ML20210R783

Regulatory and Technical Reports (Abstract Index Journal). Compilation for First Quarter 1997,January-March

ML20210R783
Person / Time
Issue date:	06/30/1997
From:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
To:
References
NUREG-0304, NUREG-0304-V22-N01, NUREG-304, NUREG-304-V22-N1, NUDOCS 9709030367
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4 NUREG-0304 Vol. 22, No.1 1

Regulatory and Technical Reports 2

<( Abstract Index Journall s

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Compilation for i

First Quarter 1997 January - March U.S. Nuclear Regulatory Commission l

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l AVAILADILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most unm ? .11 cited in NRC publications will be avaJable from one of the following sources:

1. Ths, NAC F sbtic Document Room, 2120 L Street, NW., Lower Level, Washington, DC

?O555- 7 1

2. The S.porintendcnt vf Documents, U.S. Government Printing Office, P. O. Box 37082, W6shington, DC 20402-9328

3. Ths National Technical Information f ervice, Springfield, VA 22101-0002 Although the listing that follows represents the majority of documents cited in NRC publica.

tions, it is not intended to be exhaustive.

f.eforenced documents available for inspection and copying for a fee from the NRC Public Docuraent Room includo NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensco event reports; vendor rr 3rts and correspondence; Commission papers; and applicant and licent.,ee docu-monts and correspondence.

The f ollowing documents in the NUREG series are ovallable f or purchtco f rom the Government Printing Offico: formal NRC staff and contractor reports, NRC sponsored conference pro-ceedings, internatiorial agreement reports, grantee reports, and NRC booklets ar'd bro-chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula-

• tions, and Nuclear Regulatory Commission Issuances.

Documents availablo from the Nationallochnical Information Service include NUREG series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.

Documt ,vailable from public and special technical libraries include all open literature items, si as books, journal articles, and transactions. Federal Register noticos, Federal and State wisla0n, and congressional reports can usually be obtained from these libraries, Documents such as theses, dissertations, foreign reports and translations, and non NRC con-f erenco proccodings are available for purchase fiom the organization sponsoring the publica-tion cited.

Single copies of NRC draft reports are available free, to the extent ot Supply, upon Written request to the Office of Admir,istration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001, Copios of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library Two White Flint North.11545 Rockville Pike, Rock-villo, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute 1430 Broadway, New York, NY 10018-3308.

NUREG-0304 Vol. 22, No.1 Regulatory and Technical Reports (Abstract Index Journal)

Compilation for First Quarter 1997 -

January - March Date l'ublished: June 1997 M. A. Sheehan, I'mject Manager l'uhlications tiranch Office of Informutlun ami Resourus Maungement U.S. Nuclear Hegulatory Commission Washington, DC 20555-(NNil j,. .. a'..q, t

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CONTENTS Profaco ............... ....... .......... . . . ...... ... ...... ... .. . v Index Tab Main Citations and Abstracts . . . . . . . . . . . . . . . . . . . .. ... . .. . . ....... . 1 o Staff neports e Conferenco Procoodings e Contractor Reports e Grant Reports e International Agroomont Reports Secondary noport Number inoox . . . .. . . .., .. . . . ... .. . ...... ..... 2 Personal Authorindex .. ,,. . ... .. . .. . ... . . . .. . . ... 3 Subject Index . . . . . . . . . .. ..... .. . .. . . . . . .. . . . . 4 NRC Originating organization index (Staff Reports) .. . .. . .. ... .. . . . .. 5 NRC Originating Organization index (intornational A0rcoments) ... ... .. . 6 NRC Contract Sponsor Index (Contractor Reports) , ,. . . . . .. . .. 7 Contractor index . . . . . . . . , . ..., .. . . , ... . ,. . .. .. . . . 8 International Or0anization index . . . . . . . . . , .... .. ... .. . ... .. . .. 9 Licensod Facility lndex . . . ...... .. ..., ,, . . . . .... . . 10 til

PREFACd This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NAC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly ar$d to cumulate it annually. Your comments will be appreciated. Please send them to:

Publications Branch ,

Office of Information Resources Management T 6 E7 U S. Nuclear Ret astory Commission Washington D.C. rJ555-0001 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG XXXX, NU.

REG /CP XXXX, NUREG/CR XXXX, and NUREG/lA XXXX. These precede the following indexes:

Secondary Report Number index Personal Author index Subject index NRC Originating Organization index (Staff Reports)

NRC Originating Ortwnization Index (International Agreements)

NRC Contract Sponsor index (Contractor Reports)

Contractor index International Organization Index Licensed Facility index A detailed explanation ,$f the 6ntries precedes each index.

The bibliographic elements of the main citations are the following:

Statt Report NUREG 0808: MARK ll CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA ANDER.

SON, C. J. Division of Safety Technology. August 1981, 90 pp. 8109140048. 09570:200.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System acces-sion number, (8) the microfiche address (for internal NRC use).

Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABIL-ITY ENGINEERING IN NUCLEAR REGULATION, JANERP, J.S. Argonne National Laboratory. May 1981, 141 pp. 8105280299. ANL-81-3. 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 Document Con-trol System accession number, (8) the report number of the originating organization, (9) the microfiche ad-dress (for NRC internal use),

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Contractor Report NUREG/CR 1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR UGHT WATER  !

1 REACTORS CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT.PR. Sandla Labo-  ;

i ratories. May 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 authors {

or publisher, (5) date report was published (6) number of pages in the report, (7) the NRC Document Con- l trol System accession number, (8) the report number of the originating organization (if given), (9) the micro. l

, fiche address (for NRC intemal use).  !

Grant Report  ;

NUREG/GR 0013: APPUCATIONS OF A NEW MAGNETIC MONITORING TECHNIOUE TO IN SITU EVAL-UATION OF FATIQUE DAMAGE IN FERROUS COMPONENTS. JILES, D.C.; BINER, S.B.; GOVINDARAJU, 1 M.; et al. Iowa State Univ., Ames, IA. June 1994. 41 pp. 9407250286. 80328:195. [

d Where the entries are(1) ieport number, (2) report title. (3) report authors, (4) organizational unit of authors  ;

j_

or publisher, (5) date report was published. (6) number of pages in the report, (7) the NRC Document Con-trol System accession number, (8) the report number of the originating organization (if given), (9) the micro- [

fiche address (for NRC intemal use).  ;

Intemational Agreement Report i

NUREG/lA-0001: ASSESSMENT OF TRAC PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA. NEUMANN, U. Kraftweek Union. August 1986. 223 pp. 8608270424, 37659:138. ,

l Where the entries are(1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages inthe report. (7) the NRC Document Control System acces-sion number, (8) the report number of the originating organization (if given), and (9)the microfiche address '

(for NRC internal use).

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

^

ADD addendum

-APP appendix ,

DRFT draft ERR errata l N number R revision S supplement

-V volume i

Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Government Printing Office (GPO) or from the National TechnicalInformation Service, Springfield, Virginia 22161. To purchase docu- i ments from the GPO, send a check or money order, payable to the Supenntendent of Documents, to the following address: _

l Superintendent of Documents i U.S. Government Printing Office Post Office Box 37082 Washington, DC 20013 7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge card ,

by calling the GPO on (202) 512 2249 or (202) 512 2171. Non U.S. customers must make payment in ad-vance either by Intemational Postal Money Order, payable 13 the Superintendent of Documents, or by draft ,

on a United States or Canadian bank, payable to the Superintendent of Documents.

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NRC Report Codes The NUREG designation, NUREG XXXX, indicates that the document is a formal NRC staff-generated re-port. Contractor prepared formal NRC reports carry the report code NUREG/CR XXXX. This type of identifi-cation 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 re-ported.

In addrtion to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC sponsored conference pro-ceedings NUREG/GR is used for NRC grant reports, and NUREG/lA is used for international agreement reports.

l All these report codes are controlled and assigned by the staff of the Publications Branch of the N9C Office of Information Resources Management.

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Main Citations and Abstracts ,

The report listin s in this compilation are arranged by report number, where NUREG XXXX is an NRC staff-o inated report, NUREG/CP XXXX is an NRC sponsored conference report, NUREG/CR XX is an NRC contractor 9repared report, and NUREG/lA XXXX is an inter-national agreement re) ort. The bibliographic information (see Preface for details) is followed by a brief abstract of tais report, NUMEG-0040 V30 NOS: LICENSEE CONTRACTOR AND NUREG 0713 Vl?: OCCUPATIONAL RADIATION EXPOSURE AT VENDOR INSPECTION STATUS REPORT, Quarterty COMMERICAL NUCLEAR POWER REACTORS AND OTHER Report.Juiy September 1996(WNte Book)

• Offee of Nuclear FACILfTIES 1995. Twenty-Eighth Annual Report. THOMAS M.L Reactor Regulation (Post 941001). January 1997. 147pp. Otvision of Regulatory Appleatons (Post 941217).

9702060133. 91659 001. HAGEMEYER,D. Science Applications international Corp. (for.

TNs penodcal covers the results of inspectons periormed by merly Science Apphcatons, Inc). January 1997. 300pp, the NRC's Special Inspecten Branch, Vendor inspecton Seo- 9702190015. 91803:001, ter. that have been detributed to the lnspected organizatinns TNs report summartres the occupatonal exposure date that during the penod from Ju'y through September 1996. are maintained in the U.S. Nuclear Regulatory Comfrussion's Radat6on Exposure Informatkm and Reporting System (REIRS).

wuREG4040 V30 N04: LICENSEE CONTRACTOR AND The bulk of the information contained in the report was com-VENDOR INSPECTION STATUS REPORT. Quarterty Report,0ctober-Oecember 1996.(WNte Book) ' Offee of Nucle. pued from the 1995 annual reports subrWtted by the classes of cr Reactor Regulaton (Post 941001). March 1997,154pp. NRC heensees subject to the reporting requ6rements of 10 CFR 9703200250. 92191:001, 20.2206. Annual reports for 1995 were received from a total of TNs per6odical Covers the results of inspectons performed by 294 NRC Iconsees, of wNch 109 were operators of nuclear the NRC's Special inspecton Branch, Vendor inspecton 600 Poww reactors in commercial opwahon. Comp #atons of the &

tion, that have been detrtbuted to the inspected organizatons ports subrWtted by the 294 heensees indicated that 142,518 in-during the perlod from October December 1996. dMduals were monitored. 76,822 of whom received a measura-ble dose. The collecttve dose incurred by these indMduals was NUMEG 0304 V21 NO3: REGULATORY AND TECHNICAL RE* 24,536 personcSV (person-rom) wNch represents a 1% de-PORTS (ABSTRACT INDEX JOURNAL). Comp 6lation For TNrd crease from the 1994 value. The number of workers receMng a Quarter 1996. July-September.

• Offee of Informaton Resources measurable dose also decreased, resolung in the average Management (Post 890205L February 1997. dipp. 9703100239. measurable dose of 0.32 cSv (rom) for 1995. The average 9202 m measurable done is dehned to be the total collectNo dose divid.

TNs joumal inckxies all formal reports in the NUREG senes ed by the number of workers receMng a moteurable done. The prepared by the NRC staff and contractors; proceedings of om figures have been adfusted to account for transient reactor forences and workshops; as well as intomatonal agreement re- workers. In 1995, the annual collective dose per reactor for light ports The entries in this compliation are indexed for access by water reactor heensees was 199 person-cSv (person-rom). TNs title and abstract, secondary report number, personal author' is the same value that was reported for 1994. The annual cob subject, NRC organtraton for staff and intomatonal agree. locM dose per reach b bonin0 water roams was 256 monts, contractor, internatonal organization, and hcensed facHL gy' person cSv (person-rom) and, for pressurtrod water reactors it was 170 person-cSv (person-rom). Analyses of transient worker NUMEG4640 V10 N11: TITLE LIST OF DOCUMENTS MADE data indicated that 17,153 indMduals completed work assign-PUBLICLY AVAILABLE. November 1 30, 1996.

• Offee of Infor- monts at two or more hconsees during the ir@%g year, The motion Resnurces Manegement (Post 890205). January 1997. dose destributons are adjusted each year to account for the du-315pp. 9702070195. 91668.001. phcate reporting of transient workers by multiple hconsees. In TNs document is a montNy publication containing descrip- 1995, the average measurable dose calculated from reported tions of informaton received and generated by the U.S. Nuclear data was 0.26 CSv (rem). The corrected dose $stribubon resutt<

Regulatory Commission (NRC) TNs informahon includes (1) ed in an average measurable dose of 0.32 cSv (rem).

docketed motorial associated with cMI6an nuclear power plants and other uses of ra&oactNo mater 6als, and (2) nondocketed NUREG4750 V44101: INDEXES TO NUCLEAR REGULATORY material recorved and generated by NRC pertinent to its role as COMMISSION ISSUANCES. July. September 1996.

• Offee of a regulatnry agency The follow 6ng indones are included: Per. Informaton Resources Management (Post 890205). January monal Author, Corporate Source, Report Number, and Cross 1997,2tpp. 97011001W91456.300J Refwence of Encionures to Principal Documents. Digests and indexes for losuances of the Commission, the Atomic Safety and Licensing Board Panel, the Administratrve NUREG4640 Vit N12: TITLE UST OF DOCUMENTS MADE Law Judges, the Directors Decisions, and the Decisions on Pe-PUBLICLY AVAILABLE. December 1 31, 1996.

• Orree of infor.

motion Resources Management (Post 890205). March 1997, truons for Rulemaldng are presented.

NUREG4750 V44 N06: NUCLEAR REGULATORY COMMISSION N E 45' .N stract. ISSUANCES FOR NOVEMBER 1996. Pages 229 314.

• Offee NUREG4640 Vit N01: TITLE UST OF DOCUMENTS MADE of inforrnaton Resources Management (Post 890205). January PUBLICLY AVAILABLE January 1 31, 1997,

• Office of infor. 1997. 95pp. 9703030170. 91940.135.

meten Resouces Management (Post 890205). March 1997. Legal lasuances of the Commission, the Atome Safety and Lk 325pp. 9704170086. 92517:001. censing Board Panel, the AdmirwstratNo Law Judges, and NRC See NUREO 0540,V18 N11 abstract Program Offices are presented.

1

2 Main Citations and Abstracts l l

NUREG 0700 V44 N06: NUCLEAR REGULATORY COMMISSION NUREG 1278 V12: OPERATING EXPERIENCE FEEDBACK ISSUANCES FOR DECEMBER 1996. Pages 315 432.

• Offee REPORT. Assessment Of Spent Fuel Coohng IBARRA.J.G.;

of informahon Resources Management (Post 890205). February JONES.W.R.: LANIK,G F.: et al. Deveson of Safety Programs i 1997,123m 9703170243. 92126 222. (Poet 870413). February 1997. 46pp, 9703170237. 9213t:199.

See NUREG4750 V44,N05 abstract. This report is an assessment of the likehhood and conse-

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NUMEG 0760 V48 N01: NUCLEAR REGULATORY COMMISSION ** ^ 9'"# E'"*" **'**' 'P'"' P"'

ISSUANCES FOR JANUARY 1997. Pages 1-47.

• Offee of in- configuration is developed, and a generic toiling water reactor formaton Resources Management (Post 890205). March 1997. spent bel pwl configwaton 4 W. Ovw twWve years of '

$3pp. 9704040210. 92330 268 operatonal data 2 mwwod and assesed Sk sne viens wwe See NUREG4750,V44.N05 abstract. corducted to gather specife hformaton on spent fuel pool physcal Configuraton, Icontes practces, and icensee proco-NUMEG 0837 Vit NOS: NRC TLD DIRECT RADIATION MONI. dures. The reguistons on opent fuel poo!s were reviewed, inde.

TORING NETWORK. Progress Report July September 1996, STRUCKMEYER.R. Regoort 1 (Post 820201). January 1997, pendent engneenng assesarrents on the spent fuel pool 228pp 9702060125. 91655 001. systwn were performed on the electncal system, instrumente-ton, heat loads, ard radiaton. An assessment on the risk of Thes report provides the status and results of the NRC Thor, I motuminescent Dosameter (TLD) Direct Radiaton Monitoring loss of spent fuel coolog was pwformed Tre overall conclu-Networtu ft presents the radat.an levels measured in the vicWty sions are that the typcal plant may need improvements h spent of NRC Icensed factittes throughout the country for the third fuel pool hatrumentaton, operator procedures and trahing, ard quarter of 1996. configurshon controt NUREG 0837 Vit N64: NRC TLD DIRECT RADIATION MONI. NUMEG 1492: REGJLATORY ANALYSIS ON CRITERIA FOR TORING NETWORK. Progress Report. October December 1996. THE RELEASE OF PATIENTS ADMINIST5 RED RADIOACTIVE STRUCKMEYER.R Regon 1 (Post 820201). March 1997. MATERIALFinal Report. SCHNEIDER.S.; MCGUIRE.SA Dtvi-322pp. 9704170167. 92513:001, sion of Regulatory Apphcatons (Post 941217). February 1997.

TNs report prov6 des the status and results of the NRC Thor- 79pp. 9703200259. 92191:156.

moluminescent Dosimeter (TLD) Direct Radehon Mondoring The regulatory analysis was developed to respond to three Network, it presents the radiaton levels measured in the v6cWty petthons for rulemaking to amend 10 CFR Parts 20 and 35 re-of NRC 16 censed facihtes throughout the country for the fourth garding release of patents admWetered radcactNe matertal, quarter of 1996. The petitions requested revision of these regulabons to remove the amtsguity that existed between the 1-mSV (0.1 rem) total of- j NUMEG 00M Vil N02: NRC REGULATORY factNo dose equNelent (TEDE) pubic dose hmit in Part 20 '

AGENDASemlannual ReportJuly-December 1996.

• Ru'es & adopted in 1991, and the actvity based release hmit in 10 CFN R B h (Post 920323). March 1997. 58pp. 35.75 that, in some instances, would permit release of indtvid-The NRC Regulatory ' Agenda is a comptation of all rules on uals b exceu of N cunent @ ese he he ahwna-Me for tes luton of N petdone wwe waluated Undw Ahw-wNch the NRC has recentty completed action, or has proposed natNo 1. NRC would amend its patient release criteria in 10 action, or is considering acton, and all petitions for rulemaking CFR 35.75 to match the annual pubhc dose hmit in Part 20 of 1 which have been receNed by the Comm6ssion and are pendng I aM Agenda is @ mSv (0.1 rem) TEDE. Ahemauve 2 would maintain the status '

quo of us6ng the activtty based release crtteria currently found in 10 CFFt 35.75. Under Attomative 3. the NRC would revise the release criteria in to CFR 35.75 to spectfy a dose hmet of 5 mSv NUMEG 1031 INT R00: OPERATOR LICENSING EXAMINATION (0.5 rem) TEDE. The evaluaton demonstrates that adoption of STANDARDS FOR POWER FLEACTORS. ' Offee of Nuclear Reactor Regulaton (Post 941001). January 1997. 460pp. Attemative 1 would be considerably more expensNe to ths 9703050343. 91953 001, public compared to Altemattve 2 (the status quo), primarily due <

NUREG-1021, " Operator Licensing Examination Standards to increased health care costs associated with more patents re- I for Power Reactors." establishes the pohcies, proot.jures, and ma6ning in the hospital than under the current activity. based re-practces for exarNning iconsees and appbcants for reactor op. quirements. The evaluaton also demonstrates that adoption of orator and senior reac*.or operator iconses at power reactor fa- the 5-mSv (0.5-rom) dose hmit under Altemative 3 would result cihtes pursuant to Title 10. Part 55, of the Code of Federal in a Ngher not value to the pubHc compared to Altemative 2 Regulabotts (10 CFR Pwt 55). The examinaton standards are (the status quo), pnmartly due to lower health care costs and intended to assist NRC exameners and facihty hconsees to the increased psychologmal benefits to patents and their farre-better understand the processes associated with What and re- l*s by permitting eerber release from the hospital. Based on quahfication examinations. The standards also ensure the equi. tNo anatyees, the decis6on was made that adopton of the 5-mSv table and consistent admWetrabon of examenehone for an appli. (0.5 rem) TEDE limit 's consistent with the provisions in 10 CFR cants. The standards are for guidance purposes and are not a 20.1301(c). and the recommendatons of the Intemational Com-subetitute for the operator heensing regulatons (i.e.,10 CFR misson on Radiological Protecton that an individual be allowed Part 55), and they are aut4ect to revoion or other changes in to receive annual doses up to 5 mSv (0.5 rem) TEDE under cor-intomat operator iconsing poney TNs interim revison permsts tain circumstances. Further, it no longer restricts pabent telease facihty licensees to prepare their W0al operator hcensing exami- to a specifc actNtty, and therefore, permits release of patents nations on a voluntary bases pending an amendment to 10 CFR with actNthes that are greater than c,rrently allowed. The pri-Part 55 that win require facihty preparahon. The NRC Intends to mary benefit is in reduced hosprtal stays that prov6de emotonal sol 6 cit comments on tNa revision during the rulemaking process benefits to pabents and their families, and result in lower heetth and to issue a final Revisson 8 in conjuncton with the final rule, care costs.

NUREG 1100 Via: BUDGET ESTIMATES.Flecal Year 1998.

• Di- NUREG 1800: FINAL ENVIRONMENTAL IMPACT STATEMENT vision of Budget & Analysis (Post 890205). February 1997. TO CONSTRUCT AND OPERATE THE CROWNPOINT URANI-1a8pp 9702190053. 91802:045. UM SOLUTION MINING PROJECT, CROWNPOINT, NEW 1Ns report contains the focal year tWet justificaton to Con. MEXICO. Docket No. 40-8968.(Hydro Resources, Inc.)

• DNtsson gress. The txadget provides eshmates for salaries and expenses of Waste Management (NMSS 940403). February 1997.432pp.

and for the Orfice of the inspector General for flacal year 1996, 9703200270. BLM NM010-93 02. 92192:001.

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Main Citations and Abstracts 3 TNs Fsnal Erwwonmental impact Statement (FEIS) addresses 6mprovement should be sont to the Director, Spent Fuel Protect 6ssuing a comtdned source and lie (?) bypoduct matenal b- Offee, U S. Nuclear RegJatory Commstaon, DC 20L55 0001, cente and rmnerals operahng leases for Federal and Irdian lands to Hydro Resources, tre. (MRI) TNs action would auttor. NUREG 1546: EVALUATION CRITERIA FOR COMMUNICA tre the company to conduct h estu leach utan#vm frw.ing in TIONS.RELATED CORRECTlvE ACT60N PMNS.

• Orfce of McK6niey County, New Mexico Such rmrung would involve drili- Nuclear Reactor Regulation (Post 941001).

• Divalon of Sys-6ng wells to the ore tsodes, then rectoulahng Ground water forti. tems Techrology (Post 941217). February 1997, espp, f od with d$ sotted orygon ard sodium tacartsonate to mobihre 9703100227. 92020.240. .

uraruum rrmerals found 6n the rock. Uran 6um would then be re. TNs document provdes guidance and critena for U S. Nucle-moved from the aqueous marun0 solutons using 60n exchange at Regulatory Commission (NRC) personnel to use in evaluahng technology in processen0 plants located in liveo separate corrective acton plans for nuclear power plant communicatons.

pro}ect areas A central plant would provKle dry ig and packag. The document begins by descritmng the purpose, scope, and ing equipment for yellow cake producton for the entre project. appicability of the evaluaton critena. Nort, it presents back-The FEIS was prepared ty a hint interagency review group, in- ground informaton concerning the commurwcations process, ciud6n0 tre U.S. Nuclear Regulatory Commisson (NRC), the root causes of commutucation errors, and development and im-U S. Bureau of Land Management (DLM) and the U S. Bureau plementation of nirrective actons. The document then defines of Indian Affairs (DIA). Th a FEIS desenbes the staffs analyses spectic enteria for evaluat ng the effectiveness of the corrective concern 6ng the evaluebon of; (1) the purpose of and need for acton plan, interview protocols, and an observaten protocol re-the proposed action, (2) altomattves to the proposed acton; (3) lated to commun6 cation processes This document is intended the onytronmental resources that could be affected by the pro- only as guidance. It is not intended to have the effect of a regu-posed acton and afternatives; (4) the potential env6ronmental laton, and it does tot estabhsh any binding requirements or in-consequences of the proposed action and attomatrves; and (5) torpretabons of NRC regulatons.

the econome costs and benefits assocAated with the proposed acton. The evaluation to based on a comprehensive review of NUREG-1682 DRFT FC: STANDARD REVIEW PLAN FOR APPLl-HRrs laconse appicatson, envirorvnental reports, related submrt. CATIONS FOR LICENSES TO DISTRIBUTE DYPRODUCT MA-tals, irviependent information sources, and wntten and oral TERIAL TO PERSONS EXEMPT FROM THE REOllREMENTS comments recetved on the Draft Environmental impact State. FOR AN NRC LICENSE.10CFR Parts 30.14.30.16, rnent On the basis of its independent review, the staff con- 30 10,30.18.30.19 & 30 20 CAMPER,L; HICH,T.: GREENE,S.

ciudes that the potential a6gnificant 6mpacts of the proposed Divis6on of industnal & Medcal Nuclear Safety (Post 870729).

protect can be mategsted, and that HRt should be issued a com- January 1997,82pp. 9702190058. 91802.274.

tuned source and 11e(2) byproduct material hcense from NRC, Exemphons from the requirements for an NRC leense to per-sod rnenerals operating leases from DLM and DIA. sons who rece6ve, possess, use, transfer, own, or acquire by-poduct matenal 6n esempt osmon pmducts are provded in NUREO 1632: FINAL TECHNICAL EVALUATION REPORf FOR 10 CFR Part 30, Rules of General Applcebility to Domesuc Li-THE PROPOSED REVISED RECLAMATION PLAN FOR THE censing of Dyproduct Material. Exempt distributon products in-ATLAS CORPORATION MOAD MILLSource Matenal License ebde tilcon chips, electron tubes, resins, check sources, Dun-No SUA.917. Docket No. 40-3453 (Atlas Corporshon)

FLIEGELM.: DRUMMETT.E.: IDRAHIM,A.; et al. Divis6on of s6ghts, and smoke detectors and are generally distributed by persons who have a specWic leense from N Conunisson a+

Waste Management (NMSS 940403) March 1997. 200pp.

thonnng such distobubon to persons exempt from the require-9704100173. 92418 016.

TNs final Technical Evaluahon Report (TER) summarties the rnents for an NRC hcense. TNs document provides assistance U S. Nuclear Regulatory Commissaon staff's review of Atlas Cor- to apphcants and heensees 6n preparing Icense appleatons poraton's proposed reclamaton plan for its uranium mill tailings and describes the methods acceptable to NRC Icense rev6ew-pile near Moab, Utah. The proposed reclamaton would ahow ers in imp >menung the regulatons and m technwee used by Abas to (1) reclaim the talhngs plie for permanent disposal and the mywwers in evaluating the appl 6catsons to determine if the longterm custodial care by a govemment agency in its current proposed exempt distributon activity is acceptable for Icensing locahon on the Moab stie, (2) papere the alte for closure, and purposes. The gudance contained herein does not represent (3) rehnquish responsibehty of the atte after having its fiRC li new or proposed regulatory requirements, and icensees will not conse term 6natud. The NRC staff concludes that, subject to b. be inspected against any portion of it. In SXJde:e with NDC conse corxlitons identified in the TER, the proposed recla q usage, the word "should" is used when discussing or referenc-ton plan rneets the requirements identrfied in NRC regulatons, ing NRC regulatons. Additionally, regulatory comphance wtth all whech appear primarily in 10 CFR Part 40. *PP cable regutations is not assured by Icensees who adopt any porton of, or apply the principles described in, tNs guid-NUREG t&36: STANDARD REVIEW PLAN FOR DRY SPENT ance.

FUEL OTORAGE SYSTEMS. Final Report.

• Offee of Nuclear Maternal Safety & Safeguards. January 1997, 179pp- NUREG 1571: INFORMATION HANDBOOK ON INDEPENDENT 9703130386. 92107:104. SPENT FUEL STORAGE INSTALLATIONS. RADDATZ,M G.;

The Standard Review Plan (SRP) tor Dry Cask Storage Sys- WATERS.M D. Office of Nuclear Material Safety & Safeguards.

tems provides guidance to the Nuclear Regulatory Commisson December 1998.140pp. 9703030211,91940.001.

staff 6n the Spent Fuel Profoct Office for performing safety re- in tNs 6nformaton handbooA the staff of the U.S. Nuclear views of dry Cahk storage systems The SRP is intended to Regulatory Comrnission describes (1) background informaton ensure the quahty and undomuty of the staff reviews and regarding the hcensing Nstory of 6ndependent spent fuel storage present a basis for the review scope and requirements. Part 72, installatons (ISFSis), (2) a discusson of the iconsing process, Subpart D generally specifies the informaton needed in a b- 3) a desenpton of all currentty approved or certified models of censo appicahon for the independent storage of spent nuclear dry cask storage systems (DCSSs), and (4) a descripton of fuel and Ngh fevel radioacttvo waste. Regulatory Gu6de 3 61 sites currently storing spent fuel 6n an ISFSI. Storage of spent

" Standard Format and Content for a Topecal Safety Analysis fuel al ISFSit must t e in accordance with the provtsions of 10 Report for a Spent Fuul Dry 6torage Cask" contains an outhne CFR PART 72. The staff has provided tNs handbook for infor-of the specife informaton required by the staff. The SRP is di- mation purposes only. The accuracy of any informaton herein is vided into 14 sections wNch reflect the standard appleaton not guaranteed. For venfcaton or for more details, the reader format Regulatory requirements, staff position, industry codes should refor to the respective docket files for each DCSS and and standards, acceptance criteria, and other informaton are ISFSI site. The informaton in this handbook is current as of docussed Ccmments, errors or omissons, and suggestons for September 1.1998,

4 Main Citations and Abstracts NUREG-1674 DRFT FC: STANDARD REVIEW PLAN ON may deffor from those that appeared H the final program of the ANTITRUST. Draft Hoport For Commerrt LAMBE,W.M.: meeting.

DAVIS.M J Offee of Nuclear Reactor Regulaton (Post 941001).  ;

i January 1907,31pp. 9702190059 91604.328. NUPEG/CP0187 V02: PROCEEDINGS OF THE TWENTY.

i The Nuclear Regulatory Cominession 6s issuing tNs draft FOURTH WATER REACTOR SAFETY INFORMATION Standard Review Plan to desente the procedure used to imple. MEETING Reactor Pressure Vessel Embnttlement Ard Thermal ment the entrtrust review and enforcement prescribed in Soc. Anreahng Reactor vessel Lower Head integrtty And Evaluaton tons 10$ ard ib6 of the Atomic Energy Act of 1954, as amend. And Protecton of Steam Generator tube.... MONTELEONE,S.

ed. This draft SRP reflects current regulatons and poley, and Brookhaven Nrtonal Laboratory. February 1997. 444pp.

9703120276. 92075:001, i will be updated to reflect changes in NRC regulations.

See NUREG/CP 0167,V01 abstract.

NUREG 1677 DRFT FC: STANDARD REVIEW pun ON POWER RF>CTOR LICENSEE FINANCtAL QUALIFICATIONS AND DE. NUREQ/CP 0167 V03: PROCEEDINGS OF THE TWENTY.

COMMISSIONING FUNDING ASSURANCE Draft Report For FOURTH WATER REACTOR SAFETY INFORMATION Co nment WOOD,R S Offee of Nuclear Reactor Regulation MEETING.PRA And HRA, And Probatdlistic Seism 6e Harard As- ,

(Post 941001) January 1997, 20pp. 9702190062. 91009 334. sessment And Seismic Siting Crtterta MONTELEONE,S. Brook.  !

haven Natonal Laboratory. February 1997,160pp.9703120205. j The Nuclear Regulatory Comrwssion is lasuing this draft I Standard Review (SRP) to d6 scribe the process it uses to 92076.06 f.

rev6ew the fmancial oushfcatons ard methods of providing de. See NUREG/CP-0167,V01 abstract.

commissioning furding assurance required of power reactor li-consees. This draft SRP reflects current regulations and policy, NUMEG/CR 4219 Vit N2: HEAVY.SECTION STEEL TECHNOL. l OGY PROGRAM Serrmannual Progress Report For April 1995 ard will be updated to reflect changes in NRC regulations.

Through September 1995 PENNELL,W.E. Oak Rdge Nabonal NUREQ/CP 0164: PROCEEDINGS OF THE CNRA/CSNI WORK. Laboratory. January 1997, 9Bpp. 9702070204. ORNL/TM 9593.

91667:001, SHOP ON STEAM GENERATOR TUDE INTEGRITY IN NUCLE.

AR POWER PLANTS. DIERCKS,DR Argonne Nateonal Labore- The Heavy Section Steel Technology (HSST) Program is con-tory. Fetruary 1997, 625pp. 9703100272. ANL 96/14, ducted for the Nuclear Regulatory Commast#on (NRC) by Oak 92026 001, Rdge Natonal Laboratory (ORNL). The program's focus is on An intomatonal Warkshop on Steam Generator Tube lntegrity the development and val 6daten of technology for the assess.

in Nuclear Power Plants, sponsored by the Committee on Nw ment of fracture-prevent 60n margins in commeretal nuclear reac.

clear Augulatory Actrvities (CNRA) and the Comrruttee on the lor vessels. The HSST program is orgardred in seven tasks: (1)

Safety of Nuclear Installatons (CSNI) of the OECD.NEA, was program management, (2) constraint effects anahtical develop- ,

held at Oak Drook (suburtaan Ch6cago), Illinois, on October 30- ment and vahdaton, (3) evaluation of cladding effects (4) duc. I Novemt* 2,1995. The USNRC Offee of Nuclear Regulatory tile.to cleavage fracture-mode convers60n, (5) fracture anatysis Research served as host. The objecttve of the workshop was to mettods development and appl 6caton, (6) material property )

provde a working forum for the exchange of information by con. data and test methods, and (7) integration of resofts. The pro- ,

tributmg experts on current issues related to PWR steam gener. Gram tasks have been structured to place emphasis on resolw I stor tube integrity. One hundred persons from 15 countnes at. ton of fracture mechanies issues with near term feennhg e60-tended the workshop, including 36 from regulatory and nuclear ruficance. Resources to execute the research tasks are drawn policy agencses, 28 from research ard development laborato- from ORNL with outentract support from universitses, and nes,18 from nuclear vendors and consutting firms, and 18 from other research laboratodos. Close contact is ma6ntained with electncal utilities The workshop opened with a plenary session; the sister Heavy Sectnn Steel trradiaton (HSSI) Program at the first part of the session covered intemetsonal steam genera- ORNL and with related research programa both in the United int regulatory practices and 6ssues, featuring speakers from reg- States and abroad. This < eport provides an overv6ew of principal ulatory bodios in Belgium, France, Japan, Spa 6n, and the Urvted developments in each of the seven program tasks from April States. In Part 2 of the plenary session, comprehensive techn6- 1995 through September 1995.

cal ovenhows on steam generator tttwng drvyedawi, Mepan.

tuis, and 6ntagoty were presented by authorities in these fields NuNiEG/C44400 V04: DATA DASE ON DOSE REDUCTION from the Urvted States, France, and Delgium. Parallel working PROJECTS FOR NUCLEAR POWER PLANTS. KHAN T.A.1 seasons on the second and third days of the workshop then XIE J.W. Brookhaven Natonal lateratory. January f 697,167pp.

developed firdings and recommendatens in the areas of (t) 97020601fk8. DNL NUREG 51934. 91659:149.

TNs is the sixth volume in a sortes of reports that provide in-tutang degradaten, (2) tutung inspecton, (3) tutnng integrity, (4) formation on dose reductson research and health physics tech-preventattve and corrective measures, and (5) operatonal as.

pects and nok analysis. On the final day of the workshop, the nology for nuclear power plants. The information is taken from two of several databases maintained by BrooAhaven Natonal working. season factistators presented summanes of their sea.

sions to the workshop attendees. Laboratory's ALARA Center for the U.S. Nuclear Regulatory Commissert The research secten of the report covers dose re-NUREQ/CP.0157 V01: PROCEEDINGS OF THE TWENTY. ducton projects that are in the experimental or development FOURTH WATER REACTOR SAFETY INFORMATION phase. It includes topics such as need for cost-effectrve mess.

MEEllNG Plenary Sess6on, High Durnup Fuel, Containment And ures to control radiation fields, the h6ghly effective full-system Structural Aging MONTELEONE,S. Brookhaven National Labo- decontarrwnstion, progress in addressing the increase in radb retory. January 1997,357pp 9703120266. 92077:003. atson fields upon swttching from normal water chemistry to hy.

This three volume report contains papers presented at the drogen water chemistry in DWRs, addmon of dep6eted rinc to Twenty-Fourth Water Reactor Safety Informaton Meeting held reduce rad 6aton fields, and cobalt free wear-resistant alloys, at the Bethesda Marrett Hotol, Bethesda, Marytand. October The section on hearth phys!cs technology discusses dose re-2123,199tl The papers are printed in the order of their pres- ducten efforts that are in place or in the process of being im-entation in each session and desonbe progress and resutts of plemented at nuclear power plants. A total of 67 new or updat-programs in nuclear safety research conducted 6n this country ed projects are described The appendix provides a complete and abroad. Foreign participation in the meeting included heting of all the matenal in this area, including that from previ.

papers presented by researchers from Finland, France, Japan, ous reports The material is available through a fax machine Norway, Russia and the Untted Kingrlom The tmes of the from our ACEFAX on bne s/ system. The procedure for access-papers and the names of the authors have been updated and ing ACEFAX is also described.

Malr. Citations Old Abstracts 6 NUMEQ/CR4181 RO1: A PILOT APPLICATON OF RISK IN. a partcular plant of interest The tredels used in BLOCKAGE FORMED METHODS TO ESTABLISH INSERVICE INSPEC- 2.6 and thew vahraton are presented in t% accompanying TON PHIORITIES f OR NUCLEAR COMPONENTS AT SURRY NUREG/CF14371. The BLOCKAGE models were deogned to UNIT 1 NUCLEAR POWER STATION VO.T.V.: PHAN,H.K.; be paramenc in 1sture, allowing the user f6exitality to esamine OORE,0 F.; et et Battel 6e Memonal Institute, Pamfc Northwest the impact of esveral modehng estumptons and to conduct Laboratory. Fettuary 1997, 74pp. 9703100220. PNNL 9020. senutevity analyses. As a result, BLOCKAGE 2.6 retutta are 92027.244. known to be very sonstttvo to the user provided input it 6s As part of the NoridestrucVve Evaluaton Rehatdhty Program therefore stroVy recommended that users become thoroughly sponsored by the U S. Nuclear Regulatory Commission, the Pa- farruhat with BLOCKAGE models and thev $6mitatons as de-cerc Northwest Notonal Latoratory has developed nak informed scribed in NUREG/CR4224.

approaches for interv6ce inspecton plans of nuclear power plants TNs method uses prot >ablisate nok assessment (PRA) NUREQ/CR4371: BLOCKAGE 2.6 REFERENCE MANUAL reedte to Mentity and poortttre the most nok.important compo. SHAFFER.C.J : BRIDEAU,J.; et al. Science & Engineenng Asso-rients for inspectort The Sorry Nuclear Power Staten Unit 1 cistes, Inc. BERNAHLW. Software Edge, Ire... December 1996 was setected for pilot appicaton of tNa rnethodology. TNs 161pp. 9702060227, SEA 90-3104 A 4. 91664:118.

report, wtdch incorporates more recent plant spectic informa. The BLOCKAGE 2.6 code was developed by the United tson and improved risk mformed methodology and tools, is Revl. States Nuclear Regulatory Commesson (NRC) as a tool to son 1 of the earher report (NUREG/CR4i81) The methodolo. evaluate Icensee complance regarding the design of suction gy discussed in the ongenal report is no longer current and a strainers for emergency core coohng system (ECCS) pumps in preferred rnettodology to presented in ttus Revision. TNs report, bolhng water reactors (BWR) as requwed by NRC Bulletin 9643, NUREG/CR4181, Rev.1, therefore supersedes the earlier " Potential Plugging of Emergency Core Coohng Sueton Strain-NUREG/CR4181 pubhahed in August 1994. The spectfc syt- ers by Detris in Bothng Water Reactors." Science and Engn tems addressed in tNs report are the auxlhary feedwater, the neering /gstociates, Inc. (SEA) and Software Edge, Inc. (SE) de-low pressure injecton, and the teactor coolant systems. The re. veloped (Ns PC-tened code. The instructons to effecttvely use sdte provide a risk.6nformed ranking of Ov696f&as wttNn this code to evaluate the potential of debna to suffc6ently block these systems. a pump sucten strainer such that a pump could lose NPSH margin was documented in a User's Manual (NRC, NUREG/CR.

NUREQ/CR 6796: REASSESSMENT OF SELECTED FACTORS AFFECTING SITING OF NUCLEAR POWER PLANTS. 6370). The Reference Manual contains additonal information DWIS,A E. HANSON.AL: MUDAYl,V.: et al. Brookhaven No, mat suppwts me use of BLOCKAGE 2.6. It contains desenp-tons of the analytcal models conta6ned in the code, prog *am-tonal Lateratory, February 19g7,117pp. 9703170247. BNL.

mer gudos illustrating the structure of the code, and summanos NUREG $2442. 92130197.

Brookhaven Nat60nal Lateratory has performed a tones of of coding vertfacaten and rrodel vahdaten exercises that were probatdhetc consequence assessment calculatons for nuclear P8'iormed to ensure that the analytical models were correctly reactor sihng TNs study takes into account recent ins 6ghts into coded and apphcatdo to the evaluston of BWR pump suction severe accident source terms and examines consequences in a strainers. The BLOCKAGE code was developed by SEA and risk tened format consistent with the quantitatrve heatth objec. programmed in FORTRAN as a code that can be executed from t'ves (OHOs) of the NRC's Sa'ety Goat Pokcy. Simohfied severe the DOS level on a PC. A grapNcal users fnterface (GUI) was accident source terms developed in this study are based on the than daysloped by SEA to make BLOCKAGE easier to use and nsk insights of NUREG 1160 and compared to those used in to provide OrapNcal output capatality. The GUI was pro.

earber studies, part6cularty the Sandia Siting Study. The results grammed in the C language. The user has the option of execut-of the present study indicate that both the quantity of radonettv. Ing BLOCKAGE 2.6 with the GUI or from the DOS level and the Ity released in a severe accident as well as the likelihood of a Users Manual provides instructen for both methods of execu-release are lower than ttmo predicted in earter studies The 100.

accident naks using the atmphfed source terms are examined at NUREG/CR4379; AN lMPROVED CORRELATION PROCEDURE a sones of Doner6c plant sites that vary in populaton distribu.

FOR SUBSIZE AND FULL SIZE CHARPY IMPACT SPECIMEN DATA. SOKOLOV,M.A.; ALEXANDER,D.J. Oak Ridge Natonal rEe o ca laton a pe or v a Laboratory. March 1997, 302pp. 9704170020. ORNL4888.

facts of emergency protectrve action assumptons on the risk of prompt fatality and latent cancers fatality, and populaton reloca- 82MO M To examine the potential for using subsue Charpy specimens ton 4 The study finds that based on the new source terms, the to waluate me matedal properbes of vessel materials for life prompt and tatont fatahty naks at all generic sites meet the extenson, a study was conducted on the behavior of subsue OHOs of the NRC's Safety Goal Pohey by margins ranging from impact specimens of ftve different geometnes. Effects of nutch one to more than three orders of magnitude.

depth, angle, and radius, as well as overall specimen dimen-NUMEG/CR4370: BLOCKAGE 2 6 USER'S MANUAL RAO.D.V,; sions were determined. Correlations of the transiton tempera.

BRIDEAU,J; et al, Sceence & Engineenng Associates. Inc. ture determined by the different subsue specimens as com-DERNAHL.W. Software Edge, Inc., December 1996. 129pp. pared to full stre specimens were evaluated. A new procedure 9702060212. SEA 963104010A 3. 91657:126. for transforming data from subsize specimens was developed The BLOCKAGE 2.6 ,,odo descried in this User's Manual was developed by the United States Nuclear Regulatory Com NUREG/CR4399: IPIRO 2 TASK 1 PIPE SYSTEM EXPERI.

messon (NRC) as a tool to evaluate hcensee comphance wtth MENTS WITH CIRCUMFERENTIAL CRACKS IN STRAIGHT.

NRC Bulietin 9643, " Potential Plugging of Emergercy Core PIPE LOCATIONSTinal ReportSeptember 1991 November Coohng Suction Stra#nere by Debris in Bosling Water Reactors", 199% SCOTT.P,; OLSON.R.; MARSCHALL C.; et al. Battelle As such, BLOCKAGE 2.6 prov6 des a poneralued frarrework into Memorial institute, Columtma Laboratones February 1997, wh6ch a user can input plant-spectic and insulation-spectic data 363pp. 9703170239. BMi 2187. 92129.001.

for periorming analyses in accordance with Regulatory Guide This report presents the results from Task 1 of the Second 1.82. Rev, 2 This user a manual describes the capatdlities of international Piping Integnty Research Group (IPIRG 2) pro.

BLOCKAGE 2 6 along with a descripton of the graphics user's gram. The rationale for and objecttwo of Task 1 was to build on interface prov6ded for data entry. Each input / output dialog is de- the results of the first IPIRO program by evaluating. (1) the trac-ectlbed in detall along wtth special consideratona related to de- ture behavior of circumferentalty cracked pipe subtected to veloping and executing BLOCKAGE, Also, several sample prob- rnore complex load Nstones, such as ssmulated seisme load lems are provided such that user can easity modify them to suit Notones; (2) cracks at geometnc discontnsides, such as elbow

S Main Citat6ons ar>d Abstracts perth welds, (3) smallet orcumferential surf ace cracks, rnore typ- The NRC Human Factors Engineenng Propam Revbew Model )

6 cal of those considered in in service flaw evaluabons, sub fected (HFE PRM, NUREG-0711) was developed to support a desgn l to dynartwc, cyclec load tutones; and (4) circumferential process review for advanced reactor design certifcation under throug4 wall cracked pipe sot 9ected to dynamic, cyche k ad his- 10CFR$2. The HFE PRM defines ten fundamental elements of todos. As a resutt of trese Task 1 efforts. It was shown that. (t) a human factors ergeneering program. An Operating Exponence the load <arryvig capacity of a cracked pipe autvected to a sam- Review (OER) > one of these elements. Tre rnain purpose of ulated motsme load history is no worse than that of a ancked an OER to to A1entify potentel safety issues from operatng pge sutgected to the s6rgie-frequercy excitaton evaluated in plant exponence and ensure that they are addressed in a new IPlHG 1;(?) cracks at elbow girth welds can be adequately ana- design. Broad based exponence revows have typ6cally been fyred unsrg metteds prevkausty developed for cracks in straght performed in the past by reactor desgners. For the HFE PRM, pipe, and (3) anaysis methode previously developed and veri- the intent is to have a more focussed OER that concentrates on fed for large otrcumferential surface cracks and cucumferential HFE lesues or experence that would be relevant to tre human-tryoug4 wall packs work equatry well for sma.ler cracks, even system interface (HSI) design process for new advanced reac-when subjected to more comples load histor6es. tors. This document provides a de'alled lest of HFE-relevant op.

ersung experience portsnent to the HSI design process for ad-NUREG/CR4393: INTEGRATED SYSTEM VAllDATION: METH, varced nuclear power plants. We dement is Med to te ODOLOGY AND REVIEW CRITERIA. O'HARAJ.; STUBLER,W used by NRC rev6 ewers as part of the HFE PRM review process HIGGINS.J.; et al. Brookhaven Nabonal Laburatory. Januarh M Mormining h cornpmu of an OER perW W an 1997,116pp.9702000198. DNL NUREG 62483. 91655:231, aMeant W shanced reacw &sgn ceSch The U.S. Nuclear Regulatory Comm6ss6on reviews the human factors engveerirg (HFE) aspects of advanced nuclear power NUREQ/CR4414: PlPING BENCHMARK PROBLEMS FOR THE plant de@s, in order to support the advanced reactor desgn WESTINGHOUSE AP000 STANDARDIZED PLANT, DEZLER P.;

certifcahon reeews, the HFE Program Rev6ew Model was de- DEGRASSIG.; BRAVERMAN.J.; et al. Brookhaven Nat6onal veloped The resDdel describes the HFE program elements that Laboratory. January 1997, 300pp. 9702250218. DNL-NUREG.

are necessary and suffetent to develop an acceptable detailed 62487, 91871:001, denen and provides the rev6ew Crtterla for the6r evaluation. One To sabafy the need for verification of the computer programs of the e, view elements is vonficahon and val 6dateort The pur. and modchng techn69ues that will be used to perform the final pose of ttva dooumont is to d souse the detailed methodolog6 cal p6 ping analyses for the West 6nghouse AF500 Standardtred conssderatons necessary for a review of an HFE Integrated Plant, three benchmark problems were develotmi The prob.

system vahdahon. A conceptual approach, or paradigm, to inte' lems are representatrve p6 ping systems subjected to representa-grated system vahdacon is presented which idenUfies important ttve dynamic loads with solutions developed using the methods vahdation pnnciples and their relationships. The vahdation para- tein0 proposed for ana ysis for the AP000 standard dosegrt it dgm was used to identify the methodological aspects of the will be required that the combined Icensees demonstrate that vahdabon process that are needed to meet the general para- their solutions to these problems are in agreement with the digm requirements. The methodo6ogy must support a logeal benchmark problem set.

and defensible infe'ence to to made from vahdation tests to prodcted Integrated system performance under actual operatin0 NUREQ/CR4426 V01: DUCTILE FRACTURE TOUGHNESS OF 1 I

conditions The vahdation paradigm is based upon four Oernrat MODIFIED A 302 GHADE H PLATE MATERIALS DATA ANALY.

terms of velvtfy' tystem reprasantai6on, performance represen- SIS. MCCADE,0 E.; MANNESCHMIDT,0.; SWAIN.R.L Oak tabon, test design and statisteal conclus6on validity Vahdating Ridge Nabonal Laboratory. January 1997, 80pp 9702190023.

an integrated system to based on estabhshin0 that these four ORNL4892. 91802:192.

types of valtdity are satshed. Such assessments are made by The objective of this work was to develop ductile fracture rev6 ewing the methodology used to conduct vahdahon tests. toughness data in the form of SR curves for modshed A 302 Methodolugacal factors relevant to each of the aspects of valid 6- grade B plate matanals typical of those used in fabr6cating reac-ty are discussed. tot pressure vessels. A previous expertmental study at Materials Engineenng Associates, Lanham, Maryland, on one partcular NUMEQ/CR4397: RADLATION SAFETY CONCERNS FOR heat of A 302 grade B plate showed decreasing SR curvos with i PREGNANT OR DREASTJEEDING PATIENTS.The Posttsons Increased specimen thekness. This characterist#c b9s not been Of the NCFtP And The ICRP. MEINHOLD.C B. Brookhaven Ha. obswved in numerous teste made on the more recent produc-tional Latostory, January 1997, 23pp. 9702070213. BNL. tion motorials of A 533 grade B and A 508 class 2 pressure NUREG 52484. 91666 3I8. vessel steels. It was unknown if ttw departure from norm for the for many years, protecting the lotus has been a concem of MEA matertal was a generic charactenste for all heats of 4 302 the National Council on Radiation Protection and Measurements grade B steels or just uneque to that one partcular plate.

(NCRP) and the intamational Commission on Radiolog6 cal Pro.

tactiun (ICRP) Early recommendations focused on the possibili- NUREQ/CR 6426 V02: DUCTILE FRACTURE TOUGHNES 3 OF ty of a wide var 6ety of detrimental developmental effects while MODIFIED A 'J02 GRADE B PLATE MATERIALS. Data Gecords, later recommendations focused on the potential for severe MCCADE,D.E ; MANNESCHMIDT.E.; SWAIN,R.L Oak Ridge mental retardation and/or reduction in the intelhgence quotient National Laboratory. Fetruary 1997, 600pp. 9703200279 (10). The latest recommendations also note that the nsk of ORNL 6092 92104:001 cancer for the fetus is probably two to three hmes Dreater per TM Mw d (Nd wM wu to develop ducW fracta Sv than 6n the adutt. For all these reasons, the NCAP and the toughness data in the form of AR curves for modthed A 302 ICRP have provided guidance to physicians on taking all ree- grade B plate matenals typ6 cal of those used in fathating reac-sonatile steps to ascertain whether any woman requ6nng a radi- tor pressure vessels. A provtous expenmental study at Matenals okycal or nuclear medic 6ne procedure is pregnant or nursan0 a Engineenng Associates (MEA) on one partcular heat of A 302 child. The NCRP and the ICAP also advise the citnician to post- gr@ B pam M Moa SR s Wh incenM h ocedures until after dehvery or cosaatton of nurs- a tenus. TM charactWe hu nd W @swvM in numerous tests made on the more recent production maten-NUREO/CR4400: HUMAN FACTORS ENGINEERING (HFE) IN- als of A 533 grade B and A 508 class 2 pressure vessel ste91s.

SIGHTS FOR ADVANCED REACTORS BASED UPON OPER. It was unknown if the departure from norm for the MEA mat' nel ATING EXPERIENCE. HIGGINS J.; NASTA,K. Brookhaven Na- was a genenc cnaractonste for all heats of A 302 grace B tional Latwatory, January 1997, 61pp. 9704100181, BNL. steels or just urwque to that one particular plate. Seven heats of NUREG 52485. 92410 244. modated A 302 grade B steel and one heat of vintage A 533

Main Citadons and Abstracts 7 grade B steel were provided to this project by the Ger. oral Ele > irstal crock, in aMtion, the J-R curvea from the SEN(T) speck inc Company of San Jose, Califortwa AR plates were tested for rnons closMy match the J-R curve from the surface-cracked chorrucal content, tensee properties, Charpy transiten tempera- pipe er.penment. f3) CtT) expenmental results suggest that ture curves, drop weght nilductibty transition (NOT) tampera* there is a large 6ffererwe in the quasbatate, monotonc tough-tare, and J-R curves Tensus tests were rnade in the thrp pnn- noss between the two heats of DP2-A8, as well as a toughness cipal onentatens and at four terrporatures, rangeng from room degradston in th5 lower toughness heat of rnatorial (DP2 ABII) temperature to 550 degrees F (288 depoes C) Charpy V notch when loaded with e dyname, cycle (R = 0.3) loading history.

transtion temperature curves ws.to obtained in longitudinal, transverse, and short transverse onentatons. J-R curves were NUREG/CR4452: THE SECOND INTERNATIONAL PIPING IN-made using four specunen stres (1/2T, IT, 2T, and 4T) The TEGRITY RESEARCH GROUP (IPIRG.2) PROGRAMJenal fracture mecharwes based evaluabon method covered three test Report. HOPPER,A.; WILKOWSKlG.Ma SCOTT Pa et at Bat-onentat one and three test temperatures itBO,400, and 550 de- telle Memonal irrstitute, Columbus Laboratories. March 1997, grees F (82,204, and 288 degrees C)) However, the coverage 295 9704080E BML219E 92387M of these vanables was contingent upon the amount of matenal The IPIRG.2 program was an 6nternational group program provided. Drop we6ght NOT temperature was determined for the managed by the U.S. NRC and funded by organizatons from 15 T L onentaten only. None of the seven heats of modified A 302 natens. The emphasis of the IPIRG 2 program was the deveL grade B showed size effects of any consequence on the J-R opment of data to vertty fracture anatyses for cracked pipes and curve behacor, Crack onentaten effects were present, but none were severe enough to be toported as styp6 cal. A test tempera. fittings sub}ected to dynamc/cycic load histories typical of seis-tore increase from 180 to 550 degress F (82 to 288 degrees C) me events. The scope included: (1) the study of more complex produced the usual loss in J-R curve fracture toughness Gener- dynamic / cycle load I.istories, is., mutthfrequercy, variable am-ic J-R curves and mathemat6 cal curve fits to the same were plitude, simulated seismic excitatens, than those considered en generated to represent each heat of material. Volume 1 deals the iPIRG 1 program (2) crack sizes more typical of those con-with evaluatson of data and docusson of technical fin 6ngs. This sidered in Leak.Before-Break (LBB) and in service flaw evalua-voeurre (Volume 2) to a compilabon of all data developed. tons, (3) through-wall-crecked pipe expenments which can to used to validate LDB type fracture analyses, (4) cracks in and NUREG/CR4433: CONTAINMENT PERFORMANCE OF PROTO. around pipe fittings, such as elbows, and (5) labowery speck TYPICAL REACTOR CONTAINMENTS SUBJECTED TO men and separate effect pipe expenments to provide better in-SEVE RFi ACCIDENT CONDITIONS. KLAMERUS.E.W.;

DOHN.M.P. Sandra Natonal Laboratones. WESLEY,D.A.; et al. 36ght into the effects of dynamic and cycle load histones Also EOF Engineenng Consultants (formerty EOE Engineertng. Inc ). undertaken were an uncertainty anatysis to 6dentity the issues December 1996 125pp. 9702060245. SAND 90-2445. most important for LBB or irvoorvice flaw evaluabons, updating 91657:001. computer codes and databases, the development and conduct in SECY 90-016, the NRC mosed a safety goal of a condh of a senes of round-robin analyses, and analyst's group rt.eet-tonal containment failure probility (CCFP) of 0.1 and the al- ings to provide a forum for nuclear peping experts from around tornauve acceptance entena allowed for steel containments, the world to exchange informahon on the subject of pipe frac-with specifies that the stresses should not exceed ASME ture technology.

Level C allowables for severe accident pressures and tempera-tures. In this work, the need for an equivalent enteron for con- NUREG/CR-6466: REVIEW OF INDUSTRY EFFORTS TO oote containments was stueed. Su surrogate containments MANAGE PRESSURIZED WATER REACTOR FEEDWATER were desgned and anatyred in order to compare the margins NOZZLE, PIPING, AND FEEDRING CRACKING AND WALL between desgn pressure, pressure resulung in exceedance of THINNING. SHAH,V.N.; WAftE,A G.; PORTER,A M. Idaho Na-Level C (or yield) stress hmits, and ultimate oressure. For com- tonal Engineenno Laboratory. March 1997,100pp.9704170076.

parability, each containment has an 6dentcal intomal volume INEL 96/0089. 92531:091, and design pressure. Results from the analysis showed margins Rev60w of industry efforts to manage ther.na: fatque, flow-ac-to yoid are comparable and 6 splay a similar margin for both celerated corrosion, and steam genera. w water hammer steel and concrete containments. In addition, the margin to fall, damage to Pressurtred Water Reactor (PWR) feedwater nor-ure, although shghtly h6gher 6n the stool containments, were also comparable. F6nalty, a CCFP for code design was determined ries, piping. and feednngs is presented in (Ns report. The review includes an evaluabon of desgn rnodifcatons, operatng based on general membrane behavior and imposing an upper bound severe acc6 dent curve developed in the DCH stu$es. procedure changes, augmented inspection and monitonng pro-The resutbng CCFP's were less then 0.02 (or 2%) for all the grams, and mitegaton, repair and replacement activitiew. Four nu,rogate containments studed, showing that these contain- spectic actions were taken to perform the evaluation (a) review ment desgns all actueved the NRC safety 0041- of I' eld expertence to 6dentify trends of operating events; (b) review of the related technical literature; (c) visits to three PWR NUREQ/CR-6446: FRACTURE TOUGHNESS EVALUATIONS OF plants and a PWR vendor; and (d) solcitaten of informaton TP304 STAINLESS STEEL PIPES. CUDLAND D L; from fore 4gn ubhties. Our assessment of field expenence indi-BRUST,F.W.; WILKOWSKI,G M. Battelle Memonal institute, Co.

cates the USNRC bconsees have apparentty taken suffeient lumbus Laboratones. February 1997.116pp. 9703100252, BMI-2194, 92062 225.

acton to minimize the feedwater norrie cracking caused by in the IPtRG 1 program, the J.R curve calculated for a 16 thermal fatque, wall thinning of J-tubes and feedwater piping, 6nch nommal Gameter, Schedule 100 TP304 stainless steel and steam Donerator water hammer in both top feed and pre-(DP2 AB) surface cracked pipe expenment (Expenment 1.3 3) heat steam generators. A major findirg of this review is that the was considerabty lower than the quaskstatic, monotonc J-R analysm, inspecton, morvtonng, mitgation, and replacement curve calculated from a C(T) specimen (A812a). The results techniques have been developed for managing thermal fabgue from several related investgabons conducted to determine the and flow acce6erated corrosion damage to feedwater norries, cause of the otserved toughness difference are: (1) Chemcal piping, and feedrings. Adequate training and appropnate appli-analyses on sechorw of Pipe DP2-A8 from several surface- cations of these techniques would ensure effective manage-cracked pipe and matenal property specimen fracture suriaces ment of tNs damage. Several PWR plant operators have been inscate that there are two dstinct heats of metenal within Pipe proactive in managing this damage.

DP2 A8 that efter in chemical wiip0Ecn. (2) SEN(T) spec 6-men expenmental results 6ndcate that the toughness of a sur- NUREG/CR 6469: EXPERIMENTS TO INVESTIGATE DIRECT facecracked specimen is hgh!y dependent on the depth of the

1 i

l 1

s Main Citations and Abstracte l CONTAINMENT HEATING PHENOMENA WITH SCALED feed design /anatysse methodology for uruque types of modules, MODELS OF THE CALVERT CtlFFS NUCLEAR POWER such as the concrete fslied steel module. In the second phase i I

PLANT, BLANCHAT,T.K.; PILCH.M M.: ALLEN.M D. Sandia Na- of tNo program, Modular Constructon Review Cntena were de-teonal Laboratones. February 1997, 195pp. 9703170250. veloped to provide guidance for iconsang reviews In the tNrd )

SAND 96 2289. 92130 001, phase, an analysis effort was conducted to determane if current- l The Surtney Test FacJhty at Sandia National Laboratones ly evallatdo firste element analysis technques can be used to (SNL) is used to perform scaled expeoments for the Nuclear predet the response of concrete fdled steel modules.

Regulatory Comtnesson (NRC) that samu', ate Hgh Pressure Melt Electon (HPME) accidents in a nuclear power plant (NPP). NUREQ/CR4493: DOSES TO THE HAND DURING THE ADMIN-These expenments are desagned to investgate the effects of ISTRATION OF RADIOLABELED ANTIDODIES CONTAINING direct containment heating (DCH) phenomena on the contain. Y 90,TC-DDM,l-131, AND LU 177, BARBER,0,E. Minnesota, rnent load. In prev 6ous experiments, Ngh. temperature, chemcal- UnN. of Minneapohs, MN. CARSTEN.AL: KAURIN D G L.: et h reactrve (thertrWtc) melt was ejected by Ngh-pressure steam m NM Wratory. FeWuw 1997, %

ento a scale model of erther the Zion or Surry NPP, The results dB from the ton and Surry exportments were extrapolated to other 9703100224. DNL NUREG 52510. 92035.235.

Exposure of the hands of medcal personnet administenng re-Weshnghouse plants This report describes teste periormM with i Combustion Ergineenng plant geometries (in partcular, Catvert deolabeled anubodies (RADS) was evaluated on the basis of (a)

Chfie-hke) and the impact of codispersed water as part of the observing and photodocumenting administraton tochtwgues, overall Doli issue resolution, integral effects tests were per- and (b) expenmental data on doses to thermoluminescent dos 6-formed witn a 1/10th scale model of the Catvert Chffs NPP meters (TLDs) on f ngers of phantom hands holding syringes, inside the Surtsey test vessel The expenments investgated the and on syringes, with radionuchdes in the syr6nges in each case.

effects of codispersal of water, steam, and molten core simulant Dose rate coeffc6ents to the skin, if in contact wtth the syringe matenals on DCH loads under prototypic accident condatons wait, were 89,1.9, 3.8, and 0,41 uSv a( 1) averaged over i and plant configuratons. The resutta ind4cated that large CM(2) at 7 mg CM( 2) per 37 MBq (1 MCI) for Y 90, Tr -99m, l-amounts cd coejected water reduced the DCH load by a small 131, and Lu 177, respectivety. When using Y 90 the importance amount Large amounts of debne were dispersed from the of avoiding direct contact with syringes containing RADe and of cavtty to the upper dome (v6a the annular gap). usmg a beta.part6cle sNeld on the syringe was indcated. In NUREQ/CR447d: PRELIMINARY PHENOMENA IDENTIFICA. using a syringe for injecton, doses can best be approximated TION AND RANKING TABLES (PIRT) FOR SBWR STARTUP for the geometry studied by (a) weanrg a finger dosimeter on STABILITY, ROHATGI,U.S.: CHENG.H.S; KHAN,H.J.; et at the middle finger, toward the outside of the hand, on the hand Brookhaven National Laboratory. March 1997, 81pp. operating the plunger, and (b) weanng fnger dossmeters on the 9703200285. DNL NUREG 52504. 92196 001, inner (palm) side of the finger on the hand that supports the sy-Phenomena identificaton and Ranking Tables (PIRT) have ringe for energetic beta-partcle emitters, such as Y 90 and Re-been developed for a start up transient for SUWR. The informa- 188.

tion used for PIRT came from RAMONA-4B and TRACG anaty.

nos of the transient and from related small scale tests. The NUREG/CR4513 N01: NRC HIGH-LEVEL RADIOACTIVE l transient was divided into four dintsnct phases, namety, Sub- WASTE MANAGEMENT PROGRAM ANNUAL PROGRESS Cooled Core Heat up, Subcooled CNmney, Saturated CNmney, REPORT: FISCAL YEAR 1996. SAGAR B. Center for Nuclear and Power Ascensiort The assessment criterion selected was Waste Regulatory Anatyees. January 1997,317pp.9704080389.

Merumum Cntical Power Rato The SDWR system was divided 92385:001, into ten componenta. A total of 35 distinct phenomena aneg This annual status report for fiscal year 1996 documents the components were identified. The Phase I has 28 ranked technical work performed on ten key techn6 cal issues (KTis) phenomena with 17 low, 6 medium, and 5 Ngh ranking. The that are most important to performance of the proposed geolog-Phase 11 hasJ' 9 ranked phenomena with 18 low,13 medium ic repository at Yucca Mountairt TNs report was prepared joint-and 8 Ngh reinking The Phase til has 47 ranked phenomena with 22 low,10 rnedium and 15 Ngh ranking. TFS Phase IV has ly by the staff of the Nuclear Regulatory Commesson (NRC) Di-46 ranked phenomena with 10 low,12 medium and 18 Ngh v6 son of Waste Managenent and the Center for Nuclear Waste ranking, Regulatory Analyses. The programmate aspects of restructunng NUREQ/CR44D6: ASSESSMENT OF MODULAR CONSTRUC- " " *7 * ***** F '" #

TION FOR SAFETY RELATED STRUCTURES AT ADVANCED I*" # * * * *E'# " " *T '

NUCLEAR POWER PLANTS. BRAVERMAN.J.; each m' hems on p%M4 d Wa 4 HOFMAYER,C, Drookhaven Natonal Laboratory, MarchMORANTE.R{-

199 cane acM and Ms consequerces, impacts of sMural deb.

201pp.9704170099. DNL NUREG42520. 92518 014.

maton and sessnW, the natn of the neaMeld environment Modular construction techruques have been successfulty used and Ma docts on contaner Me and source term, h and trans-in a numter of industriew, both domest6cally and intomationaPy, Recentty, the use of structural modules has been proposed for port including effects of thermal loading, aspects of repository advanced nuclear power plants. The objective in utilmng mob design, estimates of system performarce, and activities related tar construction 6s to reduce the Construction schedule, reduce to the U.S. Environmental Protecten Agency standard are pro-constructon costs, and lmprove the quality of construction. TNa vidM report documer'ts the results of a program wNch evaluated the proposed use of modular construction for safety related struc- NUREQ/CR4528: ENVIRONMENTAL ASSESSMENT PRO.

tures in advanced nuclear power plant designs. The program in- POSED LICENSE RENEWAL OF NUCLEAR METALS.INC.

ciuded review of current modular constructon twhnology, de. CONCORD, MASSACHUSETTS. MILLER,R.L.; EASTERLY,C.E.:

velopment of hcensing rev6ew critena for modular construction, LOMBARDI,D.A. et at Oak Ridge Natonal Laboratory, February and truttal validation of currentty available anatytical techniques 1997. B8pp. v703 t 00266. 92020.152.

appled to concrete-filled steel st Wural modules. The program This Environmental Assessment was prepared to evaluate on-was conducted in three phases. The objectrve of the first phase vtronmental 6ssues associated with the renewal of NRC Licens-was to identrty the techncal tsaues and the need for further ee Nos. SMB-179 and SUB 1452 for facilrbes operated by Nu-study in order to support NRC hcens6ng rev6ew activities. The c6 ear Metals, Inc. (NMI) in Concord Massachusetts. License re-two key hndings were the need for supplementary review crtte- neoal is needed to permit the M,uation of NMI operations na to aug<nent the Standard Rev6ew Pian and the need for ver6- involving depleted and miral uranium.

Main Citations and Abstracts 9 NUREG/CR4629 VALIDATION OF TECTONIC MODELS FOR anomalous strain told-up occurnne there By reoccupying 1930 AN INTRAPLAT E SEISMIC ZONE,CHARLLSTON. SOUTH tnangulaton and 1980 GPS sitt<s witn su inmble SST dual fro-CAROLINA WITH GPS GEODETIC OATA. TALWANI.P.; quency recervers, a strain rate of 0 4 s 10( 7) yr01) was ob-KELLOGG.J N ; TRENKAMP.R. South Carolina, UrWv. of, Colum- served At the 9$% confidence level, this value is not sigruto taa. SC February 1997, Sepp 9703100260 920'9 299. cant, however, at a lower level of contdonce (- 85',) it is Although the everage strain rate in entraplate settings is 2 3 about two twders of magnitude greater than the background of orders of magrvtude lower than at plate toundanes, there are 10( 9) to 10( 10) yr( 1) The direction of contracton inferred pockets of Ngh strain rates wittun entraplate regons The results from the GPS survey 66 dogrees 111 degrees is in encellent e of a Global Positorung System survey near the locaton of cur- agreement with the duecton of the manmum toniontal stress rent seismoty (and the enferred locaton of the destructive 1886 (N 60 degrees E) in the area. Suggesting that the observed Charleston, South Caro na earthquake) suggest that there is strain rate is also real-

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Secondary Report Number index This index lists, in alphabetical order, the performing organization Issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-r:forenced to the NUREG number Tor the report and to the 10 digit NRC Document Control System accession number, SGCOIIDARY htPORT NutettR MPORT NUtIDER ttCole0ARY MPORf NUGAGER MPORT nut 00ER AtOD/ttf41 NUNLG/L* 44h6 BNL Nunt G 67604 NVAEG/CR4474 ANL.Da/14 NUHf G/CP4164 kNLWUREG 62610 NUHf G/CH4493 NUHf G 160s DNLWUNEG 62670 NURE G/CR4496 DLA E18 Bf 401 CNR (96)1 / 46

.# hl 638

<,i u DML#196 N u G,Cneo.9 NURt G/CR4462 g=t=, = ig g = vo, OANL4892 NUREG/CH4426V02 DNL NUMt G 619M NUHL G/CR.4409 YO6 cw3ytftu.9693 NVAt G/CR-4719 Vit N2 DNL WtMif.0 67442 NUlit G/CH4296 PNNL 9020 NUREG/CR4181 A01 (WdLWUHtG 62443 NUHf G/CR4393 $ANDe6 #P99 NUAE G/CR4469 DNt WUttiG 62464 NVAl'G/CH 4397 &ANC96-t446 NUAF G/CH4433 DNLWtMIEQ 67486 NVAt G/CR4400 6t A 90 3104-A 4 - NuntG/CH4371 16NLWUHLG 62497 NUHLG/CR4414 $EA963104010A 3 NUPEG/CR4370 11

I t

l l

Personal Author index This index lists the personal authors of NRC staff, contractor, and international agreemeu 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.

ALE X ANDE R.DJ. CARSTEN.A.L.

NUREG/CR4379 AN IMPROVED CORRELATION PROCLDURE FOR NUREG/CR4493. DO6ES TO THE HAND DURING THE ADMINISTRA.

SUBSIZE AND FULL SIZE CHARPY IMPACT SPECIMEN DATA. flON OF RADIOLABELED ANTIBODIES CONTAINING Y 90,TC 99M,b 131, AND LU.177, NUHEG/CR4469 EXPERIMENTS TO INVESilGATE DRECT CON. CHENG.H.S.

T AINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE NUREG/CR4474: PREUMINARY PHENOMENA 4DENTIFICATION AND CALVERT CUFFB NUCLEAR POWER PLANT, RANKING T ABLES (PIRT) FOR 88WR ST ARTVP STABILITY.

ban #ER.DA. DAYtt,MJ.

NUREG/CR4493 DOSES TO THE HAND DURING THE ADMINISTRA. NUREG 1874 DRFT FC- STANDARD REYlEW PLAN ON TION 9F RADIOLABELED ANTIBODIES CONTAINING Y.90.TC 99M,0 ANTITRUSTheft Report For Comment 131, A ND LU 177, SAUMJ V . NUREG/CR4296: REASSESSMENT OF SELECTED FACTORS AF.

NUREfls/CR4493 DOSEB TO THE HAND DUFilNG THE ADMINISTRA. FECTING SITING OF NUCLEAR POWER PLANTS.

BELED ANTIBODIES CONT AINING Y 90,TC 99M,b DEGRASSIA NUREG/CR4414; PIPING BENCHMARK PROBLEMS FOR THE WES-DEMMAHL,W, TINGHOUSE AP900 STANDARDIZED PLANT.

NUREG/CR4370. BLOCKAGE f 6 USER'S MANUAL I NUREG/CR 63T1. BLOCKAGE 2 6 RU ERENCE MANUAL CP 164. PROCEEDINGS OF THE CNRA/CSNI WORKSHOP DE2LE R.P.

ON STEAM GENERATOR TUBE INTEGRITY IN NUCLEAR POWER NUREG/CR4414 PlPING DENCHMARK PROBLEMS FOR THE WES, PLANTS.

TINGHOUSE AP600 STANDARDLit0 PLANT. DOCTORAM.

NUREG/CR4181 R01: A PILOT APPUCATION OF RISK INFORMED MANCHAT T.K.

METHOOS TO ESTA8USH INSERVICE INSPECTION PRIORITIES NUREG/CR4469 EXPERIMENTS TO INVESilGATE DIRECT CON- FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE CALVERT CLIFFS NUCLEAR POWER PLANT, POWER STATION.

EASTERLY,C E.

goggg ,*

NUREQ/CR4628. ENVIRONMENTAL ASSESSMENT PROPOSED Lb NUREG/CR4431 OONTAINMENT PERFORMANCE OF PROTOTYPl. CENSE RENEWAL OF NUCLEAR MET ALS,1NC. CONCORD, MASSA-CAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCl- CHUSETTS' DENT CONDITIONS.

PUEGEL.M tmAYtnMANJ' NUREG 1632: FINAL TECHNICAL EVALUATION REPORT FOR THE NURE G/CR4414 PIPING BENCHMARK PROBLEMS FOR THE WES- PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-

^

G S M TC LA'M CONSTRUCTION FOR 53 SAF ETURELATED STRUCTURES AT ADVANCED NUCLEAR POWER PLANTS- PRANCla#,R.

NUREG/CR4369; IPIRG.2 TASK 1. PIPE SYSTEM EXPERIMENTS SMIDEAUJ. WITH CIFtCUMFERENTIAL CRACKS IN STRAIGHT-PIPE CR OC E ENCE ANUAL OHAD6AU N.

DROWEW, NUREG/CR4452 THE SECOND INTERNATIONAL PIPING INTEGRITY NUREG/CR4393 INTEGRATED SYSTEM VAUDATION. METHODOLO" RESEARCH GROUP (lPIRG-2) PROGRAM Final Report GY AND REVIEW CRITERIA.

00mEAP.

snussestTT.E. NUREG/CR4181 Rot: A PILOT APPUCATION OF RISK INFORMED NUREG 1632 FINAL TECHNICAL EVALUATION REFORT FOR THE METHOOs TO ESTABLISH INSERVICE INSPECTION PRIORITIES PROPOSED REVlSED RECLAMATION PLAN FOR THE ATLAS COM- FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR FORATION MOAB MILLSmace Walenni Uconee No. SUA-017.Dodet POWER STATION.

No, 403453 (Ates CorPcretorg emEEMEA 940ST.F.W. ' NUREG 1662 DAFT FC: STANDARD REVIEW PLAN FOR APPUCA-NUREG/CR4446. FRACTURE TOUGHNESS EVALUATIONS OF TP304 TIONS FOR UCENSES TO DISTRIBUTE BYPRODUCT MATERIAL TO ST AINLESS STEEL PIPES. PERSONS EXEMPT FROM THE REQUIREMEN18 FOR AN NRC UCENSE.10CFR Parts 30,14,30,16, M16,30.18.30.19 & 30.20.

NUREG 1662 DAFT FC: STANDARD REVIEW KAN FOR APPUCA. HAttesEYER,0.

110NS FOR UCENSES TO DSTRIBUTE BYPRCOUCT MATERIAL 10 NUREG4713 V17; OCCUPATIONAL RADIATION EXPOSURE AT COM-PERSONS EXEMPT FROM THE REQUIREMONTS FOR AN NRC MERICAL NUCLEAR POWER REACTORS AND OTHER UCENSE_10CF R Parts M14.M16 M18.M18/J0.19 & 30.20. F ACluTIES,1995.TwentyOghth Annual Report 13 i

14 Personal Author index HAN60N,A1. EANIK,QJ.

NUHEG/CR4266 F4E ASSESSMINT OF' SELECTED FAC1DRS AF. NOREG 1276 V12- OPERATING EXPERIENCE FEEDBACK FECTING SITING OF NUCLEJJ4 FOWEF4 PLANTS. REFORT.Assessmani Of Stent Fuel Coohng HOGINSJ. LAYTON.M.

NUREGiCR4393 INTEGRATED SYSTEM VALIDATION METHODOLO$ f40 REG-1532. FINAL TECHNCAL EVALUATION REPORT FOR THE OY AND REVIEW CRITER6A IHOPOSED REVISED RECLAMATION PLAN FOR THE ATLAS ODR.

NURE QtCR44'O HUM AN F ACTORS ENGINE E RING (HFE) INSOHTS PORATON MOAB MILL Source Matenal Lxsense No. SUA 917 Docket FOR ADVANCED FtEACTORS BASED UFON OPERATING EXPERI- No. 40 3453 (Atlas Corporaton)

Ef4Cl.

LOMSARDI.DA HOFMA YE R.C. NUREG/CR4526. ENVIRONMENTAL ASSESSMENT PROPOSED Li-NURf G/CR 64b6 ASSESSMENT OF MODULAR CONSTRUCTION FOR CENSE RENEWAL OF NUCLEAR METALS.INC. CONOORD, MASSA-SAf ETY.RELATED STRUCTU84ES AT ADVANCED NUCLEAR CHUSETTS fOWLR PLANTS MANNESCHMCLE.

HOPPER,A NUREG/CR4426 V01: DUCTILE FRACTURE TOUGHNESS OF MODI-NUREG/CR4389 iPIRG 2 TASK 1 PIPE SYSTEM EXPERIMENTS FIED A 302 GRADE B PLATE MATERIALS. DATA ANALYSIS.

WIT H CIF40JMF E RE NTIAL CRACKS IN STRAIGHT. PIPE ffUREG/CR4426 V02 DUCTILE FRACTURE TOUGHNESS OF MOOl-FLED A 302 GRADE B PLATE MATERIALS Data Records NUI /CR 52 E COf D INYER TlON PI I NTEGRITY RE SEARCH GROUP (IPIRG 2) PROGRAM f Inal Report MARSCHALL.C.

f4UREG/CR4389- iPIRG 2 TASK 1 PlPE SYSTEM EXPERIMENTS ISARRAdQ. WITH CIRCUMFERENTIAL CRACKS IN STRAIGHT-PIPE NURE G.1275 V12. OPERATING EXPE RIENCE FEEDBACK LOCATIONS Final Report Septomter 1991. Novemt.or 1995.

REFORT Ateneemoni Of Spent Fuel Coohng

'BR AHIM.A.

MCCASE*0 E NURI G 1532. FINAL 1ECHNICAL EVALUATION REPORT FOR THE NUREG/CR4426 V01: DUCTILE FRACTURE TOUGHNESS Or MODI-FIED A 302 GRADE B PLATE MATERIALS. DATA ANALYSIS Pf40 POSED REVISED RECLAMATON PLAN f OR THE ATLAS COR-NUREG/CR4426 V02: DUCTILE FRACTURE TOUGHNESS OF MODI-PORATION MOAB MILLSouru Matenal Ucorse No SUA 917. Docket 14o 443453 (At.as Corporatson) FIED A 302 GRADE B PLATE MATERIALS Data Records MCGUIRE,S.A.

JOHNSON.T.

NUREG 1532 5INAL TECHNCAL EVALUATON REPORT FOR THE NUREG 1492. REQULATORY ANALYSIS ON CRITERIA FOR THE RE-PROPOSED $40VtSED RECLAMATION PLAN FOR THE ATLAS COR, LEASE OF PATIENTS ADMINISTERE'D RADOACTIVE MATERIAL Final Report PORATON MOAB MILLSource Malenal utense No. SUA-917.Doctet No 40-3453 (Atlas Corporaton) g JONE S.W.R. NUREG/CR4397: RADIATON SAFETY CONCERNS FOR PREGNANT NURf G 1275 V12 OPE RATING EXPERIENCE FEEDBACK OR BREAST FEEDING PATIENTS The Ponstons Of The NCRP And HEPORT.Asseenment Of Spent Fuel Cookng The ICRP.

JL 9TUS,P, WILLER R.L FUREG 1532. FINAL TECHNICAL EVALUATION REPORT FOR THE NUREG/CR 6528 ENVIRONMENT AL ASSESSMENT PROPOSED Li-fHOPOSED RE' VISED RECLAMATION PLAN FOR THE ATLAS COR- CENSF RENEWAL OF NUCLEAR MET ALS.tNC CONCORD, MASSA-PORATION MOAB MILL $ource Matenal Ucense f40 SUA-917. Docket CHUSETTS i 40. 40 3453 ( Atlas Corporaton)

WOHAN R.

KAutlN,0 Q.L. NUREG/CR4452 THE SECOND INTERNATONAL PIPING INTEGRITY NLREG/CR 6493 DOSES TO 1HE HAND DURING THE ADMINISTRA- RE SEARCH OROUP (IPtRG 2) PROGRAM Final Report RON OF RADOLABELED ANTIDODIES CONTAINING Y 90,TC 99M,6-131, AND LU-177, MONTELEONE,S.

NUREG/CP4157 VO1- PROCEEDINGS OF THE TWENTY-FOURTH KELLOGQJ N- WATER REACTOR SAFETY INFORMATON MEETING Pienary See-NUREGICH 6529 VALIDATION OF TECTONC MODELS FOR AN IN. son. High Bumup Fuel. Containment And Structural Aging TRAPLATE LEISMC ZONE CHARLESTON. SOUTH CAROLINA WITH NUREG/CP 0157 V02 FHOCEEDINGS OF THE TWENTYFOURTH GPS GEODET C DAT A- WATEFI REACTOR SAFETY INFORMATION MEETING Reactor Pres-KHAN,HJ

""'" N""*' I ***"' "' A""** 0 **

• NUREG/CR4474 PREllMINARY PHENOMENA IDENTIFICATION AND R ANAING T AOLES (PtRT) F-OR SUWR ST ARTUP STABILITY, NUREG/C50157 V03 PROCEEDINGS OF THE TWENTY-FOURTH WATER REACTOR SAFETY INFORMATION MEETING PRA And HRA, KHAM,T.A.

And ProbatAste Seismec Hazard Assessment And Seisme Srbn0 Ct.le-NUREG/CR4409 V06 DAT A BASE ON DOSE REDUCTION PRCUECTS na FOR NUCLEAR POWLR PLANTS.

KILINSitt,1, WORANTE.R.

NURt G/CR 6452 THE SECOND INTERNATIONAL PIPtNG INTEGRITY NUREG/CR44bo. ASSESSMENT OF MODULAR CONSTRUCTION FOR FIESEARCH GROUP (IPtRG 2) PROGRAM Final Report SAFETY-RELATED STRUCTURES AT ADVANCED NUCLEAR POWER PLANTS KLAltERUS,t W.

NUREQ/CR6433 CONTAINMENT PERFORMANCE OF PROTOTYPI- WUSAYLV-CAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCI. NUREG/CR 6295 REASSESSMENT OF SELECTED FACTORS AF.

DENT CC44DITIONS FECTING SITING OF NUCLEAR POWE R PLANTS KRi&HNASW AM Y,C. NAST A.K.

NUREG/CR 6433 CONTAINMENT PERFORMANCE OF PROTOTYPb NUREG/CR 6400. HUMAN FACTORS ENGINEERING (HFE) INSGHTS CAL RE ACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCI- FOR ADVANCED REACTORS DASED UPON OPERATING EXPERI-DENT CONDITIONS ENCE EAM6E W.M. NOURBAKHSH.H.P.

NURt G-1574 DRFT FC: STANDARD REVIEW PLAN ON NUREG/CR4295 REASSESSMENT OF SELECTED FACTORS AF.

ANil1 RUST Draft Report f or Comment FECTING SITING OF NUCLEAR POWTR PLANTS

Personal Author index 15 014ARAJ. SCOTT P.

NOREG/CH4393 INTEGRATED SYSTEM VALOATON METHC 3OLO- NUREG/CR4369 IPIRG 2 TASK 1. PLPE SYSTEM EXPERIMENTS OY AND REVIEW CRITERIA. WITH CIRCUMFERENTtAl CRACKS IN STRAIGHT PIPE LOCATIONS Final Fioport Septemper 1991. Novenber 1995.

OLSONA NUREG/CR4452 THE SECOND INTERNATONAL PIPING INTEGRfTY NUREG/CR4369 IPIRO P TASK 1 PlPE SYSTEM [KHRIMEMTS RE SEARCH GROUP (IPIRG 7) PROGRAM Final Report WITH CIRCUMFERENTIAL CRACKS IN STRAOHT4 tPE LOCATONS Final Report 1991. Nwomber 1996 SHAFFER.CJ, NUREG/ER4452 THE SE INTERNATIOFAL PIPtNG INTEGRirY NUREG/CR437Ct BLOCKAGE 2 6 USER'S MANUAL RE $[ ARCH GROUP (IPIRG-7) PROGRAM Final Report NUREG/CR4371: BLOCKAGE 2 6 REFERENCE MANUAL ORNSTSIN.H.L SHAH,VX NUREG.tt76 Yt t. OPERATING EAPEFilENCE FLEDBACK NUREG/CR4466. REVIEW OF INDUSTRY EFFORTS TO MANAGE REPORT.Aseeenment Of Speni Fuel Cooling PRESSURlZED WATER REACTOR FEEDWATEM NOZZLE, PtPING, PAUL.D. AND FEEDRING CRACKING AND WALL THINNING NUREG/CR4462 THE SECOND INTERNATIONAL PlPING INTEGRITY RESEARCH GROUP (IPIRG f) PROGRAM Final Rogert p g PENNELLW.E. METHODS TO EST ABLISH INSERVICE INSPECTION PRIORITIES NUREG/CR4219 V12 NP. HEAVY SECTION STEEL TECHNOLOGY FOR NUCLEAR COMPONENTS AT SURRf UNIT 1 NUCLEAR PROGRAM Semannnual Progress Report For April 1995 Ttrough Sep POWER STATON.

tomber 1995.

SOKOLOV,M.A.

PHAMXK. NUREG/CR4379 AN IMPROVED CORRELATION PROCEDURE FOR NUniG/CR4181 R01: A PILOT APPLICATlON OF RISK-lNFORMED SUBSIZE AND FULL SilE CHARPY IMPACT SPECIMEN DATA.

METHODS TO ESTABUSH INSERVICE INSPECTION PRIORITIES FOR NUCLEAR COMPONLNTS AT SURRY UNIT 1 NUCLEAR SOUTO.F.

POWER ST ATION NUREG/CR4370. BLOCKAGE 2.6 USEFr8 MANUAL PILCH.M M. STRUCKMEYER,R.

NUREG/CR4469. EXPERIMENTS TO INVESilGATE DIRECT CON- NUREG4837 V16 NO3 NRC TLD DIRECT RADLATON MONITORING TAINMENT HEATING PHENOME NA WITH SCALED MODELS OF THE NETWORK.Progrees Report July September 1996.

CALVERT CLIFF S NUCLEAR POWER PLANT. NUREG.0837 Vie N04. NRC TLD DIRECT MADtATION MONITORING NETWORK. Progress Report October December 1996.

NUREG/CR4456 REVIEW OF INDUSTRY EFFORTS TO MANAGE STUSLER,W.

PRESSURIZED WATER REACTOR FEEDWATER NOZZLE, PIPING. NUREG/CR4393. INTEGRATED SYSTEM VALIDATON METHODOLO-AND F EEDRING CRACKING AND WALL THINNING- GY AND REVIEW CRITERIA.

EI Y' SWAIN R.L N E 7 V OPE RATING PERIENCE FEEDBACK NUREG/CR4426 V01: DUCTILE FRACTURE TOUGHNESS OF MODI FIED A 302 GRADE 8 PLATE MATERIALS. DATA ANALYSIS.

RADDATZ,M.G. NUREG/CR4426 V02. DUCTILE FRACTURE TOUGHNESS OF MODI-NUREG-1671 INFORMATION HANDBOOK ON INDEPENDENT SPENT FIED A 302 GRADE B PLATE MATERIALS.Dete Records.

FUEL STOMGE INST ALLATONS. 9ALyggg,p.

RAO,0.V, NUREG/CA-6529 VAllDATION OF TECTONIC MODELS FOh AN IN-NURE G/CR4370- BLOCKAGE t 6 USER 8 MANUAL TRAPLATE SEISMC ZONE, CHARLESTON. SOUTH CAROLINA WITH NUREG/CR4371: htOCKAGE F 6 REFERENCE MANUAL GPS GEODETIC DATA RICH T. THOMAS.M.L.

NUREG 1562 DRFT FC: STANDARD REVIEW PLAN FOR APPLICA- NUREG 0713 V17: OCCUPATONAL RADIATION EXPOSURE AT (X)M-TlONS FOR LICENSES TO DISTRIBUTE BYPRODUCT MATERIAL TO MERICAL NUCLEAR POWER REACTORS AND OTHER PERSONS EKEMPT FROM THE REOulHEMENTS FOR AN NRC FACILITIES,1995.TwentyOghth Annual Report LICENSE.10CFR Parte 30.14,30.16,30.16.30.16.30.19 & 30.20.

TREITLER,LE.

ROHATGI,U.S. NUREG/CR45?6. ENVIRONMENTAL ASSESSMENT PROPOSED Li-NUREQ/CR6474 PRELIMINARY PHENOMENA IDENTIFICATION AND CENSE RENEWAL OF NUCLEAR METALS,1NC, CONCORD, MASSA.

A ANKING 1 ABLES (PtRT) FOR SUWR ST ARTUP ST ABILITY, CHUSETTS.

ROM.D.

NUREG-1537. FINAL TECHNICAL EVALUATON REPORT FOR THE TRENKAMP,R' NUREG/CR 4 5?9 VALIDATION OF TECTONIC MODELS FOR AN IN-PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR~ TRAPLATE SEISMIC ZONE. CHARLESTON. SOUTH CAROUNA WITH PORATION MOAB MILLSource Metenal License No. SUA 917. Docket GPS GEODETIC DAT A No. 40 3453 (Atlas CorporetkwQ  ;

VO,T.V. I RUDLARD L NUREG/CR4181 Rot: A PILOT APPUCATON OF RISK-INFORMED NUREG/CR4369. IPIRG 2 TASK 1. PIPE SYSTEM EXPERIMENTS METHODS TO ESTABLISH INSERVICE INSPECTON PRIORITIES WITH CIRCUMFERENTIAL CRACKS IN STRAIGHT PtPE FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR LOCATIONS Finel R September 1991 November 1995 NUREG/CR4446, F TURE TOUGHNESS EVALUATIONS OF TP304 POWER STATION STAINLESS STEEL PIPES WANG,YX NUREG/CR4452. THE SECOND INTERNATONAL PIPING IN".;GRITY RESEARCH OROUP (IPIRG.2) PROGRAM Final Report .. NUREG/CR4414: PIPING BENCHMARK PROBLEMS FOR THE WES-TINGHOUSE AP600 STANDARDtZED PLANT, SAGAR.S.

NUREG/CR4513 Not: NRC HGH-LEVEL RADCACTIVE WASTE MAN- W ARE.A 0-AGEMENT PROGRAM ANNUAL PROGRESS REPORT: FISCAL YEAR NUREG/CR4456. REVIEW OF INDUSTRY EFFORTS TO MANAGE 1996 PRESSURIZED WATER REACTOR FEEDWATER NOZZLE, PlPING, AND FEEDRING CRACKING AND WALL THINNING.

SCHMEIDER,8, NUREG-1492. REGULATORY ANALYSIS ON CRITERIA FOR THE RE. WATERS.M.D.

LEASE OF PATIENTS ADMINISTERED RADIOACTIVE NUREG 1671; INFORMATON HANDBOOK ON INDEPENDENT SPENT MATERIAL. Final Report FUEL STORAGE INST ALLATONS.

16 Personal Au9ar index Wf DLE V,D.A. WOLTt RM AN.R.

NUFtLG/CR4433 CONTAINMENT PE FtFORMANCE OF PROTOTYpg. NURE G/CR 4389 iPtRG t T ASK 1. PIPE SYSTIM [xPE RIME N1G WIT H C4ROUur t F4LNTIAL CRACKS IN STRAIGHT PiPC CAL REACTOR OCWTAINMENTS SUBJECTED TO SEVERE AOC4 Wild 4S final Regat Septenter 1991 f4monter 1995 Dt NT CONDITIONS.

WOOD R t.

Wit.KOW9Et,0M. NURt G 1677 DRrt IC ST ANDAftD REVirW PLAN ON POWE R RE AC.

NUREQ/Cf14389 IP6RG t TA&K T . P6PE $YSTIM [EPER'MLNTS TOR LICENStf flNANCIAL QUALIFICATIONS AND DCOOMMIS-WITH QROUMF ERt NTIAL CRACAB IN STRAIGHT. PIPE StONHG FUNDING ASSURANCE Drott Reg <r17or Comment LOCAflONS f anal Report September 1991. f4ovember t996 NURtG/CR4446 iRACTURE TOUGHNE&$ EVALUATIONS OF TP304 *(U$t' CR4474 PR[lluiNARY PNENOutNA IDENTIFICAT60N AND NUF t / 62 it $tCOND 6NTt RNATIONAL PIPING INTtGRITY RLSL ARCH GROUP (IPIRO P) PROGRAM f anal Fteptrt Elt) W.

NUREG/CR-4409 VO6 OATA BA$t ON DOSE REEMCTION PROJECTS WINDOWAT. FOR NUCLEAR POWER PLANTS NURLG/CR4528 ENVIRONMENT AL AS$t$$ MENT PROPOSED Lt. Etuut RM AN,G.P.

CENSF At NEWAL OF NUCLEAR MET AL6JNC. CONCORD MASSA

• NURin/CR4528 LNVIRONMENTAL ASSE$SulNT PROPOSED Lt.

Q4USETTS CCNSE Rt NEWAL OF NUCLEAR METALB.INC. CONCUiD, MASSA.

Q4USLTTS

Subject index This index was developed from keywords and word strings in titles and abstracts. During this developrnent 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 welcome.

O 8et trade B 9 teel Mete Commurdes#en NUREG/CR446 V01: DUCTILE FRACTURE 100GHNESS OF MODL NUREG 1646 EVALUATION CRITCHIA FOR COMMUNICATIONS-RE.

FitD A 302 GRAE4 8 PLATE MATERIALS, DATA ANALYSIS LATED CORRECTIVE ACTION PLANS.

NUREG/CR4476 V02 DUCTILE FRACTURE TOUGHNEb8 OF MODb FIED A 302 GRADE 9 PLATE MATERLALS Dete Records- Centelnment N') REG /CP4167 V01: PROCEEDINGS OF THE TWENTY FOURTH ALAAA WATER REACTOR SAFETY INFORMATION MEETING Plenary See-NU8%G/CR-4409 V06. DATA BAfit ON DOSE REDUCTION PROJECTS esori, High Bumup Fuel Centenment And Structural Ayng FOR NUCLEAR POWER PLANTS.

Centelnment Portermance N '8**' P P'*"' NUREG/CR4433. CONTAINMENT PERFORMANCE OF PROTOTYPb NUREG/CR 4486 ASSESSMENT OF WODULAR CONSTRUCTION FOR CAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACOb SAI ETY4tELATE D STRUCTURES AT ADVANCED NUCLEAR DFNT CONDITIONS-POWER PLANTS.

Control Reem m NUREG/CR4393 INTEGRATED SYSTEM VAllDATION METHODOLOw NUREG 1674 DAFT FO, STANDARD REVIEW PLAN ON ANTITRUST. Deft Report f or Commert GY AND REVIEW CNTERA Catee Corporemen Certootive Aetten Plan NUREG 1632 FINAL TECHNICAL EVALUATION REPORT FOR THE NUREG 1646: EVALUATION CRITERIA FOR COMMUNICATIONS-RE.

PROFOSED REVISED HCCLAMATION PLAN FOR THE ATLAS COR. LATED CORRECTIVE ACTION PLANS.

PORATION MOAB MILLSource Metenal Lkenee No. SUA 917. Docket

• N 608 FINAL ENVIRONMENTAL IMPACT STATEMENT TO DLOCEAOS3 CONSTRUCT AND OPERATE THE CROWNPOINT URANIUM SOLU-NUREG/CR4370 BLOCKAGE # 6 USER'S MANUAL TlON MINING PROJECT, CROWNPOINT, NEW MEXICO Docket No.

NUREG/CR4371: BLOCKAGE t 6 REFERENCE MANUAL 404988 (Hydro Resources, tre )

Dudget totimate Crvetal 9trein NUREG 1100 V13. BUDGET ESilMATER Flecol Year 1998- NUREG/CR4529 VALIDATION OF TECWIC MODELS FOR AN IN.

TRAPLATE BEISMIC ZONE.CHAFILESTON. SOUTH CAROLINA WITH U 1 DRFT FC STANDARD REVIEW PLAN FOR APPLICA.

8 0 ON E TIONS FOR LICENSES TO DISTRIBUTE BYPRODUCT MATERIAL TO Det, rte Genereuen PERSONS EXEMPT FROM THE REQUIREMENTS FOR AN NRC NUHEG/CR4370; BLOCKAGE 2 6 USLR'S MANUAL LICENSE.10CF A Parte 30,14.30 16,30 16,30 18,30 10 & 30 20- NUREG/CR4371: BLOCKAGE 2 6 REFERENCE MANUAL C88MA/C9804 Wertiehop - - -

NUREG/CP01$4 PROCEEDINGS OF THE CNRA/CSNI WORKSHOP r~NUREG-167ED 1FT FC. ST ANDARD REVIEW PLAN ON POWER ON STEAM GENERATOR TUBE INTEGRITY IN NUCLEAR POWER TOR LICENSEE FINANCIAL QUAllFICATIONb AND DECOMMIS-PLANI 8- slONtNG FUNDING ASSURANCE. Draft Report For Cornment Calvert Cane Desier' Cr%erte NUREG/CR4460 EXPERIMENTS TO INVESTIGATE DIRECT CON. NUREG/CR4433 CONTAWWENT PERFORMANCE OF PROTOTYPl.

1 AINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE CAL REACWR CONTAINMENTS SUBJECTED TO SEVERE ACCl-CALVERT CLIFFS NUCLEAR POWER PLANT. DENT CONDITIONS.

Certineate Of Comptance y y 3, G PE IMENTS TO INVESTIGATE D6AECT CON.

TAINMENT HEATING PHENOMENA WITH SCARD MODELS OF THE Certeneemen CALVERT CLIFFS NUCLEAR POWER PLANT, NUREG/CR4400t HUMAN FACTORS ENGINEERING (HFE) INSIGHTS F ADVANCED REACTORS BASED UPON OPERATING EXPERb O***

p FOR NUCLEAR POWER PLANTS.

Chern impost NUREGICR4379 AN IMPROVED CORRELATION PROCEDURE FOR 0**'**Y SUBSIZE AND FULL SLZE CHARPY IMPACT SPL*iMEN DATA NUREG/CR4493: DOSES TO THE HAND DURING THE ADMINISTRA-TION OF RADIOLABELED ANTIBODIES CONTAINING Y 90,TC 99Ml-Cereumeerennel Creoli 131, AND LU 177.

NUREG/CR4300' IPtRG4 TASK 1 PIPE SYSTEM EXPERIMENTS WITH CIRCUMFERENTIAL CRACKS IN STRAIGHT. PIPE Duette Fracture LOCATIONS Fmel Report Septernbar 1991 November 1996. NUREG/CR4426 V01: DUCTRI FRACTURE TOUGHNESS OF MODI-FIED A 302 GRADE B PLATE MATERIALS. DATA ANALYSIS.

Ctedmang Sftest NUREQ/CR-4219 Vit NA HEAVY SECTION STEEL TECHNOLOGY Dynamic Load PROGRAM Semannual Progrees Report For Aprs 1995 Through Sap- NUREG/CR4414. PtPING BENCHMARK PROBLEMS FOR THE WES-tomber 1996. TINGHOUSE AP900 STANDARDLZED PLANT, 17

18 Sut$ect indes

&mbranoment Heavy 4ect6en Stesi Technology Program NUREG/CP4167 V02 890CEEDINGS OF THE TWENTYJOURTH NUREG/CR 4219 V12 Nt HEAVY SECTON STEEL TECHNOLOGY 1 WATER REACTOR SArETY INFORMATION MEETING Reactor Pree- PROGRAM Sermannual Progrees Report For Apri 1996 Ttrough Sep- i pure Veneel Errerttnemeril Ard Thermal Anneeling Reactor Veosal tomter 1996.

Lower Head Irdegrity Ard Evenuetson Ard Projecton of Sletm Genere. ,

tur tute ., H6ph Dumup Fuel 74UREG/CP4167 V01: PROCEEDINGS OF THE TWENTYJOURTH Smbry* .

WATER REACTOR SAFETY INFORMATON MEETING Planery Geo-NUREG/CR4397. RADLATON SAf ETY CONCERNS FOR PREGNANT esurt High Durnup Fuel Contesnment Ard Structural Apng OR BFtEAST FEEDING PATIENTS The Powbone Of itw NCRP Ard Tte ICRP, H6g4 Level Weele NUREG/CR4613 f401. NRC HIGH LEVEL RADIOACTIVE WASTE MAN-Environmental Aeeseement AGEMENT PROGRAM ANNUAL PROGRESS REPORT: FISCAL YEAR NUREGICR4528 (NVIRONMENTAL ASSESSMENT f*OPOSED Lt. 1996.

CENSE RE NEWAL OF NUCLEAR METALS.lNC. CONCORD, MASSA.

CHUSETTS Human f actor NUREG-1646 EVALUATON CRITERIA FOR COMMUNICATIONS-RE-teeminemen Diendsed LATED CORRLCTIVE ACTION PLANS.

NUREG 1021 INT FtD8 OPERATOn LICtNSING EKAMit4ATON 8iAND<

AROS FOR POWER REACTORS Human Factore Engineering NUREG/CR 6393. INTEGRATED SYSTEM VALDATION. METHODOLO-teempt OletribuMon h GY AND REVIEW CRITERIA NUREG 1662 DRM FC: ST ANDARD REVl[W PLAN FOR APPLICA- NUREG/CR4400. HUMAN F ACTOR $ ENGINEERING (HFE) INSIGHTS flONS FOR LICENSES TO DISTRIBUTE BVPRODUCT MATERIAL TO FOR ADVANCED REACTORS BASED UPON OPERATING DPERL-PERSONS EKEMPT FROM THE REQUIREMENTS FOR AN NRC ENCE.

LICENSE.10CF R Parts 30.14,3016,30.16.3018.3010 & 30.20.

IPIRG-2 Tsek 1 Foodring Creeking .

NUREG/CR4389 (PIRG-2 TASK 1. PIPE SYSTEM EXPERIMENTS NUREG/CR44te REVIEW OF INDUSTRY EFFORTS TO MANAGE WITH CHCUMFEFtENTIAL CRACKS IN STRAIGHT PIPE PRESSURilED WATER REACTOR FE EDWATER NOZZLE, PlPING, LOCATONS Final Report septemter 1991. Novemter 1996 AND F E EDRING CRACKING AND WALL THINN:NQ ISF &l

" ^

CR 56 REVIEW OF INDUSTRY EFFORTS TO MANAGE $T E SYSTEMS F na PRESSllRil[D WATER REACTOR FE EDWAfEH NOZZLE, PIPING, AND F EEDRING CRACKING AND WALL THINNING Impoet Teoung NUAEG/CR 6379. AN IMPROVED CORREuTION PROCEDURE FOR 1 SUBSilE AND FULL SIZE CHARPY IMPACT SPECIMLN DATA REG 1 N NVIRON NTAL IMPACT STATEMENT TO CONSTRUCT AND OPERATE THE CROWNPOINT URANtuM SOLU. In Situ Leech TION MINING PROJECT, CROWHPOINT, NEW MEXICO Docket No. NUREG 1606 FINAL ENVIRONMENTAL IMPACT STATEMENT TO 40 8968 (Hydro Roeources, Inc ) CONSTRUCT AND OPLAATE THE CROWNPOINT URANIUM SOLU.

TION MINING PROJECT, CROWNPOINT, NEW MEKlCO. Docket No.

P1 names; Que#%eWen NUREG 1677 DRM FO- ST ANDARD REvi[W pun ON POWER REAC- 40 6968 (Hydro Resources, Inc.)

TOR LICEf4SEE FINANCIAL QUALIFICATIONS AND DECOMMIS- --

SIONit40 FUNDING ASSURANCE Dren Report For Comment -NUREb;t671: Spent Fuel Storage INFORMAflON installet6on HANDOOOK ON INDEPENDENT SPENT Prooture Resehenlee FUEL STORAGE INSTALLATIONS.

NURE G/CP4167 V02. PROCEEDING 9 Or THE TWENTY FOURTH 0 '

WATER REACTOR SAFETY INF0F1MATION MEETING Reactor Pres- 8 R01: A PILOT APPLICATION OF RISK-INFORMED sure vessel Emtrittlement And Thermal Anneehng. Reactor vessel METHODS TO ESTABLISH INSERVICE INSPECTION PRIORITl[$

Low 4eed Integrity Arwi Evolustion And Projecison of Steam Genere.

FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR POWER STATON.

NUREG/CE44f2 THE SECOND INTERNATIONAL PIPING INTEGRITY RESE ARCH GROUP (IPIRG 2) PROGRAM f Inal Report integrated System Prooture Toughnees f4UREG/CR4393. INTEGRATED SYSTEM YAllDATION. METHODOLO.

NUREQ/CR4219 V12 f42- HEAVY SECTION STEEL TECHNOLOGY GY AND REVIEW CRITERIA Pf OG Sermannual Progrees Report For April 1995 Ttrough Sel> gn,,,, ,gg,,,,,

NUREG/CR4389 IPIRG 2 TASK 1. PlPE SYSTEM EXPERIMENTS NUREG-1678: INFORMATION HANDBOOK ON INDEPENDENT SPENT WifH CIRCUMFERENTIAL CRACKS IN STRAIGHT PIPE FUEL STORAGE INSTALLATONS.

LOCAflONS Final Report Septembe- 1991 f40 venter 1905 NUREG/CR4426 V01: DUCTILE FRACTURE TOUGHNESS OF M008- #4"8'

NUREG/CR-8389 IP;RG 2 TASK 1. PlPE SYSTEM EXPERIMENTS FIED A 302 GRADE D PLATE MATEFtlALS. DATA ANALYSIS NUREG/CR4426 V02: DUCTILE FRACTURE TOUGHNESS OF MODI. W'TH Car 1CUMFERENTIAL CRACKS IN STRAIGHT PIPE FIED A 302 GRADE B PLATE MATERIALS Data Recorde. LOCATIONS Final F4eport September 1991. Hovember 1995.

NUREG/CR4446 FRACTURE TOUGHNESS LVALUAllONS OF TP304 NUREG/CR4452: THE SEODND INTERNATIONAL PIPING INTEGRITY ST AINLESS STEEL PlPES. RESEARCH GROUP (IPIRG 2) PROGRAM. Final Report Puel Reek . J41 Curve f40 REG 1276 Vit OPERATING EXPERIENCE FEEDBACK NUREG/CR4426 V02. DUCTILE FRACTURE TOUGHNESS OF MODI-REPORTAseenement Of Spent Fuel Coohno FIED A 302 GRADE B PLATE MATERIALS Data Recorde NUREG/CR4446. FRACTURE TOUGHNESS EVALUATIONS OF TP304 Punding Aeeuronee STAINLESS STEEL PIPES NUREG 1677 DRFT FC: ST ANDARD REVIEW PLAN ON POWER REAC- NUREG/CR4462 THE SECOND INTERNATIOt4AL PIPING INTEGRITY TOR LICENSEE FINANCIAL OUAltriCATONS AND DECOMMIS- RESE ARCH GROUP (IPIRG 2) PROGRAM Finni Report SiONING FUNDING ASSURANCE Deatt Report For Comment Legal leeuencee Geeeste Date NUREG4760 V44101: INDEXES TO NUCLEAR REQULATORY COM.

NUREG/CH4529 VALIDATION OF TECTONC MODELS FOR AN IN. MISS60N ISSUANCESJuly-September 1996, TRAPLATE SEISMIC ZONE. CHARLESTON. SOUTH CAROLINA WITH NUREG4760 V44 N05. NUCLEAR REGULATORY COMMISSION IS-GPS GEODETIC DATA. SUANCES FOR NOVE MBER 1996. Pages 229 314.

1

}

Subject index 19 NUREG4760 V44 606 NUCLEAR REGULATORY COMulSSON IS. Phonentne teorruheehon SUANCES FOR DECEMBER 1996 Pepee 315-432 NUREG/CR4474. PREllulNARY PHENOMENA IDENTIFICATION AND NUREG0760 V46 Not: NUCLEAR Rt GULATORY COMMISSON IS- RANKING T ABLES (PIRT) FOR SBWR ST ARTUP ST A8luTY.

BUANCE S F OR JANUARY 1997. Popes 147.

PIPE Eleonee Renmeal NUREGICR4448 FRACTURE 1OUGHNE$$ EVALUATIONS OF TP304 NUHEG/CR4628 ENVIRONMENTAL ASSESSMENT PROPOSED U- 8i AINLE SS STEEL PIPE S CEt4SE HE NEWAL OF NUCLEAR METALS.lNC. CONCORD. MASSA. NUREQ/CR4462. THE SECOND INTERNATONAL PIPtNG INTEGRITY CHUSETT8- FtESEARCH GROUP (IPIRG-2) PROGRAM Final Report M111 Telling Ptpe System NURLG 1632 Fit 4AL TECHNICAL EVALUATION REPORT FOR THE NUREQ/CR4389. IPIRG-2 T ASK 1 PIPE SYSTEM EXPERIMENTS PROPOSED Rf VISED RECLAIAATION PLAN FOR THE ATLAS COR- WITH CIRCUMFERENTIAL CRACKS IN STRACHT PIPE PORATION MOA8 MsLL Bource Melanel Uoorse No. SUA-917. Docket LOCATONS Final ReportBePternber 1991 November 1995-640 40-3453(Atlas Cor$FJretOn)

Piping Weeuler Constructlen NUREG/CR4414: PIPING BENCHMARK PROBLCMS FOR THE WES-NUREG/CR 6466 ASSESSME NT OF MODULAR CONSTRUCTION FOR TINGHOUSE AP000 ST ANDARDIZED PLANT.

SAF ETY4<E LAT ED STRUCTURES AT ADVANCED NUCLEAR NUREG'CR4456 REVIEW OF INDUSTRY EFFORTS TO MANAGE PCWER PLANIS PRESSURIZED WATER REACTOR FEEDWATER NOZZLE., PIPING, AND FEEDRING CRACKING AND WALL TH!NNING.

NUREGICR 6101 A01: A PILOT APPUCATION OF RISkiN80AMED Piping System METHODS TO $$TADUSH INSERvlCE INSPECTION PRIORITIES NUREG/CR4161 R01: A PILOT APPUCATON OF RISK INFORMED FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR METHOOS TO ESTABUSH INSERVICE INSPECTON PRIORITIES POWE R ST AT ON. FOR NUCLEAR COMFONENTS AT BURRY UNIT 1 NUCLEAR

^

Nuclear C;.nn NURIG/CR4181 A01: A PILOT APPLICATON OF RISK-INFORMED piege maiorgel METHODS TO ESTADLISH INSERVICE INSPECTION PRIORITIES NUREG/CR44?6 V02: DUCTILE FRACTURE TOUGHNJS$ OF MO(L FOR fiUCtE AA COMPONENTS AT SURRY UNIT 1 NUCLEAR FIED A 302 GRADE 9 PLATE MATERIALS Date Rooords.

POWER ST ATION Pregnant Women Noch We<pcIno NUREG/CR4397 RADIATION SAFETY CONCERNS FOR PREGNANT NOREG/CR4493. DOSES TO THE HAND DURING THE ADMINISTRA- OR BREAST FEEDING PATIENTS.The Poemons Of Tte NCAP And ilON OF RADOLABELCD ANTIBODIES CONT AINING Y 90,TC 99M.l- The ICRP, 131, AND LU 177.

Presoure Veoeel

""****' I"* NUf4EG/CR4379- AN IMPROVED CORRELATON PROCEDURE FOR NUREG/CR4678 INVIRONMENTAL ASSESSMENT PROPOSED U. SUBSIZE AND FULL SIZE CHARPY IMPACT SPECIMEN DATA.

CE NSE RENEWAL OF NUCLE AR MET ALS.INC. CONCORD, MASSA.

CHUSET18- Proteurtied Water Reactor NUREG/CR4456 REVIEW OF INDUSTRY EFFORTS TO MANAGE Noch Pm Punt PRESSURIZED WATER REACTOR FEEDWATER NOZZl.E PIPING, NUREG/CR4?v5. REASSESSMENT OF SELECTED FACTORS AF. " "" " ^" ^

FECTING SITING OF NUCLEAR POWER PLANTS N REG 6j69 P M NtS O $1i TE DIRECT CON-Occupeuonal Redlet6on Esposure T AINMENT HEATING PHENOMENA WITH 3CALED MODELS OF THE NUftEG0713 V17, OCCUPATIONAL RADIATION EXPODURE AT CC*g_ CALYLRT CLIFFS NUCLEAR POWER PLANT.

MERICAL NUCLEAR POWER REACTORS AND OTHER F AClutlES,1995. Twenty Eighth Aswiuol Reptwt

/CR4397. RADIATON SAFETY CONCERNS FOR PREGt4 ANT OPereting Esportonce OR BREAST FEEDING PATIENTS The Poortione Of The NCRP And NURE G 1276 Yt t. OPERATING EXPERIENCE FEEDBACK The lCRP.

ftE PORT Assessment Of S NUREG/CR 6400: HUM AN pent Fuel Coolmg Rathouon Doce ACTORS E NGINEERING (HFE) INSIGHTS FOR ADVANCED REACTORS BASED UPON OPERATING EXPERI. NUREG/CR4493. DOSES TO THE HAND DURING THE ADMINISTRA-TION OF RADIOLABELED ANTIBODIES CONTAINING Y.90,TC 99M,l-ENCE.

131, AND LU 177.

Operator Licensin9 NUREG 1021 INT R06 OPERATOR LICENSING EXAMINATON ST At40 Redlenon Protection ARDS FOR POWER RE ACTORS NUREG/CR-4409 V06. DATA BASE ON DOSE REDUCTON PROJECTS FOR NUCLEAR POWER PLANTS.

PWR NUREG/CR44's6 REVIEW OF INDUSTRY EFFORTS TO MANAGE Redloactive Meterial PRESSURt2ED WATER REACTOR FEEDWATER NOZZLE, PIPING, t4UREG 1492. REGULATORY ANALYSIS ON CRITERIA FOR THE RE.

AND f E f DRING CRACKING AND W ALL THINNING LEASE OF PATIENTS ADMINISTERED RADIOACTIVE NURE G/CR 4469 E XPERIMENTS TO INVESTIGA1E DIRECT CON- MATERIALFinal Report i AINMEN1 HEATING PHLNOMENA WITH SCALED MODELS OF Trit CALVERT Clif FS NUCLEAR POWER PLANT.

RN An'W NUREG/CR4493. DOSES TO THE HAND DURING THE ADMINISTRA.

Pettent Reisees CrMerle TON OF RADIOLABELED ANTIBODIES CONTAINING Y 90,TC 99M,1-NUREG 1492 REGULATORY ANALYSIS ON CRITERIA FOR THE RE. 131, AND LO 177, LEASE OF PATIENTS ADMINISTERED RADCACTIVE MATERLAL Final Report Reactor Accident NUREG/CR4295, REASSESSMENT OF SELECTED FACTORS AF.

Portermance Aseeeement FECTING SITING OF NUCLEAR POWER PLANTS.

NUREG/CR4513 Not: NRC HOH4EVEL RADCACTIVE WASTE MAN-AGEMENT PROGRAM MNUAL PROGRESS REPORT: FISCAL YEAR Reettor Component 199tt NUREG/CP 0157 V02: PROCEEDINGS OF THE TWENTY FOURTH H WATER REACTOR SAFETY INFORMATON MEETINC Reactor Pree-PetNtone For RulemeMrN eure Vessel Embrtttlement And Thermal Anneelmg. Reactor Vessel NURE04936 Vil NO2: NRC REGULATORY AGENDA.Servuonnual Lower Head integrity And Evolueton And Proleetson of Steam Genere-ReportJuly December 199tk tor tube.

30 SuMoot indu NUREG/OR4400; HUMAN FACTORS ENGINEERING (HFE) lHSIGHTS tempIWhed temng Water Roseter l FOR ADVANCED REACTORS BASED UPON OPERATING EKPERL NUREG/CR4474. PRELIMINARY PHENOMENA IDENTIFICATION AND ENOE. RANKING TASLES (PIRT) FOR SBWR STARTUP STABILITY.

Meester Operater este Chereetorteetlen NtaREG/CR4303 INTEGRATED BYSTEM VAllDATION METHODOLO- NUREG/CP4167 V03. PROCEEDINGS OF THE TWENTYJOURTH l QY AND REYlEW CRITERA WATIR REACTOR SAFETY INFORMATION MEETING PRA And HRA, I nd Probabilete Seeme Harord 6 ; we And Seemic Srtm0 Crne. )

NUMEG/CR4476 V01: DUCTILE FRACTURE TOUGHNESS OF MODI- )

FIED A 302 GRADE D PLATE MATERIALS. DATA ANALYSIS- este setect6en NUREG/CR4296: REAhSt$$ MENT OF SELECTED FACTORS AF.

G 167 Vot: PROCEEDINGS OF THE TWENTYJOURTH WATER REACTOR SAFETY INFORMATION MEETING Planery See- geluten Mene econ. High humup Fuel, Cor'lemment And Structural AgmD NUREG.1600. FINAL ENVIRONMENTAL IMPACT STATEMENT TO NUMEQ/EF4167 V02. PROCEEDINGS OF THE TWENTYJOURTH CONSTRUCT AND OPERATE THE CROWNPOINT URANIUM SOLLA WATER REACTOR SAFETY INFORMATION MEETINGReactor Proe' TlON MINING PRCUECT, CROWNPOINT, NEW MEXOO. Docket No, owe Yeessi Embrneomord And Thermal Armeelmg, Reactor Veneet j Lower Hood integrey And Eve 6uehan And Propecton of Steam Genere-M968 (H$ Rwm tre )

tot tube ... Spent Fuel NUMEQ/CP4167 V03 PROCEEDINGS OF THE TWENTYJOUPTH NUFtEG-1776 V12 OPERATING EXPERIENCE FEEDB4CK WATE R ftt ACTOR SAFETY INFORMAflON MEETING PRA And HRA. REPORT.Asessement Of Spent Fuel Coolmg And Probetdhetc Samme Hatertl Aseeeement And Somme Sten C 0 rne' NURLG 1636. STANDARD REVIEW PLAN FOR DRY SPENT FUEL NbG/ CMS 79& REASSESSMENT OF SELECTED FACTORS AF.

FECTING SITING OF NUCLEAR POWER PLANTS, geendard Review Plan NUREG.1636. STANDARD REVIEW PLAN FOR DRV SPENT FUEL Restamesen Plan STORAGE SYSTEMS Final Report NUREG 1637 FINAL TECHNICAL EVALUATION REPORT FOR THE NUREG 1t42 DRFT FC: STANDARD REVIFW PLAN FOR APPLICA.

PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR. TIONS FOR LICENSES TO DISTRIBUTE BYPRODUCT MATERIAL TO PORATION MOA9 MILLSource Meiertal License No. SUA-917. Docket PERSONS EXEMPT FROM THE REQUIREMENTS FOR AN NRC No. W463 (Anne Corpor*W LICENSE 10CFR Ports 3014,3016,3016.3010.3019 4 30.P0.

NUREG.1674 DRFT FC. STANDARD REVIEW PLAN ON

^ U S,8 40 6 N02. NRC REGULATORY AGENDA.Somennual NU E 7 C 1 0 EVIEW PLAN ON POWER REAC.

ReportJu*ytecember 1996- TOR LICENSEE FINANCIAL QUALIFICATIONS AND DECOMMIS. )

SiONING FUNDING ASSURANCE Oren Repor1 For Comment Regulatory W NUMEG 1492: REQULATORY ANALYSIS ON CTilTERLA 'OR THE RE.

FA O PATIENTS ADMINISTERED RADIOACTIVE EG 4474: PRELIMINARY PHENOMENA IDENTIFICATION AND

• I RANKING T ABLES (PIRT) FOR SBWR ST ARTUP STABILITY, )

Regulatory And Technteel Repe*t I'**"' h*

NOREG4304 V71 NO3 R(GULATORY AND TECHNICAL REPORTS NUREG/CP4164 . PROCEEDINGS OF THE CNRA/CSNI WORKSHOP (ABSTRACT INDEX JOURNAL) Comreannn For Ttwd Quarter ON STEAM GENERATOR TUBE INTEGRITY IN NUCLEAR POWER 1996)uirSeptember. PtANTS NUREQ/CR-4409 V08; DAT A BASE ON DOSE HEDUCTION PROJECTS Repeestery pesegn NUREG/CR4513 Not: NRC HIGH-LEVEL RADIOACTIVE WASTE MAN. FOR NUCLEAR POWER PLANTS.

MENT PROGRAM ANNUAL PROGRESS REPORT: FISCAL YEAR ,

NUREG 1636 STANDARD REVIEW PLAN FOR DRY SPENT FUEL Rules STORAGE SYSTEMS Fmal Report NUREG49J8 V16 N02: NRC REGULATORY AGENDA Semiennual NUREG 1571: INFORMATION HANDBOOK ON INDEPENDENT SPENT ReportJulyCecember 1996. FUEL STORAGE INSTALLATIONS-geWR 9 trees Corteenen Creeking NUREG/CR4474 PREllull.ARY PHf NOMENA IDENTIFICATION AND NUREG/CP 0164. PROCEEDINGS OF THE CNRA/CSNI WORKSHOP RANKING T ABLES (PIRT) FOR S0WR ST ARTUP STABILITY, ON STEAM GENERATOR TUDE INTEGRITY IN NUCLEAR POWER PLANTS.

Detety Moloted Structure NUREQ/CR4486 ASSESSMENT OF MODULAR CONSTRUCTION FOR Structural Aging SAFETY RELATED STRUCTURES AT ADVANCED NUCLEAR NUREG/CP4167 V01: PROCEEDINGS OF THE TWENTYJOURTH POWER PLANTS. WATER REACTOR SAFETY INFORMATION MEETING P6enery See-saon. High Sumup Fuel, Contamment And Structural Agmg.

NUREQ/CP4167 V03 PROCEEDINGS OF THE TWENTYJOURTH Suhetos Spoolmen WATER REACTOR SAFETY INFORMATION MLETING PRA And HRA, NUEG/CR4379. AN IMPROVED CORRELATION PROCEDURE FOR And Probotshenc Beanmc Haterd Aseeeement And Somme Sen0 Cme. SUBS 12E AND FULL SIZE CHARPY IMPACT SPECIMEN DATA.

ne.

Suct6on Streiner telenteIone NUREG/CR4370 BLOCKAGE f 6 USER'S MANUAL NUMEG/CR4629. VAllDATION OF TECTONIC MODELS FOR AN IN- NUREG/CR4371: DLOCKAGE 2.6 REFERENCE MANUAL TRAPLATE SEISMIC ZONE, CHARLESTON. SOUTH CAROLINA WITH GPS GEODETIC DATA. Surhoe Creek NUREQ/CR4462: THE SECOND INTERNATIONAL PlPING INTEGRrTY tovere Aceteent RE SEARCH GROUP (IPIRG.7) PROGRAM.Fmel Report NUREQ/CR 6433: CONTAINMENT PERFORMANCE OF PROTOTYPL CAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCL TLD DENT CONDITIONS. NURE04837 V16 NO3: NRC TLD DIRECT RADIATION MONITORING NUREGICR44e9 EXPERIMENTS TO INVESTIGATE DIRECT CON- NE'TWORK.Progrees Report July-Septemtaar 1996.

T AINME NT HEATING PHFNOMEM WITH BCALED MODELS OF THE NUREG4837 V16 N04. NRC TLD DIRECT RADLATION WONITORING CALVERT CLIF F S NUCLE AR PCMER PLANT. NETWORK. Progress Report OctoberCecember 1996.

l

$UID)DCtindeX 21 TPted teeinlese Insel PORATION MCM8 WILL&owce Metenal Lbenee No. BUA 917.Docest NUMG/OR4440 FRACTURE TOUGHNESS EVALUATIONS OF TP304 No. 40 H63 (Atee Caporoton) 8i AINLE64 8 TEEL PtPE8 NUREG/CR4624 ENVIRONMENTAL ABSEStMENT PRM.D U.

g CE RENEWAL OF NUCLEAR METALS.pc CONCORD, M ASSA-9 '

NUREGIOR4679 YAllOATION OF TECTON40 WODELS FOR AN IN-TRAPLATE SEISMoo ZONE,DMRLESTON.DOUTH CAROLINA WITH Vender inspeemen O

NURt.G4040 V70 NO3 LICENKE CONTRACTOR AND YENDOR IN-Therapeutie Aeneestremen SPECTION STATUS REPORT. Quernm9y ReporLJ48eploreet NUREG 1492. REGULATORY ANALYtat ON (RitERIA FOR THE RE. 1996.(Whmo Bots)

LEASE OF PATIENTS ADMNISTERED RADIOACTIVE NUREG4040 V20 N04. LICENKE CONTRACTOR AND VENDOR IN.

MATERLALFrel Report SPECTION STATUS REPORT, Ouwier1y ReportOctober Decenter 1996 (WNie Book)

NUREG483F V10 NO3. NRC TLD DIRECT RADIATION MONif0 RING Web Th6rFIIng Noe R NUREG/CR4466 REVliW OF INDUSTRY EFFORTS TO MANAGE 3 TION MONITORING

• NETWORK.Propees Report October Oscomber 1996 ACTOR E NOZZLE, PIPING, g

Ties Ust NUREGM40 V10 Nit:ifTLE LIST OF DOCUMENT 8 MADE PUBLICLY WW AVAIL.Attthereer 1 30 1996. NUMEG/CR4101 R01: A PILOT APPUCATION OF RISK INFORMED NURE04640 Vit Ntr. TITLi List OF DOCUMENTS MADE PUBLICLY METHODS TO ESTA8USH INKRVICE INBPECllON PRIORITIES AVAtLADL1 Deconder 1 31 1996 FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR NUREGC640 V10 N01: TITLd LIST OF DOCUMENTS MADE PUBLICLY POWER STATION AVAILABLE. January 13 t,19e7.

Wesenghouse APete IR 4164 PROCEEDINGS OF THE CNRA/C8NI WORKbHOP NUREG/CR4414. PIPING BENCHMARK PROBLEMS FOR THE WES-ON STEAM GENERATOR TUDE INTEGRfiY IN NUCLEAR POWER TNGHOUK N BTANDARNED W.

PLANTS. y, urentwn NUREG/CR 4613 N01: NRC HIGH-LEVEL RADIOACTIVE WASTE MAN.

NUREG 1632. FINAL TEO1NoCAL EVALUATION REPORT FOR THE AGEMENT PROGRAW ANNUAL PROGnESS REPORT: FISCAL YEAR PROPOKD REVISED RECLAMATp0N PLAN FOR THE Alus COR- 1996

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I NRC Originating Organization Index (Staff Reports)

This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by ma,or NRC organizations (e.g., program offices) and then by sub-sections of these (e.g., divis ons, 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.

OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) NUREG 1571: INFORMATION HANDBOOK ON INDEPENDENT REGION 1 (POST $20201) SPENT FUEL STORAGE INSTALLATIONS.

NUREG4637 Vit NOT NRC TLD DRECT RADIATION MONfTORING DVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST NUF E NWT D RA ION MONITORING N $62 DRFT FC STANDARD REVIEW PLAN FOR APPLICA-NETWORK.Progrene Report. October December 1996. TIONS FOR UCENSES TO DSTRIBUTE BYPRODUCT MATERIAL TO PERSONS EXEMPT FROM THE REQUIREMENTS FOR AN T 99 6) NRC LICENSE 10CFR Parts 30 14,30.16, 30.16.30.18.30,19 & 30.20, ULE & RCi 8 EV EW S 20 3 ^

NUHEG4936 Vt0 NO2 NRC REGULATORY AGEN Semiennual R N E M C STATEMENT TO DM N CONSTRUCT AND OPERATE THE CROWNPOINT URANIUM SO.

EDO . OFFICE OF THE CONT 710LLER 430418 & POST se030s) LUTION MINING PROJECT. CROWNPOINT. NEW MEXICO. Docket DIVISION OF BUDGET & ANALYSTS T 890205) No 40-8968 Resources. Inc )

NUREG-1100 V13 D'J0GET ESTI TES Flecal Year 1996. NUREG 1532: 1 AL TECHNICAL EVALUATION FIEPORT FOR THE PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS EDO . OFFICE POR ANALYSIS & EVALUATION OF OPERATIONAL CORPORATION MOAB MILLSource Metonal License No. SUA.

01 OF SAFETY PROGRAMS T 870413 NUREG 1275 Vit OPERATI EXPER NCE FEEDBACK EDO . OFHCE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

REPORT Asessement Of Spent Fuel Coonng Olvig E T g lONg 94g1 EDO . OFFICE OF INFORMAT10N RESOURCES MANAGEMENT & ARM COMMERICAL NUCLEAR POWER REACTORS AND OTHER (POST 841100) FACILITIES,1995. Twenty-E.ghth Annual Report OFFICE OF INFORMATION RESOURCES MAdAGEMENT (POST NUREG 1492: REGULATORY ANALYSIS ON CRITERIA FOR THE RE-8902061 LEASE OF PATIENTS ADMINISTERED RADIOACTIVE NUREG4304 V21 Not REGULATORY AND TECHNICAL REPORTS MATERIALFirsal Report (ABSTRACT INDEX JOURNAL). Compdation For Thrd Ouarter DIVtsiON OF SY0TEMS TECHNOLOGY (POST 941217) 1996. July-September. NUREG 1545: EVALUATION CRITERIA FOR COMMUNICATIONS-RE.

NUREG4540 V10 N11: TITLE LIST OF DOCUMENTS MADE PUBUG. LATED CORRECTIVE ACTION PLANS.

N EG 8 L 48 OF DOCUMENTS MADE PUBLIC. EDO . OFFICE OF NUCLEAR REACTOR REGULATION T 000420)

LV AVA.LABLE.Decorrber 131 te96 OFFICE OF NUCLEAR REACTOR REGULATION 941001)

NUREG4540 V19 Not: TITLE U$T OF DOCUMENTS MADE PUBUC- NUREG 0040 V20 NO3. UCENSEE CONTRACT AND VENDOR IN.

LY AVAILABLE. Anuary 1 31,1997, SPECTION STATUS REPORT. Quarterly Report. July-September NUREG4750 V44101: INDEXES TO NUCLEAR REGULATORY COS N W M Book)

MISSION ISSUANCES. September 1996. NUREG4040 V20 N04: UCENSEE CONTRACTOR AND VENDOR 4 NUREG4750 V44 NOS: N EAR REGULATORY COMMISSION IS. SPECTION STATUS REPORT. Quarterly ReportOctober December SUANCES FOR NOVEMBER 1996. Pages 229-314 NUREG4750 V44 N06: NUCLEAR REGULATORY COkWSSION IS. 1996 1021 NUREG (WtuteINT Book) OPERATOR ROS. LICENSING EXAMINATION SUANC 25 FOR DECEMBER 1996 Pa0ee 315 432. STANDARDS FOR POWER FIE ACTORS.

NUREG4 750 V45 N01; NUCLEAR REGULATORY COMMISSION IS. NUREG 1545: EVALUATION CRITERIA FOR COMMUNICATIONSRE.

SUANCFS FOR JANUARY 1997, Pages 147. ggD RECTf/E A ION PLA EDO . OFFICE OF NUCLF AR MATERIAL SAFETY & SAFEOUARDS ANTITRUST. Draft Repori For Comment.

OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG-1577 DRFT Fu STANDARD REVIEW PLAN ON POWER RE.

NUREG-1536 STANDARD REVirW PLAN FOR DRY SPENT FUEL ACTOR UCENSEE FINANCIAL OUAUFICATIONS AND DECOMMIS-STORAGE SYSTEMS, Final Report SiOMNG FUNDING ASSURANCE. Draft Report For Comment 1

23

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NRC Originating Organization index (International Agreements)

This index lists 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., dMslons, brancies) where appropriate. Each Gntry 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.

There were no NUREG/lA reports published this quarter.

i 25

NRC Contract Sponsor index (Contractor Reports)

This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically b,y major. NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) are3ared by that organi-z tion. if further information is needed, refer to the main citation by tie 9UREG/CR number.

EDO. OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR4433. CONTA!NMENT PERFORMANCE OF PROTOTYPl-DATA CAL FIEACTOR CONTAINMENTS SUBJECTED TO fr/ERE ACCl-DfvlSON OF SAFETY PROGRAMS (POST 870413) DENT CONDITONS NUREG/CR4456. REVIEW OF INDUSTRY EFFORTS TO MANAGE NURLG/CR4446: FRACTURE TOUGHNESS EVALUATONS OF PRESSURIZED WATER REACTOR FEEDWATER NOZZLE. PIP 240, TP304 STAINLESS STEEL PIPES.

AND FEEDRING CRACKING AND WALL THINNING. NUREG/CR4452; l'HE SECOND INTERNATONAL PIPING INTEGRI-TY RESEARCH GROUP (IPIRG 2) PROGRAM Final Report EDO. OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NvREG/CR4486. ASSESSMENT OF MODULAR CONSTRUCTON OfVtSION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST FOR SnFETY RELATED STRUCTURES AT ADVANCED NUCLEAR 870729) POWER PLANTS.

NOREG/CR4528. ENVIRONMENTAL ASSESSMENT PROPOSED L1- NUREG/CR4529. VAUDATION OF TECTONIC MODELS FOR AN IN-CENSE RENEWAL OF NUCLEAR METALS,1NC. CONCORD. MAS. TRAPLATE SEISMIC ZONE. CHARLESTON. SOUTH CAROLINA SACHUSETTS WITH GPS GEODETIC OATA.

OlVISON OF WASTE MANAGEMENT (NMSS 940403)

E i RY S POS 21g h/CR 44 vO6 HUREG/CR4513 N01: NRC HIGH LEVEL RADCACTIVE WASTE PROJECTS FOR NUCLEAR POWER PLANTS.

MANAGEMENT PROGRAM ANNUAL PROGRESS REPORT: NUREG/CR 6397: RADIATON SAFETY CONCERNS FOR PFIEG-FISCAL YEAR 1996.

NANT OR BREAST FEEDING PATIENTS.The Posihone Of The EDO = OPFICE OF NUCLEAR REGULATORY RESE ARCH (POST 820405) NUREG/ 4 3 ES TO THE HAND DURING THE ADMINIS-DIVISION OF ENGINEERING TECHNOLOGY (POST 941217) TRATON OF RADOLABELED ANTIBOO4ES CONTAINING Y 90,TC-NUREG/CR-4219 V12 N2; HEAVY-SECTON STEEL TECHNOLOGY 90M,l 131 AND LU 177.

, PROGRAM.Sermannual Progress Report For Ap1 1995 Through OlVILON OF 5YSTEMS TECHNCtOGY (POST 941217)

Septernber 1995 NUREG/CR4295: REASSESSMENT OF SELECTED FACTORS AF.

NUREG/CR.6181 Roi: A PILOT APPLICATION OF RISK INFORMED FECTING SITING OF NUCLEAR POWER PLANTS.

METHOOS TO ESTABLISH INSERVICE INSPECTON PRIORITIES NUREG/CR4469: EXPERIMENTS TO INVESTIGATE DIRf0T CON-FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR TAINMENT HEATING PHENOMENA WITH SCALED MO% S OF POWER STATION. THE CALVERT CUFFS NUCLEAR POWER PLANT.

NUREG/CR4370 liLOCKAGE 2.5 USER'S MANUAL NUREG/CR4474. PREUMINARY PHENOMENA IDENTIFICATION NUREG/CR4371 BLOCKAGE 2.8 REFERENCE MANUAL- AND RANKING TABLES (PIRT) FOR SBWR STARTUP STABluTY.

NUREG/CR4379. AN IMPROVED CORRELATION PROCEDURE FOR (MBS12E AND FULL SIZE CHARPY IMPACT SPECIMEN DATA EDO OFFICE OF NUCLEAR REACTOR REGULATION T 000428)

OFFICE OF NUCLEAR REACTOR r.20ULATION 941001)

NUREG/CR4389. 6PIRG-2 TASK 1. PIPE SYSTEM EXPERIME' NTS NUGEG/CR4393. INTEGRATED SYSTEM VAU TION: METHOOOL.

WITH CIRCUMFERENTIAL CRACKS IN STRAIGHT. PIPE OGY AND REVIEW CRITERIA.

LOCATONS. Final Reportsepternber 1991 Novernbor 1995.

NUREG/CR4400: HUMAN FACTORS ENGINEERING (HFE) IN- [

NUREG/CR 6426 V01: DUCTILE FRACTURE TOUGHNESS OF MODI- SIGHTS FOR ADVANCED REACTORS BASED UPON OPERATING i FIED A 302 GRADE B PLATE MATERIALS, DATA ANALYSIS. EXPERtENCE.

• NUREG/CFI4426 VD2; DUCTILE FRACTURE TOUGHNESS OF MODI- NUREQ/CR4414. PIPING BENCHMARK PROBLEMS FOR THE WES- i FIED A 302 GRADE B PLATE MATERIALS Deta Records. TINGHOUSE AP600 STANDARDIZED PLANT.

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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 needed, refer to the rnain citation by the NUREG/CR number.

ARGONNE NATIONAL LADORATORY EQE ENGlNEERING CONSULTANTS (FORMERLY EQE ENGlNEERING, NUREG/CP4154. PROCEEDINGS OF THE CNRA/CSNI WORKSHOP INC.)

ON STEAM GENERATOR TUBE INTEGRfTY IN NUCLEAR POWER NUREG/CR4433. CONTAINMEN1 MAFORMANCE OF PROTOTYPl.

PLANTS. CAL REACTOR CONTAINMENTS EUBJECTED TO SEVERE AOCl-BATTELLE MEMORIAL INSTITUTE. COLUMSUS LABORATORIES NOREG/CR4369' IPIRG-2 TASK 1 PIPE SYSTEM EXPERIMENTS IDAHO NATIONAL ENGlNEERING LAaORAWlY WITH CIRCUMFERENTIAL CRACKS IN STRAIGHT PIPE NUREG/CR4456: REVIEW OF INDUSTRY EFFORTS TO MANAGE LOCATIONS Final RepetSeptember 1991. November 1995. PRESSURIZED WATER REACTOR FEEDWATER NOZZLE, PIPING, NUREQ/CR4446: FRAuuRE TOUGHNESS EVALUATIONS OF TP304 AND FEEDRING CRACKING AND WALL THINNING.

STAINLESS STEEL PIPES.

NUREG/CR4452 THE SECOND INTERNATIONAL PlPING INTEGRITY MINNESOTA, UNIV. OF. MINNEAPOLit, MN RESEARCH GROUP (IPIRG-2) PROGRAM Final Report NUREG/CR4493: DOSES TO THE HAND DURING THE ADMINISTRA-TION OF RADOLADELED ANTIBODES CONTAINING Y 90.TC 99M,l-BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWLST 131 AND LU 177.

LADORATORY NOREG/CR-6181 R01: A PILOT APPUCATION OF RISK-INFORMED OAK RIDGE NATIONAL LA90RATORY METHODS TO ESTADUSH INSERVICE INSPECTION PRIORITIES NUREG/CR4219 V12 N2 HEAVY SECTION STEEL TECHNOLOGY FOR NUCLEAR COMPONENTS AT SURRY UNIT 1 NUCLEAR PROGRAM. Semiannual kgress Report For Apre 1995 Through Sep.

POWER STATION. tomber 1995.

NUREG/CR4379 AN IMPROVED CORRELATION PROCEDURE FOR BROOKHAVEN NATIONAL LABORATORY SUBS 17E AND FULL-SIZE CHARPY IMPACT SPECIMEN DATA.

NUREG/CP4157 V01: PROCEEDNGS OF THE TWENTYTOURTH NUREG/GR4426 V01: DUCTILE FRACTURE TOUGHNESS OF MOD-WATER REACTOR SAFETY INFORMATION MEETING. Plenary S**- FIED A 302 GRADE B PLATE MATERIALS. DATA ANALYSIS.

eson, H6gh Dumup Fuel. Conteenment And Structural A NUREG/CR4426 V02- DUCTILE FRACTURE TOUGHNESS OF MODI-NUREG/CP-0157 V02- PROCEEDNGS OF THE TY FOUHTH FIED A 302 GRADE B PLATE MATERIALS.Deta Records.

WATER REACTOR SAFETY INFORMATION MEETING Reactor Pres- NUREG/CR4526: ENYlRONMENTAL ASSESSMENT PROPOSED Ll-sure Vessel Embrtttlement And Thermal Anneshng, Reactor Vessel CEN3E RENEWAL OF NUCLEAR METALS,1NC, CONCORD, MASSA.

Lower Head Integrtty And Evaluation And Protection of Steam Genera- CHUSETTS.

tor tube ..-

NUREG/CP 0157 V03. #ROCEEDINGS OF THE TWENTY FOURTH SANDIA NATIONAL LADORATORIES WATER REACTOR SAFETY INFOhMATION MEETING.PRA And HRA. NUREG/CR4431 CONTAINMENT PERFORMANCE OF PROTOTYPI-And Probabdiste Seistruc Hazard Assessment And Seisme Satin 0 Crtte- CAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCl-na. DENT CONDITIONS.

NUREG/CR-4400 V06: DAT A BASE ON DOSE REDUCTION PROJECTS NUREG/CR S469: EXPERIMENTS TO INVESTIGATE DIRECT CON-FOR NUCLEAR POWER PLANTS. TAINMENT HEATING PHENOMENA WITH SCALED MODELS OF THE NOREG/CR4295. Rr ASSESSMENT OF SELECTED FACTORS AF- CALVERT CUFFS NUCLEAR POWER PLANT, FECTING SITING OF NUCLEAR POWER PLANTS.

NUREG/CR4393: INTEGRATED SYSTEM VAUDATION METHOOOLO" SARGENT & LUNDY. INC, GY AND REVIEW CRITERLA. NUREG/CR-6433; CONTAINMENT PERFORMANCE OF PROTOTYPI-NUREG/CR4397: RADIATION SAFETY CONCERNS FOR PREGNANT CAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCI-OR BREASTfEEDING PATIENTS.The Positions Of The NCRP And DENT CONDTIONS.

The ICRP.

NUREG/CH440& HUMAN FACTORS ENGINEERING (HrE) INSIGHTS SCIENCE & ENGlNEERING ASSOCIATES,INC.

FOR ADVANCED REACTORS BASED UPON OPERAlfNG EXPERI- NUREG/CR4370 BLOCKAGE 2.5 USER'S MANUAL ENCE. NUREG/CR4371: BLOCKAGE 2.5 REFERENCE MANUAL NUREG/CR 6414: PIPING BENCHMARK PROBLEMS FOR THE WES-TINGHOUSE ape 00 STANDARDt2ED PLANT. SCIENCE APPUCATIONS INTERNATIONAL CORP.(FORMERLY NUREG/CR4474. PREUMINARY PHENOMENA IDENTIFICATION AND SCIENCE APPUCATIONS, RANKING TADLES (PIRT) FOR SBWR STARTUP STADIUTY. NUREG-0713 V17: OCCUPATIONAL RADLATION EXPOSURE AT COM.

NUREG/CR-6486: ASSESSMENT OF MODULAR CONSTRUCTION FOR MERICAL NUCLEAR FOWER REACTORS AND OTHER SAFETY RELATED STRUCTURES AT ADVANCED NUCLEAR FACILITIES 1995. Twenty-Eighth Annual Report POWER PLANTS.

NUREG/CR 6493 DOSES TO THE HAND DURING THE ADMINISTRA- SOFTWARE EDGE,INC.,

TION OF RADIOLABELED ANTIBODIES CONTAINING Y 90,TC-99M,l- NUREG/CR4370 BLOCKAGE 2.5 USER'S MANUAL 131, AND LU 177. NUREG/CR4371: BLOCKAGE 2.5 REFEF ENCE MANUAL CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES SOUTH CAROUNA, UNIV. OF, COLUMSIA. SC NUREG/CR4513 N01: NRC HIGH. LEVEL RADIOACTIVE WASTE MAN- NUREG/CR4529 VAUDATION OF TECTONIC MODELS FOR AN IN-AGEMENT PROGRAM ANNUAt, PROGRESS REPORT: FISCAL YEAR TRAPLATE SEISMIC ZONE, CHARLESTON, SOUTH CAROUNA WITH 1996. GPS GEODETIC DATA.

29

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 per-1orming organization are the NUREG/lA numbers and titles of their reports. If further infor-mation is needed, refer to the main citation by the NUREG/lA number.

There were no NUREG/l A reports published this quarter.

31

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Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in' alphabetical order. They are preceded by their Docket number cnd followed by the report number. If further information is needed, refer to the main citation by the NUREG number.

$M03 AP900 Standwd Plert % Wesanghouse NUREGO4414 W il Cawt CWts Ntteer Power Piert, unt 2, NUREG O 4400 3 Cans Power Plant, Uni 1 NURE

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. vastst u ievaa nea Regulatory and Technical Reports (Abstract Index Journal)

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Publications Branch Office of Information Resources Management U.S. Nuclear Regulatory Commission Washington, DC 20555 - 0001 S

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