISKS MCCABE D E NUREd/CN4708 A COMPARISON OF WEIDULL AND DOC) ANALYSIS

" # #U # b"***#

OF TRANSITION RANM FRAL,1URE TOUGHNESS DATA-PATRICK,W.C.

WCCONNELL.J.W NUREG/CR4817. REPORT ON RESEARCH ACTIVITIES FOR CALEN NUREG/CR 62h9 Yb4 FIELD LYSNETER INVESTIGATIONS t.OW-DAR YE AR 1990 LEVLL WASTE DATA BASE DEVELOPMENT PROGRAM FOR FISCAL YE AR 1991 Annual Reg PAYNE.A.C.

NUREG/CR-4551 V2 RIP 3 E V ALUATION Of-SEVERE ACCIDE NT MCHUGH.P.R.

RISKS QUANYlFICATION OF MAJOR INN /I PARAMETERS Extwrts' f4UREG.CR 6769 NATURAL CIRCULATION COOUNG IN O S. PRES.

Datenmnaten Of Suwal Response sus SUR12ED W ATER REACTORS.

PEARCH,E.C.

MCKAY,M.K.

NUREG/CR 5817: REPORT ON RESEARCH ACTIVITIES FOR CALEN-NJREG/CR 5813 V01: INTEGRATED REL1ABillTY AND RISK ANALy.

DAR YEAR 1990 SIS SYSTEM (IRR AS) VERSION 4 0 Reference Manue'.

PELAYOA MERKLE.4G.

NUREGRA Or)41. ASSESSMENT OF TR AC.PF1/ MOD 1 AGAINST AN IN-NUREO'CA $799 REVIEW OF REACTOR Pf1SSURE VESSEL EVAL-ADVERTENT STEAM LINE ISOLATON VALVE CLOSURE IN THE UATION REPORT FCv4 YANKEE ROWE NUCLEAR POWER $TATION RiNGHALS 2 POWER PLANT.

(V AEC NO.1735)

l l

l 16 Per&Onsl Author index PENNELL,W1 NURE G'iA 00$$ AN ASSE STME NT OF T R AC PF 1/ MOD 1 USING f

NU6LO'CR.4219 V08 N1: HE AVY-SECTON St[EL TECHNOLOGY

$1RAtttCLYDE 1/10 SCALE MODEL REf tLL 1ESIS PROGRAM Semannual Progress Report For Cctwer 1990 - March 1

1991 SJOB E RO.A.

I f4UREG/lA 0041: ASr ESSMENT OF TRAC PF1rMODI AGAINST AN IN.

i NU EGIC $B42 GASTROINTESTINAL AD SORPTION OF PLUTOdlVMMRANIUM, AND NEPTUNfUM IN FED AND F ASTED g

y ADULT BABOONS APPLICATION TO HUMANS SKINNER,NL RASMUSON.D M.

NUREG'OR $303 V01. SYSitM ANALYSIS AND R:SK ASSESSMENT NUREGICH 061D V0F INTEGRATED RELIABILITY AND R!SK ANALY.

SYS1EM (SAR A) VE PSON 4 0 Rederente Mawal SIS SYSTEM ORRAF) VERSION 8 0 Reference Vanual NUREG/CR4303 V02 SYSTE M ANALYSi9 AND Rl*K ASSE SSMENT SYSTE M (SARA) VERSON 4 0 Tutonal l-ROE,C.

NUREG/CR 5813 Vol. INTEGRATLD RELIABilffy AND Al$K ANALY.

l NUREG/C80$F74 ELASTICSLASTIC CHARACTER 12ATON Or A CAST SIS SYSTEM VARASI VERSON 4 0 Refwence Manust l

STAINLESS STLEL PIPE ELBOW MATERIAL SLOVid,G C, ROGERSJM.

NUREGICH 46 t $ EVALUATONS Or 1990 PRISM DE sign REVI.

NUREG/lA-0052. AN ANALYS!S OF BEMISCALE MOD 2C S-F S-1 SIONS 1

STEAM LINE BREAK TEST U$ LNG RELAP5/ MOD 2 l

SOPPE T,W.K.

UREd 4229 V04-FIELD LYSiMETER INVESTIGATIONS L OW.

LEVEL WASTE DATA BASE DEVELOPVENT PRvGRAM FOR FISCAL YE AR 1991 Annual Report SRIDH AR,N.

ROTHJ.

NUREG/OR4BiL REPORT ON RESEARCH ACTIVITIES FOR CALEN.

NUREG 1324. PROPOSED METHOD FOR RFOULA'IN3 MAJOR MA.

DAN NAN N TERIALS LICENSEES' SRINivASAN.M G.

RUSSELL,K.D.

NUREG/CR 5641. VERIFICATON OF NONLINEAR PIPING RESPONS(

i l

NUREG/CR $303 V01 SYSTEM ANALYSIS AND hiSK ASSESSMENT CALCULATON WITH DATA FROM SEISMIC TLSTING OF AN IN l

SYSTE M (SARA) VERSON 4 0 Referonce Manual PLANT PIPING & STEM NUREG/CR4303 V02; SYSTEM ANALYSIS AND R'SK ASSESSMENT NUREGICR4813 )Voi:SVSTEM (SARA VERSON 4 0 Tutorial STEWART.H D.

INTEGRATED RELIABILITY AND RISK ANALY-NUREG/CR4303 01-SYSTEM ANALYSIS AND HISK ASSESSMENT SIS SYSTEM (IRRAS) VERSON 4 0 9eference Mamel SYSTEM (SARA) VERSION 4 D Reference Manual RUTHER,WE STRRuf NUREG/GR4067 V13. ENVIRONMENT ALLY AS$! SLED CRACKING IN LIGHT WATER REACTORS Semiannual Report Apro September 1991.

NUREG/ lao 040 ' BOIL-OFF EXPERtMENTS WITH THE ElR NEPTUN F ACILITY ANALYStB AND CODE ASSESSMENT OvlRVIEW l

SAGAR.Sf REPORT.

NUREG/CR401P. REPORT ON RESEARCH ACTIVITIES FOR CALEN DAR YEAR 1990 STRAKA,4.

NUREG/CR 5787 DAF FC TIMING ANALYSIS OF PAR FUEL PIN SAMANTA PL F ALLURES Dratt Report For Comment NUREG/CR 5775 OUANTITATIVE EV ALUAllON OF SURv[iLLANCE TEST INTERVALS :NCLUDMG TEST CAUSED RISKS.

SUDVDHI,M.

NUFIEG/CR 5643 INStGHTS GAINED FROM AGING RESL ARCH NUREG/CR 5303 V01: SYSTEM ANALYSIS AND RGk ASSESSMENT SUNLC.

SYSTEM NUREG/CR(SARA) VERSON 4.0 Reference Manual NUREG/CR 5725 PROGRESS REPORT ON H3T PARTICLE STUD {S 5303 V02. SYSTEM ANALYS4S AND RISK ASSESSMENT SYSTEM (SARA) VERSON 4 0 Tutonal.

T A M.P.S.

NUREG/CR 5013 V01: INTEGRATED RELIABILITY AND RISK ANALY' SIS SYSTEM (IRRASI VER$10N 4 0 Reference Manual NUREG-0847 SOS. SAFETY EVALUATON REPORT RELATED TO THE OPERATION OF WATTS BAR NUCLEAR PLANT UMTS 1 AND SCHULTZ,R.R.

2 Docket Non 54390 And 60 391(Tennesse Varle, A&#N NU G/CR 5$15 V05 RELAP$/ MOD 3 CODE MANUALUWs Guajo-THOMPSON,N.G.

NUAEG/CR 5708 POTENTODYNAMIC POLARIZATION STUDIES ON SClACCAf.

CAND!DATE CONTAINER AL'.OYS FOR THE TUFF REPOSITORE NUREG/CR-4627 R02: GENERIC COST ESTLMATES Abstracts From NUREG/CR 5709: PIT 1 LNG. GALVANIC, AND LONG. TERM CORROSION Genenc Studes For Use in Propanng Regulatory impact Ana'ytes STUDIES ON CAND10 ATE CONTAINER ALLOYS FOR THE TURF RE.

POSITORY.

SHACK,WJ..

NUREG/CR4d67 V13. ENVIRONMENTALLY AGSISTED CRACKING IN THR ALL,K.0, LIGHT WATER FWACTORS. Serrmannual Report,ApnbSeptemtwr 1991.

NUREG/CR 5631 A01 CONTRIBUllON OF MATERNAL RADIONU.

54EFKENLJ.

CLIE,i BURDENS TO PRENATAL P ADIATON DOSES Intenm Recom.

mandatens NUREG/CR 5767 DRF FC: tlMING ANALYSIS OF PWR FUEL PIN FAlLURES Droft P9 port For Comment ygyg,p, SIM OV,M.R NURE G-1324 PROPOSED METHOD FOR REGULATING MAJOR MA.-

HUREG/CR 5631 Rot: CONTRIBUTON OF MATEHNAL RACIONU.

TERIALS LICENSEES.

CLIDC BURDENS TO PRENATAL RADiATON DOSES Intenm Recom' aus T RAUS,R.J.

NUREG/CF05631 R00 CONTR!DUTION OF MATERNAL RADONU-

$1a40NENf.A.

CLfDE BURDENS TO PRENATAL RActATON DOSESIntenm Recom-NUREG/CR 5799. REVIEW OF REACTOR PRESSURE VESSEL EVAL.

rnendations.

UATON RiPORT FOR YANKEE ROWE NUCLEAR POWER STATON i

(YAEC NO '735).

TRUMMIR.DJ.

NUREG/CR 4$$4 V01 R1: SCANS (SHIPPING CASK ANALYSIS l.-

SIMPSON,H.C.

SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR NUREG,4A4053 AN ASSESSMENT OF TRAC-PF I/ MODI USING SHIPPING CASK CES!GN REVIEW. User's Manual To Version 2s (In-l STRATOWLYDE 1/10 SCALE MODEL REFKL TESTS 2ND REPORT.

ciuding Program Reference) l l

l l

Pe'sonal Author indes 17 VAN TUYLE,0.J.

W AHD L W.

NJ4[GO f,P15 f i ALU ATONS Cf 1193 PH!su Dt AGN ht vt NUf4 G'CR fi99 HE vlf W Dr Ri AC1DH Phi 59Jf 4L VEb5E L L V AL-ggyg (IATIDN O(IOnt FOff Y AN> ll HOWE N At t A4 PDat 4 ST ATON ti Al; NO 17351 V ANDE NKit BOOM ggq( q 'D S fF NUh!G CH 502 IDE NillICATON ANU ASM StMI N1 O' CONT A N n W V;i4 i 3 (D t Wytit H INit STG AlluNS tOh Mf 41 AND AE L L ASI MANAGE M[NT STRAf f L LS F D4 A P AH AAST[ DAla

[, A?.[ plS(torV(NT PROjhAM f- 04 t, y yt t M AHA l!! CONT AINML Nf gg, qgg,gggy 9,,g V ANHOt N AC Kl.RL WILLIAug K A NURl G /t A 0351 ASSE S WL NT STUDf Or DE L As t MOD 2 CiLLL NUsat u'C 6i s7is9 ht ytt W or hE AC104 PRI 55UHE VL 55f L f val-

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VISE LY,W t..

WITTg,M C.

t49r t Gicn t775 OVAN1 f Ativr Ev ALUAttoN of sun v[

L Nuht G/Cn at54 v33 H+

LCANs 6H+P!NG ( Ask AN AL YS'S TE ST W1[ ne ALS INCLUDiN31E ST.CAU5L D R,5= s SYSit Vi A McRNx;>Mr uti n DASE D ANAlit.ts SiSTLM Ion SHWPIN3 CAbA Dl StG4 DE VIE W itwy Manual (Lead Stump in trtipart Anat<ss Afx! Ver i t atnin O' impact AnW,$4) rf W ADE.N L NUht G/CR-5707 DHf FC 11 MING ANAL YSiS Of PWH Full PIN WOOD.S T.

F AtLUHl S [We't Acpyt f v Comrmot NUht GtCR 53% V01 SYST[ M ANAL YS 5 AND P!5A AE SI SbML Ni Njht oin(san Ai % E hMON 4 0 Hevew e Manuar sy st( M WLil00nsKI,M.

beta Vol

'N T E GH Af t U HE L IAl'iLi! Y AND RISK AN AL Y-NURLO/CP b7M PnOGhlsS REPOHT ON HO f PAHilClf 3TUDd 5 m sn,1r M ponAs> vi Hs!ON 4 D HWenre Manual W ALTHE R,H.P.

Y RJOL A.V.

nun [G/CR-%74 E V AL U A fiON Or M H A VOR AND THE R ADi AL NURI G 'iAOS47 ASSE SSMEN T Of RE L AP5/ MOD? C YC:L L 36 04 SHC AR STREN3f H Of A f4EINf onCLO CONCHE TE CONT A!NVINT

/ G AINST T HE L OVi6A 2 S TUCLO.'l N TURDiNE BY. PASS V AL VE

$1HUCT Unt' TR AN5tE N1 DN 5[Pil MDI H 1,1991

W m

~

__ - - __ -- ^"-~~__

Subject Index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be some redundancy, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements are welcomo.

A $33 Otede b NUldWCR 5?O9 PilTINGLALVANic. ANU LONG if HM CGROOSiON r

NUREG/CR ',78 8 A COMP /stitSON Or WEiDULL AND DK) ANALYSIS STUDIES ON CANDihAti CONT A!Nl8 ALLOYS f04 THI TUf f Hf -

J 5

Or TRAN5f f40N AANGE FRACTURE TOUGHNf SS DA1 A POfa10H r A..

C o,,

.lon,.,,,e NUHf'G/CP 0121 AGING FitSEAhCH INFOPMATION CONrtRENCt NUREGrCH 4%1 V13 ENVIRONMlNT ALLY AwlSit D CHACMNG IN LIGHT W AilR AL ACtOHS Samianrum Heport AH4 Septeinter 1W1 NUi i Cl i

f S GAtNED FROM AGING RE St AHCH Aging Assessment Cost Analys4 NUHEGICR $162 COMPHlHf hSivt AGING ASS (SSMENf of Ciq NUH( G/CH 4627 H02 GENtulC U091 F 816MA f tS Atattarin f rom CUli BREAKERS AND HEt AYS Genn'c Stuale f u Uw in Prepanml Regulatury irrvad Anaiv9es f

Alloy Cracking NUnfG/GR 6709 PITTING GALVANIC. AND TONG Tf hM CORHOSON NUHEG/CH 4M7 V13 ENVIHONMLNYr tLY ASSiS7(D CHACONG IN STUDIES ON CANDIDATE CON 1 AiNLR ALLOTS f 04 THE TUf F NE-LeGH1 WATER RE ACTOHS Senwannual Repo t Armi Septender 1991 r

POSITORY.

t Dose L4mit gg WNIU'Cn $775 PHOGN bs HtPORT ON HOT PAHflCLE S10Dif S NUREG /C94444 IPSTRUMENT AVAlt AfULITY DUR!NG SE Vf RE AC-CIDEN1B FOR A BOILING WATER HL ACTOR WITH A MAPM I CON-

-r U ""*08b0*d Y

T AINVENT.

NUREG/CH (443 INSIGHTS GAINED FPOM AGING Rt St Ar4CH NUNE GiCH 4M1 V2 HIP 1 EVALUATON Or M ViHr ACCIDLNT

+

NURE G/GR 202. IDt NilF ICAllON AND ASSE M.ME NT (4 CONT A:N DiSAS OUANTli tC ATION Or MAJOH INPUT PARAME f ERS Esperti i

MENT AND HElf ASE MANAGEMENT STRATEGtES TOR A HWit

[Mormmanun 01 Siructural Responw inaues MARK lit CONTAINME NT-I PICORE il 808-0 "

NUld GIC4 6229 V04 f l[LD L YNMFitR INVC ST4GAliONS L OW-i NUHEG/lA0040 B01L Of f E XPERIMENTS WITH THE -[.14.NtPTUN LEVEL WASTE DATA HASE (CVE LOPMI NI PROGHAM FOH F ACILITY: ANALYSIS AND CODE ASSESSMENT OWRVIEW FISCAL Yt/ H t991 Antma! Report REPORT.

Ibstic Plastic Dollmg Water fienctor NUREG/CR 6774 ti A$flC=PtAStic CHAHACit HilATON OF A CAST NUHEG/CR 6444 INSTRUMENT AVAILADillTY DURING SEVLHE AC-CIDENTS FOR A BOILING WATER REACTOR WITH A MAf4K I CON-ST AINLf SS STL EL PIPE El00' V MAff HtAL T AINME NT.

I NUNEG/CH4802 IDENTIFICATION AND ASSESSMLNT OF (4Nf MN.

Enforcement Action MENT AND RE LEASE MANAGEMENT STR ATEGi(E IDH A t!Wp NUREG-0940 V10 N04 [Nf 0RCEVENT AC1 TONS SIGNiflCANT AC-MARK lli CONF AINMENT, TONS Rf SOLVED Quatriy Progren Reputf#tohor Decemt.et 1%1 Budget NUREG 1100 V08 DVDGET LSilutif $ riscal Year 1993 Fatique Crack NURf G1CH ST74 iLASTIC-PLAS11C CHA4ACTIRI?AT:GN Or A CAST b

NU E I 5762 COMPREHENSIVE AGtNG ASSESSMENT Or C2H-CUlf BREAklRS AND REL AYS p g,, y,,,

Concrete Aomg

- NUNCO-1100 V0B SUDGET f ST! MATES Fiscal Year 19M NUHfG/CR M74 FVALUATION Or BCHAVIGH AND THE RADIAL SHE AR STRENGTH OF A PflNT ORCED CONCHETE CONT AINVENT f racture Mechanks STHUCTUHF NUREGrCR 5799 REV!EW Of REACTOR PRESSURE VESSEL EVAL.

DATION REPORT FOR YANKEE ROWE NUCLEAR POWER St ATION Containment (Y AEC NO 17351 -

t NUREG/CH4M t V2H1P3 EVAt.UATION OF SEVERE ACCiDE NT RISKS. QUANTiflCATON OF MAJOR INPUT PARAMETERS Luperts' Fracture iAethodology Ontormir won Gf Structtsal Heapnnte Inues

- NUHf G/CR %50 i XTRAPOLATON Of-THE J R CUHVE FOR PRE.

NUDt G/CR 6674 EVALUAf 0N OF Bt HAVIOR AND THE RADiAt p,CT!NG RE ACTOR VESSf t INT [GRITY SHEAR STAl'NGlH OF A RL1NFORCED CONCRE1E CONTAiNMLNT STRUCTURE-Fracture Toughness NUAEGICH474'/ DHF f C. CS1! MATE OF RAD 40NUCUDC RELEASE NUHtG/CM S7es A COVFARISON OF WUBUIL AND D110 ANALY9s CHARACTERISTICS iNTO CONT AINMENT UND0H SEVERE ACCI Of TPANSITON RANGE F RACTURE TOUGHNE SS DAT A Of NT CONDt fiONS Dratt Hepori F or Comnw+nt Fractured Media Core Coonng NUREG/CH $769 NATUHAL CIRCUL ATION COOtING IN U S PHES NUREG/CR 5817 REPORT ON HES[ AHCH ACTIVITIES FOH CAtEN SURIZE D W ATEH RE ACTONS DAR YE AR 1990 t

Corrosion Fuel Pin

+

NUREG/CR 5700 POTINTODYNAMIC POL ARi2AllON STUD 4ES ON NUREG/CR S787 Dur FC TIMNG ANALYSIS Or twn ruEL pin CANDIDATE CONTAINER A1LOY% FOR THE TUFF 4(POS: TORY F ALLURE S Draft Hoport f or Corns ioni r

19

.. ~ -..

20 Subject inciex oneiroanie.mai Aa,sorpuon ucenaea Operating Reactors NUREGICR $842 GASTRO4NTEETINAL ABSORPTION C#

NUREGOO20 V1C LICENSED OPERAf tNG REACTOR $ STATUS SUM-PLUTONIUM. URANIUM, AND NEPTUNIUM IN FED AND F ASTED MARY REPORT Data As Of Decemter 31,1991(Gray BxA t)

ADULT BADOONS ADPUCATION TO HUMANS.

Licensee Event Report Hoevy $ecton Steel Technology Program AURE G/CA-2000 V10N12 UCENSEE EVE NT REPORT (LER)

Ni$1EG/CR 4299 V0f N1: HEAvvM J10N SWEL TECHNO'.'X1Y COMht ATON Fos Month Of Decemter 1991.

PROGRAM Semannual Pro 9'ess Report For October 1993 March NURE G/CR-20'O V11 N1: UCE NSE E EVENT REPORT (LE R)

J 1991.

COMPILATON F'or Month Of January 1992 H Eevel Waste D6spossa

"'*"M4'"EcM*Tb FOR REw'^= u^;m MA-

'"" M M O a ? " M #S M ?h'E M " M s*Y Nu NURLG/CR 5709 PtITING, gat.VANC, AND LONSTE nM CO8 ROSON TERIAL $ UCT NSE ES S IDI 4 CANDOATE CONTAINER ALLOYS FOR THE TUf F RE-L,9h,,,,,,g,,c,,,

NUREG/C$14667 V13 EfCRONMENTALLY ASSISTED CRACKING IN Hot Part6cle UGHT WATER REACTOaB Semant'ual Repo<t.A vtScPlember 1991-l NUREG/CR 572$ PROGRESS.it PORT ON HOT PARTICLE STUDIES Liquid Metal Cooled Reactor ICAP Program NUREG/CR 5815 EVALVATONS OF 1990 PR:SM DESIGN REVI-NUREGriA4040 BOILCFF E PERIMENTS WITH THE EtR 41rDTUN SiONS F ACILITY: ANAL,YS?S ANE CODE ASSE SSMENT O(ERVIEW Rt POat Lo..Ee.e Wesi.

NUREG/lArit. ASSESSMENT OF TPJ C-PF1/ MOD 1 AGAINHT AN IN.

NUREGICR 5229 V04 FIELD LYblMETE A INVES1!GATIONS LOW ADVERTENT STEAM UNE l$0LATILN VALVE CLOSURE IN THE LEVEL W AS1 E DATA BASE DEVELOPMENT PROGRAM FOR MSCAL YEAR 19nAnnsal rem NUi 1

1 SSES 4T STUDY OF RELAP5/ MOOT CYCLE J6 05 DASED C" THE DOEL 4 AFACTOR TRIP Or NOVWeER 22, to,.pe,,, op,,,gion NL O/lA4052 - AN ANALYSIS OF SEMISCALE MOD 20 - S F S 1 NUREG 1449 DRFT FC SHUTDOWN /ND LOW-POWER OPERATION STE AM UNE BAE Ak TEST USING RELAP5/ MOD?

AT NWAR NH MAWB W M W6 M AM Dan W NUREG/LA-0053 AN ASSESSMENT OF T RAC.Pf i/ MOD 1 USING 6 Comment STRATCHCLYDE 1/10 BCAL E MODEL REFILL TESTS 2N3 HEPORT.

NURE G/lA.OoS5 AN ASSESSMENT OF TRAC-PF 1/MOC 1 USING Lysimeter STRATHCLYDE 1/10 SCALE MODEL REMLL TE STS.

NUREG/CR 5229 V04 FIELD LYSIMcTER INVESTIGATONS LOW-NUREG/LA-0056 ASSE SSMLNT Of THE SUB COOL ED DOfLING LEVEL WASTE DATA BASE DEVELAPMENT PROGRAM FOR MODEL USED IN RELAPS/ MOD 2 (CYCLE 36 05 VERSION 00'l)

MSCAL YE AR 1991. Annual Report AGAINST EXPERIMENTAL DATA.

Mark i Contahrnent -

IRRAS NUREG/CR 6444. INSTRUMENT AVAILABiUTY DURING SEVEriE AC-NUREG/CR 5813 V01: INTEGRATED REUAfilLITY AND RGK ANALY' CIDENTS FOR A BoluNG WAFER HEACTOR WITH A MARK l CON-SIS SYSTEM (IRRAS) VER$10N 4 0 Reference Manual T Aiyytyt, NU GC 58 DENTHCATON AND ASSESSMENT OF CONTA!N D

R ACT VES IN G TY' MENT AND RELEASE MANAGEMENT STRATEGIES FOR A SWR LER MARK lit CONI AINMENT.

NUREG/CR 2000 V10N12 LICENSEE EVENT REPORT (LER)

COMPILATION For Month Of December 1991.

Materials Ucenaces NUREG/CR 2000 V11 Nt: LICENSEE EVENT REFORT (LE R)

NURE41324 PROPOSED METHOD FOR REGULATING MAJOR MA-COMPILATON Fur Month Of January 1992 TERiALS UCENSEES LOCA Mictocomputer Program NUREG/CR $761 DAF FC. TIM'NG ANALYSIS OF FWR rVEL P N NUREG/CR4554 VC1 R1: SCANS (SHIPPING CASK AN ALY S6S t ALLURE S Dralt Report For Comment SYSTEM) A MCROCOMPUTER BASED ANALYSl$ SYSTEM FOR LOCA Refill SHIPPING CA$K DESIGN REVIEW Usei a Manual To Versson Es (In-NUREG/ WOOL 3.

AN ASSESSMENT OF TRAO-PF1/ MODI USING N

V 1: SCANS (SHIPPING CASK AN AL YSIS NL E /t 5 AN AS E

C TA 1

i t SY3 TEM) A MCROCOMPtF'ER BASED ANALYSIS SYSTEM FOR STFMThCLYDE 1/10 SCALE MODEL REFILL TESTS.

SHIPPING CASK DESIGN REVIEW. Theory Manual (Lead Glump in impact Anaysis And verificaton Of impact Analy$s)

LOVilSA 2 NUREG/lA 004f; ASSESSVE NT OF RELAP5/ MOD 2 CYCLE 36 04 NONPtPE Code AGAINST THE LOWSA 2 STUC%OPEN TURBINE '3Y. PASS VALVE NUREG/CR 5841: VERIFdAflON OF NONLINEAR P:PlNG RESPONSE TRANSIENT ON SEr'IEMCER 1,1981, CALCULATON WITH DATA FROM SEtSMC TESTING OF AN IN-PLANT PIPING SYSTEM NUREG/CR-4667 V13. ENVIRONMENTALLY ASSISTED CRACKING IN Natural Circulation Cooling UGHT W ATER REACTORS Semiannual Report.Apr& Sop ember 1991.

NUREG/Cf457ee NATURAL CIRCULATON COOUNG IN U S PRES-SURilED W ATER RE %CTORS.

g,,g g g

NUREG 0750 V34101 INDEXES TO NUCLEAR Rf GULATORY COM' Neptunkha FNE kVORY COMMISSON 1%

NWEWM5M M ROW M M AERM N

NU So V SUANCFS FOR NOVEMBf' A 1991. Pa 261 298 NUREG 0750 V34 N00 NUCLEAR RE JL ATORE COMMISSION IS.

ADULT BABOONS.APPUCATON TO HUMANS.

$ DANCE S FOR DECEMBER 1991. P s 29747f.

NUHiG4750 V35 Not. NUCLEAR R Ut.ATORY COMMIESON IS.

Once Through Steam 0enerator SUANCES Foil JANU ARY 1992. Pages 146.

NUREG/CR476tr NATURAL CIRCUt.ATON COOUNG IN U S PRES-SURt2ED WATER REACTORS Ucensed 'uel Facmty Statua Report NUREG 0430 V11:

UCENSED IVEL FACiUTY. STATUS Organuation Chart REPORT. inventory Odference Data July 1,1990 June 30.199t(Gray NUREG.0325 R15 U S NUCLEAR REGULATORY COMutSSON FUNC-Ba:A 11).

TONAL ORGANIZATON CHARTS. January 31,1992, I

+

i

Subject index 21 PRA Rt EAPl/ MOD 2 NURIG/CR f003 V01. SYSTEM ANALYSIS AND R SA ASSESSMENT NUAE GaAW>40 Boit.Off L XPE RIMENTS W11H THE E IR N(PluN SYSTI M IS ARA) VE RSON 4 0 Rot ~en e Mansal F AciLIT Y AN AL YSIS AND CODE ASM E SSML NT OVi fR/ll W NUHLGICR 5303 VE2 M115M ANALYSIS AND HISK ASSE S4ME NT sgpORT SYST EM (SARA) VERSION 4 0 Tvional NURE G.tAao47 ASStSSMtN1 OF ht LAPS / MUD 2 C1 CL E 36 04 AGAINST THE LOMA 2 STLOK OP(N TURBINL BVSASS VALVL PW 1H AN',lE NT ON bl Pil MN A 1.1Mi NURE G/CR 5615 EVALUATONS OF 19M PRISM DE SIGN RE vi' Nant G/6A OD51 A%t SSME NT STUDV Dr RE L AP5' MOD / CYCL E EN 36 05 BAStD ON THE DOLL 4 RE ACTOR TRIP OF NOVlMDER 22.

N 11 GnAo05? AN ANALYS:S OF SiutSC'LE MOD 2C S f S-t JREGICH %431NSIGHTS GAWi D f ROM AGING HESE AHCH NUREG/CR 5769 94A1 URAL CIRCULA104 CCOUNO IN U S. PHE g.

STL AM LINL DRt AM llST USh3 ret AP5/MOL2 SURIZED WAYlH Rf ACTORS NURLG4A W A%mW N1 M THE SUB MW D W IW NURE G/CR 5787 DRF (C ltM NG AN.8LYS!S OF PW R F UL L PIN MODEL 1;5t D IN RE LAPS / MOD 2 (CYCll 30 0tt VE RS ON L OM F All URE S Drott Raget For Comment AGAiNST EUTH1 MENT AL DAT A NURtG/CR 5%6 IDLNTIFILAflON AND [VALUATON OF PWR IN VESSEL SEVERE ACCIDENT MANAGEMENT STRAf tGilS RELAPf,/ MOD 3 Computer Code NURF G/CR 5135 VOS hE LAP 5/ MOD 3 CODE MANUAL User a GA Performance History lines NVREG-1214 R09 HISTORICAL DAT A

SUMMARY

OF THE SYSTEMAT-IC ASSESSMENT OF LICENSEE PERT ORMANCE Radiation Dome NUr4E G /CR W t R01 CONTNBUTON OF MAT E RN AL HADIONU.

Petitions Foi lulemaking CUDE DURDi NS TO PRE N AT AL R AD: ATION DOSE S Intenm Hecom-i NUREG W 6 V10 Na4 NRC RE GUL ATORY AGE NDA CNarteny mesta%ns Reput.Octc6er-Docemter 1991, Radiation Effect UFCG/CR 5774 ELASTIC PLASTIC CHARACTERilATON Or A CAST STAINLLS% STErL Pilt ELOOW MATERIAL Radioactive Release NUNEG/CR 2650 V10 POPULATION EOSE COWi1MENTS DUE TO RADCACM ht LEASE S F HOM NUCLE AR POM R Pt ANT bite S N EGICR $841 VE RIFICATION Or NONLINEAR PIPING RESPONSE IN CALCl)LATON WITH DAT A FROM SliSMIC 1ESilNG OF AN IN.

Pt ANT PlPnNG SYSTEM.

Redsonuclide Plutonburtt NUHEG/CR M31 R01 CONTHtUTON Of M AT E RNAL R ADQNU-NUHEC/CR 942 GAS 1 ROWTL 311N AL ABSORPTON Or CLIDE DURDENS TO PRL NA1 A'. RADIAllON DOSES Intmm Recorm PLUTONIUM VfiANIUM. AND NEPTUNIUM IN FED AND FASTED rnnrxtatens AOULT BADOONS APPLICATION TO HUMANS-Radionuclide Release Population Dose NunEG/CR 5747 DRF FC LSTIMATE OF RADtOM N OE Rf LEASE NUREG/CR 2850 Vtu POpVLATON DOSE COMMITMENTS DUE TO CHARACTEHisilCS INTO CON 1 AINMlNT UNDER SEVERE ACCl-RADsOACTIVE RELE ASLS FROM NUCLEAR FOWER Pt ANT SITES M NT COND!10NS Deatt Report F cv Comment IN IM8.

Reactor Potentlodynamic Polartaat6on NUHEGiCR %43 INSOH15 GAINED f HOM AGING DESE ARCH NUREG/CR 5700 POTENTODYNAMIC POLAH12ATION STUDIES ON CANDtDATE CON 1 AINLR ALLOYS FOR THE TUFF RE. OSl10Hy Reactor Acc6 dent NUREGICR 5747 DRF IC-ESTIMATE OF RADIONUCLOC RELE ASE Proctko And Proceiture Digest CHAHACTE RistlCS INTO CONTAINMENT UNDER SEVE RE ACCl-NU4 EGO 386 006 ROI: UN11ED STATES NUCLE AR REGULATORY DENT CONDITIONS tutt Report For Comment COMMISSON STAFF PRACTICE AND PROCE DURE NUREG/CR 900. IDE NTillCATION AND ASSESSMENT Or CONTAIN-DIGEST Commission. Appeal Board And Ocenung Decmcens Aly 1972 MENT AND RELLASE MANAGEMr NT STRATEGIES FOH A BWR Mwch 199L MARK lll CONT AINMENT, NUREG/CR-5816 EVALUATIONS OF 19W PRISM DESIGN RE VI-Prenatal Does giONS NURE G/CR 5631 RO1 CONTR!BOTION OF MATERNAt. RADONU-CtIDE DURDENS TO PRENAT AL RADIATON DOSES Intenm Recom-Reactor Pressure Vessel mandatens NURE.;/CR %50 ExTRAPOLATON OF THL J R CURVE f OR PRE.

DICTING REAC10R NiSSEL INTEGRITY, Pressure Vessel NUREG/GR 5/99 REVIEW C# REACTOR PRESSUHE VESSEL EVAL.

NUREG1CR-4219 VOS Nt AE AVY SECTION STEEL TECHNOLOGY UATION RE PORT F OR Y ANAEE ROWE NUCLE AR POWER ST AllON PROGRAM Someannual Pro 0ress Report f or October 1990 March (Y AEC NO 1735)

N NURE G/CR 5856 IDENTIFICATION AND EVALUATION OF PWR IN' VESSEL SEVERE ACCIDENT MANAGEMENT STRATEGIES Pressurtred 'hermal Shock NUHEG/CR 5799 REVliW OF REACTOF, PRESSURE VESSEL EVAL-p UATON REPORT FOR YANKEE ROWE NUCLEAR POWER STATON NUREG/CR 5775 OUANTITATivE EVALUATION OF SURVElt LANCE WA NO. m 1EST INTERVALS INCLUDING TEST CAUSED RISAS P.essurized Water Reactor NUHEG 'OR 5815 EVALUATONS OF 1990 PRISM Di SIGN REVI-NUREG/CRM43 INS 8GHTS GAINED FROM AG;NG RESEARCH SIGNS NUREG/CR 5769' NATURAL CIRCULATON COCONG IN U S. PRES.

SUR12ED WATER RE ACTORS Reactor Trip NUREGICR $707 DAF FC Ti%NO ANALYSIS Of PWR FULL PIN NURF G!!A 0051 ASSESSML NT STUDY OF RELAP5/ MOD 2 CYCLE F ALLURES Draft Report For Comment 36 05 DASED ON THE DOEL 4 Al ACTOR TR>P OF NOVEMotR 22, NURE G /CR-M56 IDENTIFICATION AND EVALUATION OF PWR IN-19 %

%ESSEL SEVERE ACCIDENT MANAGEMENT STRATEGtES Regulatory Agende ProbatMilstic Risk Assessment NUME G-0936 V10 N04 NRC ht GUL AT OR f AGENDA Ouarteny NUHE G /CR4551 V2 RIP 3 EVALUATON OF SEVERE ACCIDENT Heport October December 1991 RSKS QUANTIFICATION OF A4AJOR INPUT PARAMETERS Erports' Determinaton O! Structura! Resronse issues Regulatory impact Analy6es NUREG/GR 0005 V01 n'SK DASE D INSPECTION, DEVELOPMENT OF NUREG/CR 4E27 RC2 GENLPiG Cost ESTIMATES Ateams From GUOC UNE S General Documen' Gerenc Stuses For Use in Prepamg Regulatory impact AnM,$es

22 Subj2ct in2x Reguatory Method NURE G/CR an4 V03 R1 SCANS (SH.PPING CASK ANALYSIS NUREG 1324-PROPOSED METHOD l'OR REGULA'tNG MAJOR MA Sv51EMn A MCROCOVPU1ER BASLD ANAtibis Sv5 FEM FOR TERLALS L4 CENSE E S GHfPPING CASK DESIGN REVIEW Theor) Manual (Lead %mp in Retnforced Concrete t4UREG/CR4674= EVALUATON OF f4EHAVOR AND THE RAD 4AL Shvidown SefEAq STPENGTH OF A RE!NFORCED CONCRETE CONT AINMENT NUREG 1449 DHf1 FC. SHUTDOWN AND LOW POWTfi OPERATON STRUCTURE.

AT NUCLE AR POWLR PLANTS IN THE UNIT E D ST ATES Dra'i Report F or Comment HUREGICR-576? COMPREHENSfvE AGING ASSESSMENT OF CIR-Stainless Stul CUit BREAKERB AND RELAYS NUREG/CR4774 E LASTIC PLA$1tC CHARACTER 2 ATON OF A CAST Research Activity NUREG/CR4817. REPORT ON RESEARCH ACTlylttES FOR CALEN Steam line Dreak DAR YE AR 1990 NUAEG4A-0052 AN ANAL) SIS OF SE MISCRI MOD FC STS1 Risk Assessment NOREG/CR Le13 vot-WTEGRATED HEt, ABILITY AND R4K ANALY.

Steam Line isolanon Vetre SIS SYSTEM (IRRASI VERSON 4 0 Reference Manual NOREGriA.co4t ASSESSMENT C* 1RAC PFI/ MODI AGAWST A4 IN ADVERTENT STEAM UNE ISOLATON VALVE CLOSURE IN THE Risk Assessment System 84fNGHALS 2 POWER PLANT' NUREG/CR 5303 V01 SYSTEM ANALYSf3 AND R!SK ASSESSVE NT SYSTEM (S'M) YERSON 4 0 Reiv'ence Manual SutFCooled Nucleate BollinD

~

NURE GUA 00La ASSESSVENT OF THE SUB-COOT E D BOILING

_ fgg o

D A

C WW M E MSON %

N iEG/GR

1. RISK. BASED INSPECTON DEVELOPMENT Or g

GUIDEUNE $ Genua! DocumeM 8""'""' ' I I Ruin a

NUREG/CR 5775-QUANTITATIVE EVALUATION OF SURVIILLANCE NURE60916 V10 t404 f4RC REGULATORY AGENDA Ouarterfy TEST INTE RVALS INCLUDING TESTCAUSC D R:SKS Repor1.Octobe December 1991.

Rules Of Procuce System Analyste And Risk Assessment System NUREG 0386 Doo Rot. UNITED STATES NUCLEAR REGULATOHY NUREG/CR 5303 V02 SYSTEM ANALYSIS AND RISK ASSESSMENT SYSTEM (SARA) \\ E R$0N 4.0 Tutonal.

COMutSEON STAFF PRACTICE AND PROCEDURE OlGEST Commiscon, Appeal Board And trensing Decisions July 1977 Systemat6c Assessment Of Licensee Performance M*'Ch 1991-NUREG-12td R09 HISTOroCAL DATA

SUMMARY

OF THE SYSTEMAT.

BARA IC ASSE6SMENT OF LICENSEE PERFORMANCE NUREGICR5303 V01: SYSTEM ANALYSIS AND RISK ASSESSMENT TRAC BD1/M001 SYSTEM (SARAJ VERSON 4 0 Ra erence Manual NUREG/lA-0040- BOIL-OFF E APERIMENTS WITH TME EinNEPTUN SCANS F ACIUTY-ANALYSIS AND CODC ASSESSMENT OVERVIEW b

L NUREG'CR 4554 V01 R1: SCANS (SHIPP1NG CASK A14 AL YSiS SYSTEM) A MICROCOMPUTER BASED ANALY3IS SYSTEM FOR TR AC-PF1/ MODI SHIPPING CASK DE SIGN REVOW User's Manual To Vrn on ta en*

NUREGAA.0041 ASSESSMENT OF TRACff t/ MOD 1 AGAINST AN IN-f4 E CWv 1 SCANS (SHIPPING CASK ANALYSIS R HA S2 P li SYSTEMS A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR f4UREGdA.0053 AN ASSENMENT Or TRAC PF1/ MODI USING

- SHIPPING CASK OESIGN ret /IEW. Theory Manual Gead Slump in STRATCHCLYDE 1/10 SCALE MODEL REFILL TEST 3 rN9 RE PORT.

Impact Analyws And Venttation Of impact Analysial-NUREG/tA4055: AN ASSES 5 MENT OF TRAC PF1/ MOD 1 USING Safety Evaluation Report STRATHCLVDE 1/10 BCALE MODEL REFILL TESTS NUREG,0847 S06' SAFETY EVALUATON REPORT RELATED TO THE Techn4cel Spect6ce tions OPERATION OF WATTS BAR NUCLEAR PLANT. UNITS 1 AND NUREG/C457 F5. QUANTIT/iTIVE EVALUATON OF SURVElLLANCE 2 Docket Nos 50 390 And 50 391]Tennesse Valley AuthorM TEST INTERVALS INCLUDtNG TEST-CAUSFD RISKS NUREG-1135 S01: SAFETY EVALUATON REPORT RELATE D TO THE CONSTRUCTION PERMIT AND OPERATING L' CENSE FOR 1HE RE-Thermal-HydrauM SEARCH REACTOR AT THE UNIVER$lTY OF TEKAS Docket too. 50-NUREG/CR $535 V05-RELAPS/ MOD 3 CODE MANUALUser's Guide-6024the Univgrsity Of Texasi knet Setemic Testm9 Thermohydraulic NUREG/CR.5641: VERIFICATON OF fv0NUNEAR PIPtNG TESPONSE NUREG/CR4817; REPORT ON RE 1. ARCH ACTIVITIES FOR CALEN, CALCULATON W1TH DATA FROM SEISMIC TESTING OF AN IN-DAR YEAR 199*

PLANT hPING SYSTEM. -

Title List Severe Accident NUREG-0540 V13 N11. TITLE UST OF DOCUMENTS MADE PUBUCLY

.NUREG/ COTS 51 V2R1P3 EVALUATION OF SEVERE ACCIDENT AVA'LAOLE November 1-30, 1991, RISKS OUANTIFICATON OF MAJOR INPUT PARAMETERS Emperts' NUREG 0540 V13 N12. TITLE UST OF DOCUMENTS MADE PUBUCLY

- Osterranation Of Structural Response issues AV AILADLE. Decertber 1 31.1901 NUREG/CR-5444 (NSTRUMENT AVAILABluTY OURING SEVERE AC-f4UREG-0540 V14 Noi: TITLE LIST OF DOCUMENTS MADE PUBl.lCLY CIDENTS FOR A BO1 LING WATER REACTOR WITH A MARK i CON-AVAILABLE. January 131,1992

- T AINMENT MllREGICR 5747 DRF FC'. ESTIMATE OJ RADIONUCUDE ret. EASE TuH f;epository CHARACTERISTICS INTO CONTAINMENT UNDER SEVERE ACCI NUREG/CR 5708. POTENTODYNAMIC POLARIZATION STUDIES ON DENT CONOR ONS Draft Report For Comment.

CANDOATE CONTAINER ALLOV5 FOR THE TUFF REPOSITORV.

NUREG/CR.5656 IDENTIFIC-ATiON AND EVALUATON QF PWR IN-

-MUREG/CR 5709-PITTING. GALVANIC, AND LONG. TERM COGROSON

. VESSEL SEVERE ACCDENT MANAGEMENT STRATEGtES STUN

• ON CANDIDATF CONTAINER ALLOYS FOR THE TUFF RE-Shipping Cask.-

NUREG/CR.4554 V01 R1: SCANS (SH'oPING CASK ANALYSIS Turbine By Pass Vatvo SYSTEM) A M?CROCOMPUTER BASED ANALYSIS SYSTEM FOR NURE' IA-0047. ASSESSMENT OF RELAP5' MOD 2 CYCLE 3304 o -

54PPING CASK DESON REVEW. User's Manual To Verson 2a Crw AGA NST THE LOVilSA 2 STUCK OPEN TURBINE BY4 PASS VALVE ciudsng Program Re'e ence)

TRANSIENT ON GEPTEMBER 1,19b1.

Subj:ct index 23 v.no, in.p.ct.

urwem

- NUREGICR 6642:

GA$fROINiCSitt4AL ABSORP1CN Or NUAEGaldo V16 N04 LICENSEE CfY4THAC1CR AfdD VENDOR 6N.

SPECTON STATU5 AtPOr f, Quaderly Rewt orioter CWemter PLUTONIUM UAAfdfUu, AND NEPfutilUM IN FED AND FASTFD W MM' BN*)

ADVT.T BABOO 4S APPtnCATION TO HUMANS Weibull NUAEG/CR 6768. A COMPARISON Or WE60Vlt AND IWC) AN ALYSiB OF TRANSITION RANGE FRACTURE TOtJGHNFSS DAT A

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NRC Originating Organization Index (Staff Reports)

This index lists those NRC organizations that have published staff reports. The index is ar.

rangea alphabetically by ma or NRC organizations (e.g., program offices) and then by sub-sections of these (e.g., divis ons, branc los) where appropriato. Each entry is followed by _a NUREG number and title of the report (s), if further information is needed, refer to the main citation by NUREG number.

OFFICE 04 tItCUflVE DIRECTOR FOR OPERATIONS (tDO)

NUREG 1M4 PROPOSCO METHOD FCe REGULATING MAJOR MA-OFCofINFORCEMENTjPOSI 8704131 TERmLS DCf NSEf B HURT 30940 V10 NM $NFORCEMENT ACTIONS SIGNIF CANT AC.

TONS RESOLVLDOverterly Progress Report Ocioter-Decemt+r U.S. NUCLEAR FtEOULATORY COMMISSION 1998 OFFICE OF THt GENERAL COUNSEL t OST A50701)

P N

062 1

NUCL P FtEGULATORY COMViSSION CONON STAU KACy AW-MW T UNCTIONAL ORGAN 6Z AT ON CHART S Jawary 31,1992 DIGESS CwwusmAppeal Br d av Leenmng Decisor* July 1972. March 1991 (OO. OFFICE OF ADMINISTRATION (PRE $70413 & POST 49070$)

NRC NO DETAILED AU1UATON GIVEN D!VISON OF FREllOM 08 INFORMATION & PUDLICATONS SERV.

NU"EG/CR 5613 V01: INTEGPATED RELIADlilTY AND RI% ANAL-ICES (FOST 89020$

HUREG4540 V13 N11: TITLE LIST OF DOCUMLNTS MADE PUdtfG vS:s SVSTEM (!RRta VE RSON 4 0 Reference Manual LY AVAll ABLE Novereder 1 30.1991.

NUHEG4540 V13 Nt?. TITLE usf OF DCCUWNTS MADE PUDLIC-EDO. OFFICE OF NUCLEAR Rf GULATORY REbt ARCH (POST 870405)

LY AVAll ABt E Decert** 1 31,1991 DNtSON OF ENGINCE RING t OST 670413; P

NUREG 07hD V34101: INDEy.ES TO NUCit AR REGULATORY COM NUREG/CP4121: AGING RESEAf04 idiORMA10N CONFERLNCE MMON ISSUANCESJuly-SaptemNet 1991

. AgstpActs og p4ptps NUREG?750 V34 N05 NUCLEAR REGULATORY COMM:$5CN IS SUANJS FOR NOVEMDER 1991 Pages 261-235 too. OF FICE OF NUCLE AR RE ACTOR REOULATiON (POST 600470)

NUREG 0760 V34 ND6 NUCLEAR REOULATORY COtrMISSION IS' DNislON OF REACTOR PROJECTS Inl (POST 870411) 1 SUANCES FOR DECEMDER 1991. Papas 297 378 NUREG4A47 SOS SAFETY EVALUAllON RD'OHi RELATED TO NUREG-07t0 V36 Not, NUCLE AR REaulA10RY COVMiSSON IS' THE OPERATON OF warts BAR U"OL E AR PLANT, UNITS 1 AND EDodet Nos 60 390 And 60 391(lentwe Valioy Aut*erity)

REWL ORY AGE NDA Quartody DnhSON OF ADVANCED REACTORS & OPECIAL PROJf CTS NU [

.6 VO

1. 1 NRC Report (HoteDecember 1991 (901216 920510)

NUREG 1135 501; SAFETY tVALUAftON REPORT RELATEC TO EDO. OFFICE OF THF CONTROLLER (PRt $20418 & POST 890206)

THE (CNSTRC, TION PERMIT AND OPER ATIt'3 LICENSE FOR DIVISON OF DVDGET & ANAL VSIS (POST 89020M HUR1G 1100 Vots DVDGE1 ESilMATE S Facal Year 1093 THE RE5 LARCH REACTOR AT THE UNfvf RSITY OF E00. OFFICE ut INFORMATION RESOURCES MANAGEMENT & ARM D

10 0 T

S 2'

NURE G-1449 DRrT FC' SHU1DOWN AND LOW POWl R OPE R-Or iN MPUTER & TELFC(A4MUNICATKNS SE RVicc o AftCN AT NUCtE AR POWEH Pt. ANT S IN THE UNIT E D l

(POST OW1M ST ATES thsti Report F or C.wnment NUREG4020 Vie. LICENSED OPERATING REACTORS ST ATUS F3UMMARY REPORT. Data As Of December 31,1991 (Gray BW 1)

DIVISON OF REAC'OR IN9"ECT ON & SAFEGUARDS (POST 670411)

DIVISON OF INFORMATION SUPPORT SERvlCES (POST 89020M NUREG4040 Vib Nod LICENSEE CONTRACTOR AND VEr4 DOR IN.

NUREG-0540 V14 N01: TITLE LIST OF DOCUMENTS MADE PUDLIC-LY AVAILABLE January 1,31,1992 SPC C10N ST ATUS REPORT. Quaderty Retert,0ctober Decemter 8

DIVI 4

L PERFORMANCE & TIAt TY EVAlt. TION F

N

[A VAT RI%L LTY SA EGU S

POST 87Nm NUnt Ge430 Vil: LICE 15L D FUEL F ACill1Y STATUS NUREG 1214 F409 HISTORICAL DATA

SUMMARY

OF THE bYSif M-Juns 30, REPORT inventory Diffe<ence Data e dy 1,

1990 Afl0 ASSESSMCNT OF LICENSEE PERFORMANCE 1991.(Gray Doch 14 25

l 9

4

I NRC Originating Organization index (International Agreemonts)

This index Ikts those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s), if further information is needed, refer to the main citation by NUREG number.

EDO OFrlCE OF NUCLE AR REGULATORY PESE Af4CH (POBf $20405)

NURE G ri A 00$1 AS4[ 55M[NT St uDi " NE L apt"M3D2 CVCl E OF F tCE OF NUCLE AR RLGULATOHV RE St ARCH (POST 80072W 36 05 tiASE D ON 1HE COI.L 4 RE ACit 4 14fD 08' N9Vt VDE R NURE G/tA 0040 DOIL-OF F DPE RIMENTS Wif H THE ElR NL PTUN

?? 19%

F ACILIT Y: ANALY95 AND CODE A55E 5bM(NT OVE A oE W NUH; Gila-Oct ? AN ANAlvaiS Or bE M 5C ALL MOD PC 51S 1 Sit AM UNE I$f Ak TI $1 UblNG 4[t APS /M9D2 pg mqi NUREboA 0053 AN AbSt SGMLNT OF 1RAC P! I tMDD1 US'NG NUREG/ LAM 41' AS5 E SSMENT OF 1RAC4'I 1/ MOD 1 AGAINST AN STHAT W W DL U 10 $ cad MOM Rt 8 4 L M M S ?W INADVERTENT $1E AM LINE ISOLAllON VALVE Cl05UAE IN THE RINGHALS P POWE R PLAN 1 qq[p f

gg,,i AN ASSE S5M(Ni OF 18 AO Pf 1. MODI U5;NG NURI G/iA 004L ASSE 65ML Ni OF hELAPS/ MOD 2 CYCLE 36 04 cTnATHOLvDC 1/10 $cM E MODEL I4 Ftti T[5f 5 AGAINSt THE LOV115A-2 Slur % OPE N TURB0JE LEPASB VALVE NUHE G 't A W% ASSE bWL N1 OF THE SUH-COOLf D BDitING TRAN5:ENT ON SE PT(Mut R 1.1981-MODll USED IN HE LA.% MOD 2 (CYCt.L 30 05, Vt A510N E03)

AGAINST E APf R'ME N T At DA1 A 27

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NRC Contract Sponsor Index (Contractor Reports)

This index lists the NRC organizations that sponsored the coniractor reports listed in this compilation, it is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriato, The sponsor organiza.

tion is followed by the NUREG/CR number and title of the report (s) prepared by that organi-zation. If further information is needed, refer to the main citation by the NUREG/CR number.

(DO Of FICE FOR ANALY$is & EV ALU AT10N OF OPERATION AL DOSON 03 Hi aut A f r_m A rt'L i: Af tDNs (f o%T fed 4 t h NuhE G L A dr27 WG GI td hic CO5T E LT A4^1t L Awa:ts 8 to+

DATA 05 6 G F OR ANALY51$ & [yALU ATVN Of 00[h ATlp4AL D A T A. De GMPN Sims F W UW m by aq DN Sauy Img C A 8 W s N;mLG-(h 02W VO4 F if t D L v hW T [ H % E 510 a A f 40% (D A FdCTO4 NUh( G/CH P300 V1DN12 UCl)45t l I V( N T !4t PO4I (L E Fy li4Il AA$If DATA E4 A EL DI VI L OiV{ NI P41sh AM IDh COMMLAtlON F or M..ee ()t Ew omte ipt F N,AL YE AR W 1 An ur N ft P

DN1hMJTION Di M A.TLhN At R ADQNU.

NUhl G/l 4 2XK) Vit N1 LICE NSI L { V[$4T Mf.POOT R [ $4 NUkt.;s 'C A !611 H?t t

GOMhLATION For Met'i Of Januay 1W2 CL Of DURDENS T O Pkt N AT AL H AD ATION l'O;f S mioom hn 0-m0fviiiktnB EDO Of flCE OF INFORM ATION Rth0VHCES M ANAGEMENT & ARM Nuni RH E 7a ; Olt N10DeNAMc Pogn; A fiON s1UD-[ s ON (POST 84 t t09) cc.N; 0Ai{ CONT AIN(H AL LOrb FOR THL TU6 F DI PDS'1Dhv D!vi5 TON OF COMPUTE R & T E L L COMMUNC A T !ONS LE A N T S N@! b 'L R *.7W NTUNG G A V A?M AND LO % 1(bV CODDD L

POST fWl?")

%ON S TUD!t b 04 C ANDCAf t CONT AiNI R At L OT S I Oh 1HE NUhtu'CR 2%0 V10 POPUL ATION DOSI COVV TME NTS DUL la Tu fhtPosipuy r

RADiOACTNE h[ll ASE 3 I MOM NUCL[ A4 POA( H Pt AN f StilS frJht G ( H $725 PuoGu( SS HE THf DN H?1 PARiff tl SILO IN 19%

II 9 NUnl G 1H 91t ( V AL U Al TONS 08 IVC P4'5M Df 90N DEW 100. OFFICE OF NUCLE AR MATERIAL EATITY & SAFEGUARDS SONS DNtSON OF 5AF t GUARD 5 & in ANwO41 AlivN :POr,1 ti 441 h N@( G Cn 5e t 7 ht is *T ON h[ 5[ AFK H AC1NITil S f DO CAL-NUh[ G 'CH -4%4 V0t R1 SCAN 5 (SHIPPING CA$p. ANAL Yb 9

[NDA4ytAq194 SYSTLM) A MICfEOMPUTE R F. Abf D ANALYSIS Lib 1[ M F OR NJhtG44 %42 G A51 hDlNil 51 A AL AH50RP f CN Of 5H!PhNG CASp. DL'iGN DEVtLW Uw a Manun? To wson la e PLUTON)UM UH AN!UM AND Ni PTUNWM IN f I D AND F ASif D c4drg Pryppm Detorenc p)

ADU( t [s A!)3ONS APPL #C A flCN TO HUM AN%

NuhlU/Cn 4554 V03 n1 SCAMS (5HfPING CA5k ANAL 4 5>S W ISON Or s AF t t y I? Sui H1 sot U t ION (PO5 f w t h Sf SIEMi A MICHOGOVPUTER BASE D ANALYLf 5 SY81( M F On NuhE G'Ch 4551 V2H1P3 ( V AL U A T ON 08 bl t l HE AC QDi Ni H95 QU AN1lf LAllON OF V AJO4 lNPUI gHiPp!NG CASK DISGN PEVTW Um Vmal N Wmp m I AH AMt1E H5 I:4pects' Detemaxm of It% teat Hcw w we impact Anal H And Veritu aton Of impact AnaNn) y M4 dM EDO. Of flCE OF NUCLE AR REGUL AiORY f:E SE ARCH (POST 820405)

NUhl WCN 5L) VC1 S4 51t M ANa;v P5 AND H9 AMi SsVI NT DtilbiON 05 t NSNE IRING (POST B7041T SV Sit M '5 A4A) VI H50N 4 3 Reiemn, Va%at NUHLG'CH 4219 Yv6 N1 HL AVV < 5E C T ION S1 E E L 1[ CHNM OW NuHt G Cn s'iy3 vo/ Sis:[M ANAL ists AND h 9 A55L 5b Ml NT Ph000 AM 5emiannual PrDyess bport f cet 0; tate iM - Marth SYSIE M (S AR A) VE H560N 4 0 Tut:e at 1991 NU61 GiCH E ?47 DHf F C L S hM ATE Of N ADIONUCUDI hell ASI NUHLG CH 46M V13 ENVtRONMENT ALLY A551ST LD CRAct iNG CHARACTER 15 tic 51410 CONT A:NVF NT UND! R 50 vf RE ACCI IN UGHT W ATIH Mt; ACTOPS Sermanttua: Howt Apol Septemte Dr.NT CohniTIONB D'att bewt I cw Comment 1991 NURE G/CH $767 DHI FC tim NG AN Ali bis Of PAh FUE L NN NUhr G/CR SW INStGHTS GA;NF D F fcv AG;NG DESF ARCH F Att unE S D.att nePort I or Comme,t NUREbXH 5t 50 i ETRAPOLATION Or THt J H cuqVE F ca PnE.

NUiq G g n 9 33 V0 iNit GH AT E D RE Li AEqUTy AND nt9 ANAL DICilNG Rf. ACTOH VF SSE t IN1E GR1TY

, % sy$1[M onRAW VtnCOON 4 0 heiment t MaNa!

Divtr 04 OF E,Ett Ms DE SE Ant H ipos 1 wi t; L V A U AT ION OF E4E H A viOR AND T HE H ADi AL NUhlGiCR %74 L

a SHL AR STRE NG1H OF A RilNFORCf D CONCHETE GONT AN NJH( G!CA 5 44 tNST HUUl N T AV ail AbillTY DUR!NG SEVE Al VE NT STHUCTU6f ACCO[NTS FOR A FOiUNG W ATE R hl AC1CH W1TH A MAnn i NUHE G/CH $ 7t2 COMPHIHE N5NE AGING ASSE SWE NT OF C:A CONT A;NMt N' Culi E1RE AtTRS AND HEL A1 B NUhlGCH M1 NrL APE MOD 3 CODE MANU AL US"'s Gwh NU4EG'CR E774 L L ASTIO. PLAST [ CH AA ACT E RV ATION Of A es CAST ST A NLESS BTti L NPE Eli>OW Malt 4:AL Nuht G/CH ! N4 N AlURAL C,hCUtATON CO3dNG !N U S I%ES-NUnf G/CHCb6 A COMI AR@N OF WfIBULL AND (NC) AN ALY-SUR 7E D W A1[ H HEACTOHs S!S Of TR AN5IllON RANGE F RACTUn( TOUGHNf SS DAT A NUHtG CR4' ' OUANTli Af NE f v AL UA'ON Of SJHillL L ANCE NUREG/CH E799 HE VtE W OF HLAC104 PhlSSURL Vf Lbf L ll LT !N1E4v A L S iN^LUD N31[ST C AU$1 D HiSW 9 LVALUAliON REPOHf f OR Y AN* E t HOAE NUCLE AR POW L A NUht G 'CR tC2 IDt Nh5 [ AllON AND AME SWENT OF CON ST ATION D AEC ND 1DS) 1 A mMPt At'D PlLE ASE M AN AGE MI NT LlhAl[G![ 5 F OR A NUHE GiGHM41 VF Rif lC ATION OF NONUNE AR I"P N HE-(mR M AR* DI CONT A8NVE NT SPONSE CALCULATION WoH DAT A FRCM SEISMcC TLSitN3 OF NunEG'CH %% Ot NT r CATION AND E v At u AisON OF Pern rN AN IN PL ANT P! PING SY STE M VF SSE L mE RE ATOL NT M AN AGE MENT STRATEGIS 29

)

Contractor Index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation. Listed below each contractor are the NUREG/CR numbers and titles of their reports, If further information is nooded, refer to the main citation by the NUREG/CR number.

AMtRICAN &OCIETT OF MICHANICAL ENGtNitHf NuhtG ( H4444 i%f HUVtNT 4 M AM riv (NAN 7 M f N AC NUHL 3/GHOW V01 f0SCOAbt D IN(P(CilON - DIif(Oft { NT Of QDi Nf 5 f DH A bOniN3 W A1( H HE AC TUA WitH A MAHP l CON OUlDf LINf S Gtueat Dat 9 ment i A:NylNf A54GONNE NATIONAL LABOHATORf NUHEOfCH-4fC V13 LN/HOWENT ALLY ANSISif D CHACKINu IN h4 5% N AT UH At uf K-Ut Af TON L00t 145 IN U K in S TIGHT W Alf R AI ACT04S Semennom neamt Ara wpn mt+< itm "M ^ AM U M ANM NUHL GiGH %41 yt HiriC ATION O& 994iINt AH FWea Ht 510%[

M O U W IM N WW ^* U'S UI PAH ' Ull M CALCUL A10N WITH DAT A F HOM St rWiC T( S11NG Of AN!N r AllUHL 5 DW1 F4eport f or Rrnwnt PL ANT PihNG $Y$tt M NUht G!CH %42 GAS 1HO!Nf f STINAL ADLORP flGN Of N#l O!CH %D W1 IN1f GR ATI D M L:AM 11Y AND H9 ANM O

$!S SYSil M (WHAL) YlHSON 4 0 ht4ence Mnd PLU10N!UM UHANIUM AND NE PTUN"JM IN f C D AND F AST[D ADULT BkbOONS APPLICATION TO HUMANS HALLIBun1ON NUS t NVIHONMT NT AL CORP BATTELLE HUM AN AFF AIRS RE St A$1CH CENTE RS taVHt GTH 6707 D* 4 8C TIMt40 AN Al ns 01-PWH 5 Ut t hN NUHlG/CH M % IDLNTiF ICATION AND LVALUATION Of PWH 44 F A40HE % Dran Hop *t f w C('wwnt VEMIL $lVEOf ACCIDI N1 MANAG( MI NT STRAT(Glt 5 DAT'isLLE MtMO41AllNSTITUTE' PAClflC NO84THWEST UM N*

A l IN LABORATORY I

M NUHL WCH ?ftSO V10 IOPUt ATION DOSE COM51 f ur N15 DUE TO DADIOACTivl HE LLASE S f ROM NUCLE Af4 POWLR PLANT Sf f[5 IM 19%

UN

1. A E

NUNEGICH f431 R01 CONT R OU flON Ol' MATf hNAL HADtDNU NUHL 'FCR %74 i V AI U AllON 08 h( H AViOH AND THf T4DaAL CLIDL DUHDE NS 10 PHLNAT AL kADI AflON DO5LS intwem Huom.

but Ah 51Hf NGiH Of A Of M OHUf D CONC Hf iL C(>NT ANVE t4i mw,Mtuts NUHLG/CH b799 MEVil W Of HE AC104 PPl%SUHE Vt $$t1 EVAL.

51HUCTUHL UAflON RL PORT f Oh YAN*EE HOWE NUCL[ AH POWL H 51 AlkW JASON ASSOC 1ATIS tY At C NO 1739 NURLG/CH %% IDt N11f ICAllON AND I V ALUAllON Of PWH IN NUHf G/CR 9% IDt tHIFICATON AND I v AL UA10N Of PWRiN Vf Mf L 5[VLHL ACCIDE NT MANACt Mi NT STRAT[ PPE $

V[ 55[ L StVI HE ACCIM Nf M ANAS! MLNT 5f H Aif Gil 5 DHOOkHAVEN NATIONAL LABORATORY L AWRENCE LlytHMORE N ATIONAL LABORATORY NUHf G/CR SA43 INSIGHTS GAINf D f ROM AGING Hf %f ARCH NurG/CH W VM Rt SCANS (SWPPING CAS* AN ALY NS NUHf.GICH 5725 PMN84t SS ht FOHT ON HOT PAH f Ctf STUDtLS WWi A KH% MUM H W D M M W E M f W-NUNEWCM $747 D0f IC E 5itMAIE (A HADONUCLIDL htLL Att SumNG CASK DE StGN HE v:EW Um s Ma%i lo been Fa On-CHARACTEHISTICS INTO CONT AiNurNT (MDt H 5t vth[ Aco.

oudny Pmyam hetemnce)

Dr N1 COND4TIONS Deati Report F or Comment NUHEWCH 6775 OUANilT ATIVE EVALUAllON Or bUHVilLL ANCE NU4E GICH 45',4 V03 DI LCANS (SHPPING CA% AN AL Y DS SYSTE W A UCRCCOMPUlf R BASED ANALYSIS SYSTLM f 04 f( St INTE Hb ALS INCt UDtNG Tf ST(AUSF D hm S NUni G/CH %D? IDENilf ICAllON AND AMr S5VLNT OF CONT AtN bHiPPtNG CASK D( SIGN HEVif W Iheory Ma%ai ste.rl 9 ump in MLN1 ANU H[LE ASE MANAGEME NT SinATTGif S f OR A DWH Impact Analyu And veteuton Of imp wt AwyW lMHK lit CON 1 AINY[ NT NUHE WCH M15 L V ALU A flONS OF 1990 Pf4!sM DE SIGN HE vt MCHIGAN UNIV. OF, ANN AfiDOR. Mi SONS NUnlG/CH M32 IDENN ICAllON AND ASSE 5SMLNT OF CONT AIN CtNit R FOR NUCL EAR WASTt REGULATCRY ANALYSES

^

NUME G/CR M17 HLPORT ON HE!WCH AC1!VITIES i D4 cat EN U^" " A" #

NEW YOHK VNIV. MEDICAL CENTE R. NEW YORK, NY NUREGiCR M42 G AS T ROINT E SitN AL ADSORPTION Of CC'1 TEST COLUMBUS TECHNOLOGIES. INC (TORMERLY CORTEST PL UT ON!UM UR ANtUM AND NL P10NiUM IN f I D AND i A$f f D COLUMDUS. (NC.)

ADULT BADOONS APPUCAf ON TO HUMANS NUHE WCH STOB POlt NTIODYNAVic POL /Rt2 Af TON STUDtES ON CANDIDATE CCA1 AINE R ALLOYS T OR THf Tut F HLPOSITOfW NUHEG/CR 5709 F1T11NG GALV ANiC, AND LONa TE HM CoH403ON OAK RIDGE NATIONAL LABORATOHV STUD 4 5 0N CANDtDA1L CONTAINE R ALLOYS FOR THE TUF F HE-NUREG/CR POOO V U,)N17 t lCE NSE t fy[NT BEPO4T fl(3N COMP:LATION rof Month of Dommm im PO5110RY NUREG/C0 F000 Vit N1 LICEN5f E L Vt NT n! PORT n E R.

D AVID T AYLON Rt SE ARCH CE NTE R COMPuiON Fu mmh Of Ja%at it W NUHf G/CH $774 i LASIC PLASitC CHARACT ER:lAliON OF A CAST NUHEG 'CH 4219 VDe Nt Hl3YY 5LCTiGN St[EL TtCHNOLOG; ST AINLL5s ST([L PiFL [ LBOW M Al[niAL pg g gg p,g gg i G&G 10 AHO, INC.

NUR! G /CR %'*0 EiTR APOL ATION Of TH! J H CUHit FOR PRC NUREG!CH W2a V04 OELO LYSIVL TI O INVE SilGAllONS LOW.

M T hG nf ACTon u SSit INTE GRW L E vil W AS T E DATA BASE DE VE L OPME NT PHOGRAv ron N#t QCR $ H A COW AH" SON OF M $Ut L At.D BUC) AN ALYS6 T ISC AL YE AR 1991 Annel Report NUREG'CR 5303 V01 SYS1EM ANALYS$ AND HM ASSESW!NT Of in ANSITION fMNSE FR ACiuhf TDUGHNE SS DAT A NUHf fr ' n 57W Af vif W Of HL ANOH PHf %UHE Vf 5$0L t V Ai S6il M (SAH A) VEHSON 4 0 Referen'e Ma%M NUHFG 'CR bW VtV $YS1LM AN AL YS'5 AND R Sk ASS [SSMfNT UATION Hf DOHT iOH t ANvE E DOWE NUCLE AR POW ( H ST AlaON ST STL M (SAHA) VL HStON 4 01wel p AEC ND 1DN 31

32 Contractor Index SANDIA NATION AL LADORATORIES TECHNADYNE ENGINEERING CONSULTANTS. INC.

NUREQ1CR 4551 V? RIP 3 E V ALU ATION OF SE41RE ACCIDENT NURE G/CR.4$$1 VtRtP3 E vat uATON OF SEVEHE ACCIDE NT RISKS. QUANTIFICATION C* MAJOR INPUT PARAMETERS I atwts' Deterrtunation Of Structural Response lasues RtSAS OUANTIFtCATION OF MAJOR INPUT PARAMETERS f trerts' betertreation Of Struct#al Respcense inwes BCIFNCE & ENGINEEsHNG ASSOCIATES. INC.

NURLwCR-4627 Nk; GENERIC COST ESilMATES At'stracts Frum TE kNE $$E E. UNIV. OF. N NOK VILLE. TN Generc Studss for Use in Propenng heputatory Irnpact AnaWes NURE G/CR f450 l'ETRAPOLATON OF THE J R CURVE TOR PRE-LnCTING RE ACTOR VESSE L IN1EGRITY.

SCIENCE APPLICATION 6 INTERNATIONAL CORP.(FORMERLY SCilNCE APPLICAftONS.

U.S. NAVAL ACADEMY ANNAPOLit. MD

• tVREGtCR 45$1 V2R t P3. EVALUATION OF SEVERE ACCIDENT NUREG/CR 5774 ELASTCPLASTC CHARACTEHf2ATION Or A CAST RISKS QUANTIFICACON OF MAJOR INPUT PARAMETERS Eur,rts-ST AiNtESS STEEL hPE E'tDOW MATERIAi.

Determnatnn 01 Structual Rurmse issues NUREGrCR $799 REVIE W OF RE ACTOR PRES $URE VESSEL EVAL.

WYLE LABORATORIE$

UATON REPORT FOR YANFEE ROWE NUCLE AR POWER $1 ATON NUREG /CA$762 COMPREHENS!VE AGING ASSE SSMENT Of Cin (Y AEC IC 145)

CUlf DRE AFERS AND RELAYS i

l l

l 1

l 9

international Organization index This index lists, in alphabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation Listed below each country and por.

i If further infor.

. forming organization are tho NUREG/lA numbers and titles of the r reports.

mation is needed, refer to the main citation by the NUREG/lA number.

SWIT2tRLAND CtLOlUM t.AUL SCHLnntn tN9TITUT* *SO THACTfBEL NURCO/iAM51; ASSES & MENT STUDY OF AELAPS/ MOD 2 CYCLE 4:JnEGitAw40 poit.Of [VPL40WNIS Wl?H THE L14 N(PTUN

% 05 BABE D ON THE DOf L 4 REACTOR TAIP OF NOVLMBLR F ACILITY. AN ALY fet$ AND CODE Ai,SL S5ME NT Ovr RVIE W F2,125-Bf PORT.

FINLANf5 UNiitD KINODOM TLCHNICAL RESE ARCH Cf 4THE OF FINLAND CENTHAL ELECTHOf Y GENE RAfiNG GOAhD NUAEG/iAM4L ASSESSMLNT Or h[ LAP 5/ MOD 2 CYCLE 36 D4 NUAEO/1A pose ASSESSMENT Or THE SU0COOtiD BO! LING

-- AGAINST THE LOVilSA 2 STUCKOPE N TUABINE HY. PAS') VALVC MODEL USED IN RELAP$/ MOD 2 (CYCil 36 0k v[ ASION ID*)

3 TRANSfENT ON SLPILMDEA 1,1981.

AG AINST [ RPC AlMt NT At DAT A UNITED KINGDOM ATOMIC ENE AGV AUTHObtTY SPAIN

^

>RI /iA 1

E SL4 1 OF TRAC Pp1/ MOD 1 AGAINS1 AN GTC N BRE AK T ST N REL F6 M D2 0L EN STEAM L t4E ISOLAT60N VALVE CLOSURE IN UN!VE R TY OF GTRAltCLvDf / CENTRAL ELECTRCTY HEM Af CH 1

NUAEC/ LAM 53 AN ARSESSMENT 05-1H AC Pr1/ MOD 1 L15lNG QWEDEN STRATCHCLYDE 1/10 SCALE MODEL RUltL TESTS 2ND STUDSVik [NERGfif kN!K A 0 NURL3/ LAM 41' ASSESSMLNT Or TRACP51/ MOD 1 AGAINST AN ALPORT.

INADVtAT;NT STEAM LINE ISOLATION VALVE CLOSURE IN NUMEG/ TAM 55 AN AS5t S5 MENT Or TRAC-PF1/ MODI USING STHATNGf 'DL 1/10 SCALL MODEL NEFILL Tf STS RINGHALS 2 POWER PLANT.

h a

33

,~

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Licensed Facility index 3

. Index lists the facilities that were the subject of NRC staff or contractor reports. The yg Wity names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number. If further information is needed, refer n the main citation by the NUREG number.

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BIBLIOGRAPHIC DATA SHEET NUREG-0304

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Voi,17 No.1 r, mtE m.) sus mt;

3. DAT E HEPOR T PUOuSHED

Regulatory and Tcchnical Reports (Abstract index Journal) l YEAR MONTH June 1992 Compilation for First Quarter 1992'

( pg og anyy7 uv,,n January-March

6. T YPE C# ik POR T

6. AUTHOR (5)

Reference L PER10p COVERED Onclus ve Dates) i i

January-March 1992 R PEHFOHMNQ OHGWZATON - NWE AND ADDHESS Of two, provice Dmsm, Office or Hegen, U S, Nuclear Hgulatory Commission, and

.. mamno ador ss; n conunciar, provid. nam. and mamna sddressa

. Dhision of Freedom of Information and Publications Senices Office of Administration U.S Nuclear Regulatory Commission

' Washington, DC 20555 O. 6PONSOH8NG OHGANIZATION - NAME AND ADDRESS Pt NRC, type -Same as above*; sf contractor, proveos NHC Devtsson. Off ce or Rega.

U.S. Nuclear Regulatory Commission, and matting address.)

Same as 8, above.-

10. SUPPLEMENI AHy NOTES 11e ADSTRACT (200 words or less)

This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceed-ings of conferences and workshops; as well as international agreement reports. ~~ cntries in this compilation are indexed for access by title and abstract, secondary report number, personal ai -

bject, NkC organization for d facility,

_ staff and international agreements, contractor, international organization, ar.

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13. AVAILASsLITY STATEMENT

12. KEY WORDS/DESCRIPTORS (Elst words or phrases that wit) assist researchers in tar.at6ng t' e. apart.)

Unlimited 14c SECUR:TY CLAS5tFICATION compilation g3,,,,,,,3 abstract inder Unclasstfied (This ReporO Unclassified 15.NUMuEH OFPAGES

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_ - _ _ _ _ -