ML20093N745

Regulatory and Technical Reports (Abstract Index Journal). Compilation for Second Quarter 1995,April-June

ML20093N745
Person / Time
Issue date:	09/30/1995
From:	NRC OFFICE OF ADMINISTRATION (ADM)
To:
References
NUREG-0304, NUREG-0304-V20-N02, NUREG-304, NUREG-304-V20-N2, NUDOCS 9510270358
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Vol. 20, No. 2 l Regulatory and Technical Reports

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Compilation for Second Quarter 1995 April - June f

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AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:

1.

The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2.

The Superintendent of Documents U.S. Government Printing Office, P. O. Box 37082, Washington, DC 20402-9328 3.

The National Technical information Service, Springfield, VA 22161-0002 l

Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence: Commission papers; and applicant and licensee docu-ments and correspondence.

The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-2 ceedings, international agreement reports, grantee reports, and NRC booklets and bro-chures, Also available are regulatory guides, NRC regulations in the Code of Federal Regula-tions, and Nuclear Regulatory Commission Issuances.

Documents available from the National Technical information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the g

Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission, j

Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Rog/ ster notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries.

Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-ference proceedings are available for purchase from the organization sponsoring the publica-tion cited.

Single copies of NRC draft reports are available free, to the extent of supply, upon writtan request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

Copies 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-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the orininating organization or, if they are American National Standards, from the American National Standards Institute,1430 Broadway, New York, NY 10018-3308.

A year's subscription of this report consists of four quarterly issues.

i NUREG-0304 i

Vol. 20, No. 2 l

Regulatory and Technical Reports j

(Abstract Index Journal) i i

Compilation for Second Quarter 1995 April-June Date Published: September 1995 i

i Publications Branch Division of Reedom ofInformation and Publications Services Office of Administration U.S. Nuclear Regulatory Commission

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r CONTENTS Preface............................................

Y Index a

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. Main Citations and Abstracts........................................................... 1 e Staff Reports e Conference Proceedings e CortractorReports e Grant Reports e international Agreement Reports Secondary Report Number Index....................................................... 2 j

Personal Author index................................................................ 3 Subject index......................................................

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

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NRC Originating Organization hxlex (International Agreements)............................. 6 NRC Contract Sponsor Index (Contractor Reports)....................................... 7 Contractor index..................................................................... 8 Intemational Organization Index......................................................... 9 Licensed Facility index............................................................ 10

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PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports j

issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors it is NRC's intention to j

publish this compilation quarterly and to cumulate it annually. Your comments will be appreciated. Please send i

them to:

Technical Publications Section Publications Branch Division of Freedom of Information i

and Publications Services T6 E7 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 l

The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-)000(,

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- NUREG/CP-)000(, NUREG/CR-)000(, and NUREG/lA-)000(. These precede the following indexes:

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j Secondary Report Number index Personal Authorindex Subject index NRC Originating Organization Index (Staff Reports)

NRC Originating Organization index (Intemational Agreements)

NRC Contract Sponsor index (Contractor Reports) j Contractorindex Intemational Organization index

. Licensed Facility index i

A detailed explanation of the entries precedes each index.

The bibliographic elements of the main citations are the following:

Staff Report NUREG-0806. MARK 11 CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA.

ANDERSON, 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 i

report was published, (6) number of pages in the report, (7) the NRC Document Control System accession l

number, (8) the microfiche address (for intemal NRC use).

Conference Report l

NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND REUABILITY ENGINEERING IN NUCLEAR REGULATION. JANERP, J.S. Argonne National Laboratory. May 1981.141 pp.

8105280299. ANL-81-3. 08632:070.

l 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 Control System accession number, (8) the report number of the originating rA ganization, (9) the microfiche address (for NRC Intemal use).

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

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 Control Sys-tem accession number, (8) the report number of the originating organization (if given), (9) the microfiche ad-dress (for NRC intamal use).

Grant Report i

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

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 Control Sys-tem accession number, (8) the report number of the originating organization (if given), (9) the microfiche ad-i dress (for NRC intemal use).

Intemational Agreement Report NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA.

NEUMANN, U. Kraftweek Union. August 1086. 223 pp. 8608270424. 37659:138.

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 accession number, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC i

internal use).

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

ADD

- addendum APP

- appendix DRFT - draft ERR

- errata N - number i

R - revision S - supplement V - volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Govemment Printing Office (GPO) or from the NationalTechnical lnformation Service, Springfield, Virginia 22161. To purchase documents from the GPO, send a check or money order, payable to the Superintendent of Documents, to the following address:

Superintendent of Documents U.S. Govemment 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 advance either by infomational Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.

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NRC Report Codes The NUREG designation, NUREG-XXXX, Indicates that the document is a formal NRC staff-generated report.

Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX This type of identification replaces contractor-established codes such as ORNUNUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship or the work being reported.

In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-spon:cied conference pro-ceedings NUREG/GR is used for NRC grant reports, and NUREG/lA is used for intemational agreement reports.

All these report codes are controlled and assigned by the staff of the Technical Publications Section of the NRC DMelon of Freedom of Information and Publications Services.

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b Main Citations and Abstracts

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The report listings in this compilation are arranged by report number, where NUREG-XXXX is cn NRC staff-onginated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CR-XXXX is an NRC contractor-prepared report, and NUREG/lA-XXXX is an inter-national agreement report. The bibliogiaphic information (see Preface for details) is followed by a brief abstract of this report, NUREG-0020 V19: LICENSED OPERATING REACTORS STATUS (SAMDAs) and concluded that none of the SAMDAs, beyond

SUMMARY

REPORT. Data As Of December 31, 1994.(Gray the three procedural changes that the applicant committed to Book 1) HARTFIELD.R.A. Office of Information Resources Man-implement, would be cost-beneficial for further matigating envi-agement (Post 890205). April 1995. 350pp. 9504260255.

ronmental impacts.

83635:001.

The Nuclear Regulatory CommisLon's annual summary of li-NUREG-0540 V17 NO2: TITLE LIST OF DOCUMENTS MADE consed nuclear power reactor data is based primarity on the PUBLICLY AVAILABLE. February 1-28,1995.* Division of Free-report of operating data submitted by licensees for each unit for dom of information & Publications Services (Post 940714). April the month of December becasse that report contains data for 1995. 337pp. 9504250369. 83629.001.

the month of December, the year to date (in this case calendar This document is a monthly publication containing descrip-year 1994) and cumulative dsta, usually from the date of com-tions of information received and generated by the U.S. Nuclear mercial operation. The data is not independently venfied, but Regulatory Commission (NAC). This information includes (1) various computer checks are made, The report is divided into docketed material associated with civilian nuclear power plants two sections. The first contains summary highlights and the and other uses of radioactive materials, and (2) nondocketed second contains data on each individual unit in commercial op-material received and generated by NRC pertinent to its role as eration Secten 1 capacity and availability factors are simple a regulatory agency. The following indexes are included: Per-anthmetic averages. Section 2 items in the cumulative column sonal Author, Corporate Source, Report Number, and Cross are generally as reported by the licensee and notes as to the Reference of Enclosures to Principal Documents.

use of weighted averages and starting dates other than com-NUREG 0540 V17 N03: TITLE LIST OF DOCUMENTS MADE mercial operation are provided.

PUBLICLY AVAILABLE. March 1-31, 1995.

• Division of Free-NUREG-0040 V19 N01: LICENSEE CONTRACTOR AND dom of information & Publications Services (Post 940714). May VENDOR INSPECTION STATUS REPORT. Quarterly 1995. 360pp. 9506020497. 84148:024.

Report. January-March 1995.(White Book)

• Office of Nuclear See NUREG-0540,V17,N02 abstract.

Reactor Regulation (Post 941001). May 1995. 119pp.

9506020502. 84149:041.

NUREG-0540 V17 N04: TITLE LIST OF DOCUMENTS MADE This periodical covers the results of inspections performed by PUBLICLY AVAILABLE. Apnl 1 30, 1995.

• Division of Freedom the NRC's Special inspection Branch, Vendor inspection Sec-of Information & Publications Services (Post 940714). June tion, that have been distnbuted to the inspected organizations 1995. 207pp. 9506280447. 84468:129.

dunng the period from January through March 1995.

See NUREG-0540,V17,N02 abstract.

NUREG-0498 S01: FINAL ENVIRONMENTAL STATEMENT RE-NUREG-0725 R10: PUBLIC INFORMATION CIRCULAR FOR LATED TO THE OPERATION OF WATTS BAR NUCLEAR SHIPMENTS OF IRRADIATED REACTOR FUEL.

• Division of PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50-391 ('len" Industrial & Medical Nuclear Safety (Post 870729). April 1995.

nessee Valley Authority)

• Associate Director for Advanced Re-30pp. 9505180571. 83980:001.

actors & License Renewal (ADAR) (Post 941001). April 1995.

This circular has been prepared to provide information on the 366pp. 9505180344. 83965:118.

shipment of irradiated reactor fuel (spent fuel) subject to regula-The Final Environmental Statement (ITS) is sisd in 1978 rep-Lon by the Nuclear Regulatory Commission (NRC), and to meet resents the Nuclear Regulatory Commtsion's (NRC's) previous the requirements of Public Law 96-295. The report provides a environmental review related to the operett:,n of Watts Bar Nu-brief desenption of NRC authonty for certain aspects of trans-clear (WBN) Plant. The purpose of this NRL review is to dis-porting spent fuel. It provides desenptive stat:stics on spent fuel cuss the effects of observed changes in erwironment and tc shipments regulated by the NRC from 1979 to 1994. It also lists evaluate the changes in environmental impacts that Nye oc detailed highway and railway segments used within each state curred as a result of changes in the WBN Plant design ano f,r from January 1,1993, through December 31,1994.

posed methods of operations since the last environmental review. A full scope of environmental topics has been evaluat-NUREG-0750 V41101: INDEXES TO NUCLEAR REGULATORY ed, including regional demography, land and water use, meteor-COMMISSION ISSUANCES. January. March 1995.

• Division of ology, terrestnal and aquatic ecology, radiological and nonradio-Freedom of information & Publications Services (Post 940714).

logical impacts on humans and the environment, socioeconomic June 1995. 34pp. 9507060350. 84533:306.

impacts, and environmental justice. The staff concluded that Digests and indexes for issuances of the Commission, the there are no significant changes in the environmental impacts Atomic Safety and Licensing Board Panel, The Administrative since the NRC 1978 FES OL from changos in plant design, pro-Law Judges, the Directors' Decisions, and the Decisions on Pe-posed methods of operation, or changes in the environment.

titions for Rulemaking are presented.

The applicant's preoperational and operational monitonng pro-grams were reviewed and found to be appropnate for establish-NUREG-0750 V41 NO2: NUCLEAR REGULATORY COMMISSION ing baseline conditions and ongoing assessments of environ-ISSUANCES FOR FEBRUARY 1995. Pages71-178.

• Division mental impacts. The staff also conducted en anafysis of plant of Freedom of Information & Publications Services (Post operation with severe accioent mitigation design a ternatives 940714). May 1995.115pp. 9505230100. 84017:107, s

1

2 Main Citations and Abstracts Legalissuances of the Commission, the Atomic Safety and Li-NUREG-0940 Vid N1 P2: ENFORCEMENT ACTIONS: SICNIFI-censing Board Panel, the Administrative Law Judges, and NRC CANT ACTIONS RESOLVED, MEDICAL LICENSEES.Ouanerly Program Offces are presented.

Progren ReportJanuary-March 1995.

• Ofc of Enforcement (Post 870413). May 1995. 300pp. 9506140141,84301:001.

NUREG-0750 V41 NO3: NUCLEAR REGULATORY COMMISSION This compilabon summarizes signsfacant enforcement actions ISSUANCES FOR MARCH 1995.Pages 179-243.

• Division of that have been resohred dunng one quarterty penod (January -

Freedom of Information & Pubhcations Services (Post 940714).

March 1995) and includes copies of letters, Notices, and Orders May 1995. 72pp. 9506140062. 84297:130.

sent by the Nuclear Regulatory Commission to medical licens.

See NUREG-0750,V41,N02 abstract.

ee:: with respect to these enforcement actions. It is anticipated that the information in this publicatbn will be widely disseminat-NUREG-0750 V41 N04: NUCLEAR REGULATORY COMMISSION ed to managers and employees sogaged in activities licensed ISSUANCES FOR APRIL 1995.Pages 245 319.

• Division of by the NRC, so that actions can be taken to improve safety by Freodom of Information & Publications Services (Post 940714).

avoiding future violations simihr to those described in this publi-June 1995. 83pp. 9507120290. 84633:001.

cation.

See NUREG 0750,V41,N02 abstract.

NUREG-0940 V14 N1 P3: ENFORCEMENT ACTIONS: SIGNIFl-NUREG-0837 V15 N01: NRC TLD DIRECT RADIATION MONI-CANT ACTIONS RESOLVED, MATERIAL LICENSEES (NON-TORING NETWORK. Progress Report. January-March 1995.

MEDICAL) Ouarterly Progress Report. January-March 1995.

• STRUCKMEYER,R. Region 1 (Post 820201). May 1995. 230pp.

Ofc of Enforcement (Post 870413). May 1995. 430pp.

9506140060. 84298:001.

9506160045. 84331:306.

This report provides the status and results of the NRC Ther-This compilation summarizes significant enforcement actions moluminescent Dosimeter (TLD) Direct Radiation Monitonng that have been resolved during one quarterfy period (January -

Network. It presents the radiation levels measured in the vicinity March 1995) and includes copies of letters, Notees, and Orders of NRC licensed facilities throughout the country for the first sent by the Nuclear Regulatory Commission to Material Licens-quarter of 1995.

ees (non-Medical) with respect to these enforcement actions. It is anticipated that the information in this publication will be NUREG-0847 S15: SAFETY EVALUATION REPORT RELATED widely disseminated to managers and employees engaged in TO THE OPERATION OF WATTS BAR NUCLEAR activities ficensed by the NRC, so that actions can be taken to PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50 391.(Ten-improve safety by avoiding future violations similar to those de-nessee Valley Authority) TAM.P.S. Division of Reactor Projects scribed in this publication.

1/II (DRPE) Post 941001). June 1995,189pp. 9507120275.

84634:001.

NUREG-1125 V16: A COMPILATION OF REPORTS OF THE AD-Supplement No 15 to the Safety Evaluation Report for the VISORY COMMITTEE ON REACTOR SAFEGUARDS.1994 apphcation filed by the Tennessee Val:ey Authonty for hcense to Annual.

• ACRS - Advisory Committee on Reactor Safeguards.

operate Watts Bar Nuclear Plant Units 1 and 2 Docket Nos.

Apnl 1995.115pp. 9505190009. 83980:082.

50-390 and 50-391, located in Rhea County Tennessee, has This compilation contains 30 ACRS reports submitted to the been prepared by the Office of Nuclear Reactor Regulation of Commission, or to the Executive Director for Operations, during the Nuclear Regulatory Commission. The purpose of this sup-calendar year 1994. It also includes a report to the Congress on plement is to update the Safety Evaluation with (1) additional in-the NRC Safety Research Program. All reports have been made formation submitted by the applicant since Supplement No.14 available to the public through the NRC Public Document Room was issued, and (2) matters that the staff had under review and the U.S. Library of Congress. The reports are categorized when Supplement No.14 was issued.

by the most appropnate generic subject area and by chronologi-NUREG-0933 S18: A PRIORITIZATION OF GENERIC SAFETY ISSUES. EMRIT,R. Division of Engineenng Technology (Post NUREG-1275 VII: OPERATING EXPERIENCE FEEDBACK 941217). April 1995. 266pp. 9505190010. 83981:001.

REPORT - TURBINE-GENERATOR OVERSPEED PROTEC.

The report presents the safety prionty ranking for genenc TION SYSTEM Commercial Power Reactors. ORNSTEIN,H.L.

safety issues related to nuclear power plants. The purpose of Division of Safety Programs (Post 870413). April 1995.117pp.

these rankings is to assist in the timely and efficient allocation 9505180319. 83965:001.

of NRC resources for the resolution of those safety issues that The report presents the results of the U.S. Nuclear Regula-have a significant potential for reducing nsk. The safety pnonty tory Commission's Office for Analysis and Evaluation of Oper-rankings are HIGH, MEDIUM, LOW, and DROP, and have been ational Data (AEOD) review of operating expenence of main tur-assigned on the basis of risk significance estimates, the ratio of bine. generator overspeed and overspeed protection systems.

risk to costs and other impacts estimated to result af resolution AEOD's study provides insight into the shortcomings in the of the safety issues were implemented, and the consideration of design, operation, maintenance, testing, and human factors as-uncertainties and other quantitative or quahtative factors. To the sociated with turbine overspeed protection systems. It includes extent practical, estimates are quantitative.

an indepth examination of the turbine overspeed event that oc-curred on November 9,1991, at the Salem Unit 2 Nuclear NUREG-0940 V14 N1 P1: ENFORCEMENT ACTIONS: SIGNIFI-Power Plant. It also provides information concerning actions CANT ACTIONS RESOLVED, REACTOR LICENSEES.Ouarterly taken by other utilities and the turbine manufacturers as a result Progress Report. January. March 1995.

• Ofc of Enforcement of the Salem overspeed event. AEOD's study reviewed operat-(Post 870413). May 1995. 360pp. 9506160009. 84333:017.

ing procedures and plant practices. It noted differences be-This compilation summanzes significant enforcement actions tween turbine manufacturer designs and recommendations for that have been resolved during one quarterly penod (January -

operations, maintenance, and testing, and also identrfied signifi-March 1995) and includes copies of letters, Notices, and Orders cant variations in the manner that individual plants maintain and sent by the Nuclear Regulatory Commission to reactor hcens-test their turbine overspeed protection systems.

eos with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminat-NUREG-1280 R01: STANDARD FORMAT AND CONTENT AC-ed to managers and employees engaged in activities licensed CEPTANCE CRITERIA FOR THE MATERIAL CONTROL AND by the NRC, so that actions can be taken to improve safety by ACCOUNTING (MC&A) REFORM AMENDMENT.

• Division of avoiding future violations similar to those described in this publi-Fuel Cycle Safety & Safeguards (Post 930207). April 1995.

cation.

119pp. 9505180530. 83968 001.

Main Citations and Abstracts 3

in 1987 the NRC revised the matenal control and accounting tute (NEI). The improved STS were developed based on the cri-requirements for NRC licensees authorized to possess and use tena in the Final Commission Policy Statement on Technical a formula quantity (i.e.,5 formula kilograms or more) of stratege Specifcations improvements for Nuclear Power Reactors, dated special nuclear material. Those revisions issued as 10CFR July 22,1993. The improved STS will be used as the basis for 47.51 59 require timely monitoring of irFprocess inventory and individual nuclear power plant licensees to develop improved 1

discrete items to detect anomalies potential'y indcative of mate-plant-specific technical specifications. This report contains three rial losses. Timely detection and enhanced loss localizaten ca-volumes. Volume 1 contains the Specifications for all chapters pabilities are beneficial to alarm resoluton and also for matenal and sections of the improved STS. Volume 2 contains the recovery in the event of an actual loss. NUREG 1280 was Bases for Chapters 2.0 and 3.0, and Sections 3.1 - 3.3 of the issued in 1987 to present enteria that could be used by appli-improved STS. Volume 3 contains the Bases for Sections 3.4 -

cants, Icensees, and NRC hcense reviewers in the initial prepa-3.9 of the improved STS.

ration and subsequent review of fundamental nuclear material NURE41430 V02 Rot: STANDARD TECHNICAL SPECIFICA.

control (FNMC) plans submitted in response to the Reform TIONS BABCOCK AND WILCOX PLANTS. Bases (Sections 2.0 Amendment. This document is also e,ntended for both licensees 3.3).

• Office of Nuclear Reactor Regulation (Post 941001).

rnd license reviewers with respect to FNMC plan revisions.

Apnl 1995 300pp. 9506220131. 84396:001.

General performance objectives, system capabilities, process See NUREG-1430,V01,R01 abstract.

monitoring, item monitoring, alarm resolution, quality assurance, and accounting are addressed. This revision to NUREG-1280 is NUREG-1430 V03 RO1: STANDARD TECHNICAL SPECIFICA.

cn expansion of the initial edition, which clanfies and expands TIONS BABCOCK AND WILCOX PLANTS. Bases (Sections 3.4 upon several topics and addresses assues identified under 3.9).

• Office of Nuclear Reactor Regulation (Post 941001).

Reform Amendment implementation experience.

April 1995. 350pp. 9506220136. 84396:302.

NUREG-1350 V07: NUCLEAR REGULATORY COMMISSION IN-See NUREG-1430,V01.R01 abstract.

FORMATION DIGEST.1995 Edition. STADLER,L. Division of NUREG 1431 V01 R01: STANDARD TECHNICAL SPECIFICA-Budget & Analysis (Post 890205). March 1995. 67pp-TIONS WESTINGHOUSE PLANTS. Specifcations.

• Office of 9505230149. 84017:040.

Nuclear Reactor Regulation (Post 941001). April 1995. 350pp.

The Nuclear Regulatory Commission Information Digest 9506280476. 84456:001.

(digest) provides a summary of information about the U.S. Nu-This report documents the results of the combined effort of clear Regulatory Commission (NRC), NRC's regulatory responsi-the NRC and the industry to produce improved Standard Tech-bilities, the activities NRC licenses, and general information on nical Specifcatons (STS), Revision 1 for Westinghouse Plants, domeste and worldwide nuclear energy. The digest, published The changes reflected in Revisor' 1 resulted from the experi-convally, is a compilation of nuclear and NRC-related data and ence gained from license amendment applications to convert to b designed to provide a quick reference to major facts about these improved STS or to adopt partial improvements to exist-the agency and the industry it regulates. In general, the data ing technical specifications. This report is the result of extensive cover 1975 through 1993, with exceptions noted. information on public technical meetings and discussions between the Nuclear generating capacity and average capacity factor for operating Regulatory Commission (NRC) staff and vanous nuclear power U.S. commercial nuclear power reactors is obtained from plant licensees, Nuclear Steam Supply System (NSSS) Owners monthly operating reports that are submitted directly to the NRC Groups, NSSS vendors, and the Nuclear Energy Institute (NEI).

by the licensee. This information is reviewed by the NRC for The improved STS were developed based on the enteria in the consistency only and no independent validation and/or venfca-Final Commission Polcy Statement on Technical Specifications tion is performed.

Improvements for Nuclear Power Reactors, dated July 22,1993.

NUREG-1415 V07 N02: OFFICE OF THE INSPECTOR The improved STS will be used as the basis for individual nucle-GENERAL. Semiannual Report To Congress, October 1,1994 ar power plant licensees to develop improved plant-specific March 31,1995. BARCHI,T.; NORTON,L.; GRODIN,M.; et al.

technical specifications. This report contains three volumes.

Offee of the inspector General (Post 890417). June 1995.

Volume 1 contains the Specificatons for all chapters and sec-50pp. 9506220103. 84394:337.

tions of the improved STS. Volume 2 contains the Bases for The inspector General is required by the Inspector General Chapters 2.0 and 3.0, and Sections 3.1 - 3.3 of the improved Act of 1978, as amended. to prepare a " Semiannual Report" to STS. Volume 3 contains the Bases for Sections 3.4 3.9 of the the U.S. Congress that summan2es program activities. The 6 improved STS.

month reporting pered ends March 31 and September 30. The NUREG-1431 V02 Rot: STANDARD TECHNICAL SPECIFICA.

Inspector General's report is submitted to the Chairman of the TiONS WESTINGHOUSE PLANTS. Bases (Sections 2.0 - 3.3).

• NRC not later than April 30 and October 31, respectively. The Office of Nuclear Reactor Regulation (Post P41001). April 1995.

Chairman comtrysnts on the inspector General's report and pre-350pp. 9506280489. 84458:001, pares his own, as required by the Act, and submits both reports See NUREG 1431,V01,R01 abstract.

to Congress no later than November 30 and May 31, respec-tively.

NUREG-1431 V03 R01: STANDARD TECHNICAL SPECIFICA-TIONS WESTINGHOUSE PLANTS. Bases (Sections 3.4 - 3.9).

• NUREG-1430 VD1 Rot: STANDARD TECHNICAL SPECIFICA-Offee of Nuclear Reactor Regulation (Post 941001). April 1995.

TIONS BABCOCK AND WILCOX PLANTS. Specifcations.

500pp. 9506280506. 84459:001.

Offee of Nuclear Reactor Regulation (Post 941001). April 1995.

See NUREG-1431,V01,R01 abstract.

326pp. 9506220126. 84395.027.

This report documents the results of the combined effort of NUREG-1432 V01 R01: STANDARD TECHNICAL SPECIFICA-the NRC and the industry to produce improved Standard Tech-TlONS COMBUSTION ENGINEERING PLANTS.Specif~ atons.

c ncal Specifcations (STS), Revision 1 for Babcock & Wilcox

• Office of Nuclear Reactor Regulation (Post 941001). April Plants. The changes reflected in Revision 1 resulted from the 1995. 442pp. 9506220142. 84397:326.

cxpenence gained from Icense amendmant appleatens to con-This report documents the resuns of the Combined effort of vert to these improved STS or to adopt partial improvements to the NRC and the industry to produce improved Standard Tech-cxisting technical specificatons. This NUREG is the result of ex-nical Specifcations (STS), Revision 1 for Combustion Engineer-tensive public techncal meetings and discussions between the ing Plants. The changes reflected in Revision 1 resulted from Nuclear Regulatory Commission (NRC) staff and varous nuclear the expenence gained from license amendment applications to power plant lecasees, Nuclear Steam Supply System (NSSS) convert to these improved STS or to adopt partiel improve-Owners Groups, NSSS vendors, and the Nuclear Energy Insti-ments to existing techncal specificatons. This report is the

i 4

Main Citations and Abstracts result of extensive pubic techncal meetings and discussions from the expenence gained from license amendment applica-between the Nuclear Regulatory Commission (NRC) staff and tions to convert to these improved STS or to adopt partial im-vanous nuclear power plant hcensees Nuclear Steam Supply provements to ensting technical specificatons. This report is System (NSSS) Owners Groups. NSSS vendors, and the Nucle-the result of extensive pubic techrucal meetings and discus-ar Energy Institute (NEI). The improved STS were developed sions between the Nuclear Regulatory Commission (NRC) staff based on the enteria in the Final Commission Policy Statement and various nuclear power plant licensees, Nuclear Steam on Technical Specifications improvements for Nuclear Power Supply System (NSSS) Owners Groups NSSS vendors, and the Reactors, dated July 22,1993. The improved STS will be used Nuclear Energy institute (NEI). The improved STS were devel-as the bases for individual nuclear power plant Icensees to de-oped based on the criteria in the Final Commission Policy State.

velop improved plant. specifc technical specifications. This ment on Technical Specificatons improvements for Nuclear report contains three volumes. Volume 1 contains the Specifica-Power Reactors, dated July 22,1993. The improved STS will be tions for all chapters and sections of the improved STS. Volume used as the basis for individual nuclear power plant licensees to 2 contains the Bases for Chapters 2.0 and 3.0, and Sections develop improved plant-specifc technical specifications. This 3.1 3.3 of the improved STS. Volume 3 contains the Bases for report contains three volumes. Volume 1 contains the Specifca-Sections 3.4 - 3.9 of the improved STS.

tions for all chapters and sections of the improved STS. Volume 2 contains the Bases nor Chapters 2.0 and 3.0, and Sections NUREG-1432 V02 Rot: STANDARD TECHNICAL SPECIFICA, 3.1 - 3.3 of the iroproved STS. Volume 3 contains the Bases for TlONS COMBUSTION ENGINEERING PLANTS Bases (Sec-Sections 3.4 - 3.10 of the improved STS.

tions 2.0 - 3.3).

• Offee of Nuclear Reactor Regulation (Post 941001). April 1995. 450pp. 9506220171. 84399:040.

NUREG-1434 V02 R01: STANDARD TECHNICAL SPECIFICA.

See NUREG 1432,V01,R01 abstract.

TIONS GENERAL ELECTRIC PLANTS, BWR/6. Bases (Sections NUREG-1432 V03 R01: STANDARD TECHNICAL SPECIFICA-2.0 - 3.3).

• Office of Nuclea. Reactor Regulation (Post

+

TiONS COMBUSTION ENGINEERING PLANTS. Bases (Sec.

941001). April 1995. 356pp. 9506290228, 84464:059.

tions 3.4 - 3 9).

• Office of Nuclear Reactor Regulation (Post See NUREG 1434,V01,R01 abstract.

941001). April 1995. 602pp. 9506220172. 84400:126.

NUREG-1434 V03 301: STANDARD TECHNICAL SPECIFICA-See NUREG 1432,V01,R01 abstract.

TIONS GENERAL ELECTRIC PLANTS, BWR/6. Bases 3.4 -

NUREG 1433 V01 R01: STANDARD TECHNICAL SPECIFICA-3.10).

• Office of Nuclear Reactor Regulation (Post 941001).

TIONS GENERAL ELECTRIC PLANTS BWR/4. Specifications.

• April 1995. 444pp. 9506290230. 84467:049.

Office of Nuclear Reactor Regulation (Post 941001). April 1995.

See NUREG-1434,V01,R01 abstract.

388pp. 9506290155. 84461:001.

This report documents the results of the combined effort of NUREG-1470 V04: FINANCIAL STATEMENT FOR FISCAL YEAR the NRC and the industry to produce improved Standard Tech-1994.

• Offee of the Controller (Post 890205). March 1995.

neal Specifcations (STS), Revision 1 for General Electric 84pp. 9505180277. 83967:148 BWR/4 Plants. The changes reflected in Revision 1 resulted The Chief Financial Officer's Act of 1990 requires the NRC from the experience gained from heense amendment appica.

Chief Financial Officer to prepare end submit an annual financial tions to convert to the. irporoved STS or to adopt partial im-statement to the Director of the Office of Management and provements to existing technical specifications. This report is Budget (OMB). The OMB has replaced the requirement for the the result of extensive pubic technical meetings and discus-CFO's Annual Report with the annual financial statement. The sions between the Nuclear Regulatory Commission (NRC) staff annual financial statement was previously included in the Chief and vanous nuclear power plant licensees, Nuclear Steam Financial Officer's Annual Report. This report is the fourth Supply System (NSSS) Ownars Groups, NSSS vendors, and the annual report for the NRC and includes an overview of the Nuclear Energy institute (NEI). The improved STS were devel-NRC, the audited principal f.nancial statements and audit re-l i

oped based on the entena in the Final Commission Pokey State-ports for fiscal year 1994, and supplemental financial and man-ment on Technical Specifcations improvements for Nuclear agement information.

Power Reactors, dated July 22,1993. The improved STS will be NUREG-1478 R01: NON-POWER REACTOR OPERATOR LI-used as the basis for individual nuclear power plant beensees to CENSING EXAMif'ER STANDARDS.

• Offee of Nuclear Reac-3 develop improved plant-specific technical specifcations. This report contains three volumes. Volume 1 contains the Specifica.

tor Regulation (Pos, 941001). June 1995.172pp. 9507060351.

84533:100.

tions for all chapters and sections of the improved STS. Volume The Non-Power Reactor Operator Licensing Examiner Stand-2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1 - 3.3 of the improved STS. Volume 3 contains the Bases for ards provide policy and guidance to NRC examiners and estab-hsh the procedures and practices for examining licensees and Sections 3.4 3.10 of the improved STS.

applicants for NRC operator heenses pursuant to Part 55 of NUREG-1433 V02 R01: STANDARD TECHNICAL SPECIFICA-Title 10 of the Code of Federal Regulations (10 CFR Part 55).

TIONS GENERAL ELECTRIC PLANTS BWR/4. Bases (Sections They are intended to assist NRC examiners and facihty hcens-2.0 3.3).

Offee of Nuclear Reactor Regulation (Post ees to better understand the examination process and to 941001). Apnl 1995. 338pp. 9506290159. 84462:025.

ensure the equitable and consistent administration of examina-See NUREG-1433,V01,R01 abstract.

g,ons to all applicants. These standards are not a substitute for NUREG 1433 V03 R01: STANDARD TECHNICAL SPECIFICA.

the operator licensing regulations and are subject to revision or TIONS GENERAL ELECTRIC PLANTS BWR/4. Bases (Sections other internal operator examination hcensing pokcy changes. As 3.4 s 3.10).

• Offee of Nuclear Reactor Regulation (Post appropriate, these standards will be revised periodically to ac-941001). April 1995. 422pp. 9506290164. 84463.001, commodate comments and reflect new enformation or experi-See NUREG-1433,V01,R01 abstract.

ence.

NUREG 1434 V01 R01: STANDARD TECHNICAL SPECIFICA-NUREG-1482: GUIDELINES FOR INSERVICE TESTING AT NU-TIONS GENERAL ELECTRIC PLANTS, BWR/6.Specifcations.

• CLEAR POWER PLANTS. CAMPBELL,P.L. Office of Nuclear Office of Nuclear Reactor Regulation (Post 941001). April 1995.

Reactor Regulation, Director (Post 870411). April 1995. 328pp.

412pp. 9506290222. 84466:001.

9505030476. 83746:022.

This report documents the results of the combined effort of in this report, the staff gives hcensees guidehnes for develop-the NRC and the industry to produce improved Standard Tech-ing and implementing programs for the inservice testing of nical Specifcations (STS), Revision 1 for General Electric pumps and valves at commercial nuclear power plants. The BWR/6 Plants. The changes reflected in Revision 1 resulted report includes U.S. Nuclear Regulatory Commission guidance 4

i

-- --- =.

Main Citations and Abstracts 5

i and recommendatons on inservice testing issues. The staff dis-tons developed by NRC engineers for the General Electric (GE) cusses the regulatons, the components to be included in an in-and Babcock and Wilcox (B&W) simulators.

service testing program, and the preparaton and content of cold shutdown and refueling outage justificatons and requests NUREG/CP-0140 V01: PROCEEDINGS OF THE TWENTY-for relief im the Amencan Society of Mechanical Engineers SECOND WATER REACTOR SAFETY INFORMATION Code requirements. The staff also gives specific guidance on MEETING. Plenary Session, Advanced instrumentaton & Control j

relief acceptable to the NRC and advises licensees in the use Hardware & Software, Human Factors Research, IPE & PRA.

of this information for applicaton at their facilities. The staff dis.

MONTELEONE.S. Brookhaven National Laboratory. April 1995.

cusses the revised standard technical specificatons for the in-403pp. 9505230106. 84016:001.

a service testing program requirements ano Gives guidance on the This three-volume report contains papers presented at the process a licensee may follow upon finding an instance of non.

Twenty-Second Water Reactor Safety Information Meeting held compliance with the Code.

at the Bethesda Marrott Hotel, Bethesda, Maryland, dunng the week of October 24-26, 1994. The papers are pnnted in the NUMEG-1525: ASSESSMENT OF THE NRC ENFORCEMENT order of their presentation in each session and desenbe 4

PROGRAM. LIEBERMAN.J. Ofc of Enforcement (Post 870413).

progress and results of programs in nuclear safety research j

COBLENTZ,L. Walnut Creek Field Ofc, R4 (Post 940404). April conducted in this country and abroad. Foreign participation in 1995. 200pp. 9505040381. 83784:001.

the meeting included papers presented by researchers from Fin-On May 13,1994, the Nuclear Regulatory Commission's land, France, Italy, Japan, Russia and United Kingdom. The 1

(NRC's) Executive Director for Operatons established a Review titles of the papers and the names of the authors have been 1

Team to Assess the NRC Enforcement Program. The team updated and may differ from those that appeared in the final evaluated the current system, and solicited comments from vari-program of the meeting.

ous NRC Offices, other Federal agencies, members of industry, and the public. This report presents the team's assessment.

NUREG/CP-0140 V02: PROCEEDINGS OF THE TWENTY-The report summanzes current processes and suggests certain SECOND WATER REACTOR SAFETY INFORMATION changes. It proposes: (1) increased clanty, focus, and simplicity MEETING. Severe Accident Research, Thermal Hydraulic Re-in the enforcement program; (2) retention of four seventy levels search For Advanced Passive LWRs, High-Burnup Fuel Behav-of violations, with a clear focus on safety; (3) holding enforce-ior. MONTELEONE S. Brookhaven National Laboratory. April ment conferences only when needed, clanfying their status as 1995. 430pp. 9505230109. 84018:001.

predecisional, and making open conferences the norm, (4) a See NUREG/CP-0140,V01 abstract.

ttreamhned civil penalty assessment process, with fewer deci-sional points and hmited outcomes, and the use of discretion NUREG/CP-0140 V03: PROCEEDINGS OF THE TWENTY-wheu appropriate; and (5) implementation changes to increase SECOND WATER REACTOR SAFETY INFORMATION affanney. Recommendations are paven in each area.

MEETING. Primary Systems integnty, Structural And Seismic En-gineering, Aging Research, Products And Applications.

NUREG 1526: LESSONS LEARNED FROM EARLY IMPLEMEN-MONTELEONE,S. Brookhaven National Laboratory. April 1995.

TATiDN OF THE MAINTENANCE RULE AT NINE NUCLEAR 265pp. 9505230115. 84019:068.

POWER PLANTS. PETRONE C.D.; CORREIA,R.P.; BLACK,S.C.

See NUREG/CP-0140,V01 abstract.

Office of Nuclear Reactor Regulation (Post 941001). June 1995.

44pp. 9507060341. 84532:001.

NUREG/CR 0200 V1 R04: SCALE: A MODULAR CODE SYSTEM This report summanzes the lessons learned from the nine FOR PERFORMING STANDARDIZED COMPUTER ANALYSES pilot site visits that were performed to review early implementa-FOR LICENSING EVALUATION Control Modules. PARKS.C.V.

tion of the maintenance rule using the draft NRC Maintenance Oak Ridge National Laboratory. April 1995.781pp.9506010500.

Inspection Procedure. Licensees followed NUMARC 93 01, "in-ORNL/NUREG/CSD2. 84122:213.

dustry Guideline for Monitonng the Effectiveness of Mainte-SCALE a modular code system for Standardized Computer nance at Nuclear Power Plants." in general, the licensees were Analyses Licensing Evaluation-has been developed by Oak thorough in determining which structures, systems, and compo-Ridge National Laboratory at the request of the U.S. Nuclear nents (SSCs) were within the scope of the maintenance rule at Regulatory Commission. The SCALE system utilizes well-estab-sach site. The use of an expert panel was an appropriate and hshed computer codes and methods within standard analysis practical method of determining which SSCs are nsk significant.

sequences that (1) allow an input format designed for the occa-When setting goals, all heensees considered safety but many li-sional user and/or novice, (2) automate the data processing csnsees did r.ot consider operating exponence throughout the and couphng between modules, and (3) provide accurate and industry. Although required to do so, licensees were not moni-reliable results. System development has been directed at prob-tonng at the system or train level the performance or condition lem-dependent cross-section processing and analysis of entical-for some systems used in standby service but not significant to ity safety, shielding, heat transfer, and depletion / decay prob-risk. Most hcensees had not estabhshed adequate monitonng of lems. Since the initial release of SCALE in 1980, the code structures under the rule. Licensees estabhshed reasonable system has been heavily used for evaluation of nuclear fuel fa-plans for doing periodic evaluations, balancing unavailability and cility and package designs. This revision documents Version 4.2 ftliability, and assessing the effect of taking equipmen' M of of the system.

service for maintenance. However, these plans were not evalu-ated because they had not been fully implemented at the time NUREG/CR-0200 V2P1R4: SCALE: A MODULAR CODE of the site visits.

SYSTEM FOR PERFORMING STANDARDIZED COMPUTER ANAL YSES FOR LICENSING EVALUATION. Functional Modules NUREG 1527: NRC'S OBJECT ORIENTED SIMULATOR IN-F1-F8. PARKS.C.V. Oak Ridge National Laboratory. April 1995.

STRUCTOR STATION. GRIFFIN.J1.; GRIFFIN J.P. Technical 670pp. 9506010509. ORNL/NUREG/CSD2. 84124:266.

Training Center. June 1995.107pp. 9506280427. 84469:073.

See NUREG/CR-0200,V01,R04 abstract.

As part of a comprehensive simulator upgrade program, the temulator computer systems associated with the Nuclear Regu.

NUREG/CR-0200 V2P2R4: SCALE: A MODULAR CODE latory Commission's (NRC) nuclear power plant simulators were SYSTEM FOR PERFORMING STANDARDtZED COMPUTER replaced. Because the original instructor stations for two of the ANALYSES FOR LICENSING EVALUATION. Functional Modules semulators were dependent on the onginal computer equipment.

F9-F16. PARKS.C.V. Oak Ridge National Laboratory. April 1995.

it was necessary to develop and implement new instructor sta-869pp.9506010521. ORNL/NUREG/CSD2. 84128:273.

tions. This report describes the Macintosh-based Instructor Sta-See NUREG/CR-0200,V01,R04 abstract.

6 Main Citations and Abstracts NUREG/CR-0200 V3 R04: SCALE: A MODULAR CODE SYSTEM cleavage-crack initiation (7) cladding evaluations, (8) pressur.

FOR PERFORMING STANDARDtZED COMPUTER ANALYSES ized-thermal-shock technology (9) anahsis methods validation, FOR LICENSING EVALUATION. Miscellaneous. PARKS.C.V.

(10) fracture evaluation tests. (11) warm prestressing, and (12)

Oak Ridge National Laboratory. April 1995.793pp.9506010519.

biaxial loading effects on fracture toughness. The program tasks ORNL/NUREG/CSD2. 84126:208.

have been structured to emphasize the resolution fracture See NUREG/CR-0200,V01,R04 abstract.

issues with near term licensing significance. Resources to exe.

cute the research tasks are drawn from ORNL with subcontract NUREG/CR 2850 V13: DOSE COMMITMENTS DUE TO RADIO-support from universities and other research laboratories. Close ACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES contact is maintained with the sister Heavy Section Steel irra-

• 1991. BAKER,0.A. Battelle Memorial Institute, Pacific North-diation Program at ORNL and with related research programs west Laboratory. April 1995.192pp. 9505090280. PNL-4221.

both in the United States and abroad. This report provides an e

ot P p ation and individual radiation dose commitments have

, A p

3 been estimated from reported radionuclide releases from com-mercial power reactors operating during 1991. Fifty-year dose NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND commitments for a one-year exposure from both liquid and at.

PIPING WELDS. Seventh Program Report Merch 1993 - Decem-mosphenc releases were calcutated for four population groups ber 1994. WILKOWSKI,G.M.; GHADIAlt,N ; RUDLANRD.; et al.

(infant, child, teenager, and adult) residing between 2 and 80 Battelle Memorial Institute, Columbus Laboratories. Apii 1995.

km from each of 72 reactor sites. This report tabulates the re-74pp. 9505180445. BMI-2173. 83967:074.

suits of these calculations, showing the dose commitments for This is the seventh progress report of the U.S. Nuclear Regu-both water and airbome pathways for each age group and latory Commission's research program entitled "Short Crs:ks in organ. Also included for each of the sites is an estimate of indi-Piping and Piping Welds." The program objective is to verify vidual doses that are compared with 10 CFR Part 50, Appendix and improve fracture analyses for circumferentially ciacked i design objectives. The total collectue dose commstments large-diameter nuclear piping with crack sizes typically used in (from both liquid and airborne pathways) for each site ranged leak before-break (LBB) analyses and in-service flaw evalua-from a high of 22 person-rem to a low of 0.002 person-rem for tions. All work in the eight technical tasks have been complet-the sites with plants in operation and producing power during ed. Ten topical reports are scheduled to be published. Progress the year. The arithmetic mean was 1.2 person-rom. The total only dunng the reporting period, March 1993 - December 1994, population dose for all sites was estimated at 88 person-rem for not covered in the topical reports is presented in this report. De-the 130 million people considered at nsk. The individual dose tails about the following efforts are covered in this report im-commitments estimated for all sites below the Appendix 1 provements to the two computer programs NRCPIPE and design objectues.

NRCPIPES to assess the failure behavior of circumferontial NUREG/CR-3469 V08: OCCUPATIONAL DOSE REDUCTION AT through-wall and surface cracked pipe, respectuely; Pipe mate.

NUCLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY rial property database PIFRAC; Circumferentially cracked pipe OF SELECTED READINGS IN RADIATION PROTECTION AND database CIRCUMCK.WK1; An assessment of the proposed ALARA, SULLIVAN.S.G.; KHAN,T.A.: XIE.J.W. Brookhaven Na-ASME Section til design stress rule changes on pipe flaw toler-tional Laboratory. May 1995. 78pp. 9506140072. BNL-NUREG.

ance; and A pipe fracture experiment on a section of pipe re-moved from service degraded by microbiologically induced cor-51708. 84297:202.

The ALARA Centor at Brookhaven National Laboratory pub-rosion (MIC) which contained a gisih weld crack. Progress in the lishes a series of bibliographies of selected readings in radiation other tasks is not repeated here as it has been covered in great protection and ALARA in a continuing effort to collect and dis-detail in the topical reports, seminate information on radiation dose reduction at nuclear NUREG/CR-4918 V08: CONTROL OF WATER INFILTRATION power plants. This is volume 8 of the senes. The abstracts in INTO NEAR SURFACE LLW DISPOSAL UNITS. Progress this bibliography were selected from proceedings of technical Report Of Field Experiments At A Humid Region meetings and conference joumats, research reports, and Site.Beltsville, Maryland. SCHULZ,R.K. California, Univ. of, Los searches of the Energy Science and Technology database of Angeles, CA. RIDKY,R.W. Maryland, Univ. of, College Park, MD.

the U.S. Department of Energy. The subject material of these O'DONNELL.E. Waste Management Branch (Post 941217).

abstracts relates to the many aspects of radiation protection April 1995. 33pp. 9505030447. 83725:281.

and dose reduction, and ranges from use of robotics, to oper.

The project objective is to assess means for controlling waste ational health physics, to water chemistry. Material on the infiltration through waste disposal unit covers in humid regions.

design, planning, and, management of nuclear power stations is Expenmental work is being performed in large scale fysimeters included, as well as information on decommissioning and safe (70'x45'x10') at Beltsville, MD and results of the assessment storage efforts. Volume 8 contains 232 abstracts, an author are applicable to disposai of LLW, uranium mill tailings, hazard-index, and a subject index. The author inoex is specific for this ous waste, and sanitary landfills. Three concepts are under in-volume, The subject index is cumulatwe and lists all abstract vestigation: (1) resistwe layer bamer, (2) conductNe layer bar-numbers from volumes 1 to 8. The numbers in boldface indicate rier, and (3) bioengineering water management. The resistive the abstracts in this volume; the numbers not in boldface repre-layer bamer consists of compacted earth (clay). The conductwo sent abstracts in previous volumes.

layer barrier is a special case of the capillary barrier and it re-NUREG/CR-4219 V10 N2: HEAVY-SECTION STEEL TECHNOL-quires a flow layer (e.g. fine sandy loam) over a capillary break.

OGY PROGRAM. Semiannual Progress Report For April-Sep-As long as unsaturated conditions are maintained water is con-tember 1993. PENNELL,W.E. Oak Ridge Natsnal Laboratory.

ducted by the flow layer to below the waste. This barrier is most May 1995.150pp. 9506140082. ORNL/TM 9593. 84299:001.

ef9cient at low flow rates and is thus best placed below a resis-The Heavy-Section Steel Technology (HSST) Program is con-tive layer barrier. Such a combination of the resistive layer over ducted for the Nuclear Regulatory Commission by Oak Ridge the conductive layer barrier promises to be highly effectue pro.

National Laboratory (ORNL). The program focuses on the de-vided there is no appreciable subsidence. Bioengineering water veloprnent and validation of technology for the assessment of management is a surface cover that is designed to accommo-fracture-prevention margins in commercial nuclear reactor pres-date subsidence. It consists of impermeable panels which en-sure vessels. The HSST Program is organized in 12 tasks: (1) hence run-off and hmit infiltration. Vegetation is planted in program management, (2) fracture methodology and analysis, narrow openings between panels to transpire water from below (3) materir.1 characterizations and propertes, (4) special techni-the panels. This system has successfully dewatered two lysi-cal assistance, (5) fracture analysis computer programs, (6) meters thus demonstrating that tNs procedure could be used

Main Citations and Abstracts 7

for remedial action (" drying out") existing water logged disposal through fill-in-the-blank input screens that contain descriptive sites at low cost.

data requests.

NUREG/CR-5229 V07: FIELD LYSIMETER INVESTIGATIONS:

LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM NUREG/CR-5857: AGING OF TURBINE DRIVES FOR SAFETY.

FOR FISCAL YEAR 1994. Annual Report. MCCONNELL,J.W.;

RELATED PUMPS IN NUCLEAR POWER PLANTS COX,0.F.

i ROGERS,R.D.; JASTROW,J.D.; et al. Idaho National Engineer-Oak Ridge National Laboratory. June 1995. 64pp. 9507120251.

ORNL 6713. 84634:295 s

ratory. May 1995. 74pp. 9506140086. INEL 94/0278.

This study examines the relationship between aging, and cur-The Field Lysimeter investigations: Low-Level Waste Data rent industry practices in areas of maintenance, surveillance, B:se Development Program. funded by the U.S. Nuclear Regu.

and operation of steam turbine drives for safety related purr ps.

latory Commission, is (a) at 4ng the degradation effects in These pumps are located in the Auxiliary Feedwater (AFW) ins caused by radiation, (b) system for pressurized water reactor plants, and the Reactor EPICOR-il organic ion-exchar m examining the adequacy of ts ocedures recommended in Core isolation Cooling and High Pressure Coolant injection sys-the Branch Technical Position o.

Tste Form to meet the re-tems or Boiling Water Reactor facilities. Findings in a recent v

quirements of 10 CFR 61 using wJified EPICOR-il resins, (c) study on the AFW (NUREG/CR-5404) indicate that the turbine obtaining performance information on solidified EPICOR-il ion _

drive is the single largest contributor to AFW system degrada-Exchange resins in a disposal environmat, and (d) determining tion. However, examination of the data show that the turbine the condition of EPICOR-il liners. Compressive test results of itself is a reliable piece of equipment with a good service 11-year old cement and vinyl ester-styrene solidified waste record. Most of the problems documented are the result of forms are presented, which show effect of aging and self-irra-problems with the turbine controls and the mechanical over-detion. Results of the ninth year of rma acquisition from the speed tnp mechanism, which apparently stem from three major fitid testing are presented and diss.ased. Dunng the continuing causes.

field testing, both Portland type 1-ll cement and Dow vinyl ester.

etyrene waste forms are being tested ir' lysimeter arrays beated NUREG/CR-5954: EFFECT ON AGING ON PWR CHEMICAL Et Argonne National Laboratory-East in lilinois and at Oak Ridge AND VOLUME CONTROL SYSTEM. GROVE,E.J.; TRAVIS,R.J.

ftlional Laboratory. The study is designed to provide continu, Brookhaven National Laboratory. June 1995.

196pp.

ous data on nuclide release and movement, as well as environ.

9507060335. BNL NUREG-52410. 84532:181.

mental conditions, over a 20-year period.

The effect of aging on the PWR Chemical and Volume Con-trol System (CVCS) has been evaluated. A detailed review of NUREG/CR-5591 V05 N1: HEAVY SECilON STEEL IRRADIA-the NPRDS and LER databases for the 1988-1991 time period, TlON PROGRAM. Semiannual Progress hiport For September together with a review of industry and NRC experience and re-1993 Through March 1994. CORWIN.W.R. Oak Ridge National search, indicate that age related degradations and failures have Ltboratory. Apr,I 1995. 71pp. 9505190052. ORNL/TM-11568.

occurred. These failures had significant effects on plant oper.

83981:267.

ation, including reactivity excursions, and pressurizer level tran-The goal of the Heavy Section Steel Irradiation Prograrl is to sients. The majonty of these component failures resulted in provide a thorough, quantitative assessment of effects of neu-leakage of reactor coolant outside the containment. A repre-tron irradiation on material behavior, and in particular the hac-sentative plant of each PWR NSSS design (W, CE, and B&S) ture toughness properties, of typical pressure vessel steels as was visited to obtain specific information on system inspection, they relate to light-water reactor pressure-vessel integnty. Ef-frcts of specimen size, matenal chemistry, product form and mi-surveillance, monnoring, and inspection practices. The results of these visits indicate that adequate system maintenance and in-crostructure, irradiation fluence, flux, temperature and spectrum, spection is being performed. In some instances, the frequencies and post-irradiation annealing are being examined en a wide ringe of fracture properties The HSSI Program is arrr%dd into of inspection were increased in response to repeated failure 14 tasks: (1) program management (2) fracture toughness events. A parametric study was performed to assess the effect (K(ic)) curve shift in high-copper welds, (3) crack-arrest tough' of system aging on Core Damage Frequency (CDF) This study ncss (K(la)) curve shift in high-copper wolds, (4) irradiation ef-showed that as MOV operating failures increased the contribu-fects on cladding, (5) K(Ic) and K(la) curve shifts in low upper-tion of the High Pressure injection to CDF also increased.

thelf welds, (6) annealing effects in low upper-shelf welds, (7)

NUREG/CR 5975 RO1: INCENTIVE REGULATION OF INVES-t irridiation effects in a commercial low upper shelf weld, (8) mi' TOR-OWNED NUCLEAR POWER PLANTS BY PUBLIC UTILI-crostructural analysis of irradiation effects (9) in-service 9ged TY REGULATORS.

MCKINNEY,M.D.;

SEELY,H.E.;

m1terial evaluations, (10) correlation monitor matenals, (11)

MERRITT,C.R.; et al. Battelle Memorial Institute, Pacific North-special technical assistance, (12) JPOR steel examination, (13) t;chnical assistance for Ju'CNRS Working Grouos 3 and 12' west Laboratory. April 1995. 70pp. 9505180354. PNL-8466.

B3967:001.

End (14) additional requirerrw.nts for matenal.e This report pro-vides an overview of the act vities within wh (t tese tasks The U.S. Nuclear Regulatory Commission (NRC) periodically from September 1993 through March 1990 surveys utilities that operate nuclear plants and state regulatory commissions that regulate utility owners of nuclear power NUREG/CR 5657: AUTOCASK (AUTOMATIC GENERA'lON OF plants. The NRC is interested in identifying states that have es-3-D CASK MODELS).A Microcomputer Based System F or SNp-tablished economic or performance incentive programs applica-ping Cask Design Review Analysis. GERHARD,M.A.;

ble to nuclear power plants, including states with new programs, SOMMER.S.C. Lawrence Livermore National Laboratory. Apri, how the programs are being implemented, and in determining 1995.130pp.9505180397. UCRL-ID-118766. 83967:231.

the financial impact of the programs on the utilities. The NRC AUTOCASK (Automatic Generation of 3-D CASK Models) is interest stems from the fact that such programs have the poten-a microcomputer-based system of computer programs and data-tial to adversely affect the safety of nuctear power plants. The teses developed at the Lawrence Livermore National Labortto-information ir, this report was obtained from interviews conduct-ry for the structural analysis of shipping casks for radmactive M with each state regulatory agency that administers an incen-material. Model specification is performed on the mic9corcrut-4 o orogram and each utility that owns at least 10% of an af-er, and the analyses are performed on the engineenny workse fei o nuclear power plant. The agreements, orders, and settle-tion or mainframe computer. AUTOCASK is based on "%6 mtnts, that form the basis for each incentive program were re.

60486 compatible microcomputers The system is compos. of viewed as required. The interviews and supporting documenta-a series of menus, input programs, display programs, a r. A tion form the basis for the individual state reports describing the i

generation program, and archive programs. All data is en ert 5 structure and financial impact of each incentive program.

. -i

i 8

Main Citations and Abstracts NUREG/CR-6004: PROBABILISTIC PIPE FRACTURE EVALUA-or in physiological or subjective sleepiness-alertness on shift.

TIONS FOR LEAK-RATE-DETECTION APPLICATIONS.

Except for one subtest in the performance test battery, subjects RAHMAN,S.; GHADIALf,N.; PAUL,0.; et al. Battelle Memoria; in-on 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts were slower, but more accurate, than those on stitute, Columbus Laboratones. April 1995.336pp.9505090276.

8-hour shifts. Several measures showed better alertness, mood, BMI-2174. 83848:001.

and off-duty sleep on evening shifts than on night shifts Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," was published by the U.S. Nucle.

NUREG/CR-6109: THE PROBABILITY OF CONTAINMENT FAIL-ar Regulatory Commission (NRC) in May 1973, and provides URE BY DIRECT CONTAINMENT HEATING IN SURRY.

guidance on leak detection methods and system requirements PILCH.M.M.; ALLEN,M.D.

Sandia National Laboratories.

for Light Water Reactors. Additionally, leak detection limits are SPENCER,0.W.; et al. Argonne National Laboratory. May 1995.

specified in plant Technical Specifications and are different for 275pp. 9506010485. SAND 93 2078. 84121:302.

Boiling Water Reactors (BWRS) and Pressunzed Water Reac.

This report uses tha methodology and scenarios described in tors (PWRs). These leak detection limits are also used in leak-NUREG/CR-6075 and its supp;ement to address the direct con-before-break ediuations performed in accordance with Draft tainment heating (DCH) issue for the Surry nuclear power plant Standard Review Plan, Section 3 6.3, " Leak Before Break Eval-(NPP). Consistency of the initial distributions has been ensured untion Procedures" where a margin of 10 on the leak detection by using insights from system-level codes, specifically SCDAP/

hmit is used in determining the crack size considered in subse-RELAP5 and CONTAIN. The most useful insights are that the quent fracture analyses. This study was requested by the NRC reactor coolant system (RCS) pressure is low at vessel breach, to: (1) evaluate the conditional failure probability for BWR and metallic blockages in the core region do not melt and relocate PWR piping for pipes that were leaking at the allowable leak de-into the lower pienum, and melting of upper plenum steel is cor-tection limit, and (2) evaluate the margin of 10 to determine if it related with hot leg failure. The SCDAP/RELAP5 output was was unnecessanly large. A probabihstic approach was undertak-used as input to CONTAIN to assess the containment condi-en to conduct fracture evaluations of circumferentially cracked tions at vessel breach. The load evaluations for Surry showed pipes for leak rate-detection applications. Sixteen nuclear piping no intersections of the load distnbutions with the containment systems in BWR and PWR plants were analyzed to evaluate strengin distribution, and thus the OCH issue for Surry can be conditional failure probability and effects of crack morphology resolved based on containment loads alone. However, the likeli-variability on the current margins used in leak rate detection for hood of high RCS pressures at vessel breach was evaluated for leak-before-break.

Surry for a limited number of sequences. The probability of DCS pressures greater than 1.38 MPa for all station blackout scenar.

NUREG/CR-6016: AGING AND SERVICE WEAR OF AIR-OPER.

ios without power recovery or operator intervention was found ATED VALVES USED IN SAFETY RELATED SYSTEMS AT NU.

to be low (0.077). This probability could have been factored into CLEAR POWER PLANTS. COX,D.F.; MCELHANEY,K.L.;

the containment failure probability for Surry if there had been STAUNTON R.H. Oak Ridge National Laboratory. May 1995.

intersections of the load and strength distributions.

62pp.9506140092. ORNL/TM-6789. 84299:152, Air operated valves (AOVs) are used in a variety of safety-re-NUREG/CR-6112: IMPACT OF REDUCED DOSE LIMITS ON lated applications at nuclear power plants. They are often used NRC LICENSED ACTIVITIES. Major issues in The implementa-where rapid stro e times are required or precise control of th tion Of ICRP/NCRP Dose Limit Recommendations. Final Report.

k valve obturator is required. They can be designed to operate MEINHOLD.C.B. Brookhaven National Laboratory. May 1995 automatically upon loss of power, which is often desirable when 79pp.9505230093. BNL/NUREG-52394. 84017:240.

selecting components for response to design basis conditions.

W at The purpose of this report is to examine the reported failures of least qualitatively, the potential impacts of reducing occupation-AOVs and determine whether there are idencable trends in the al dose limits below those given in 10 CFR 20 (Revised). The failures related to predictable causes. This report examines th followin9 overall conclusions were reached: (1) Althou9h 10 specific components that compnse a typical AOV, how those mSv yr( 1) is a reasonable limit for many licensees, such a limit components fail, when they fait, and how such failures are dis-could be extraordinanly difficult to achieve and potentially de-covered. It also examines whether current testing frequencies structive to the continued operation of some licensees, such as and methods are effective in predicting such failures.

nuclear power, fuel fabncation, and medicine, (2) Twenty mSv NUREG/CR-6046: ALERTNESS, PERFORMANCE, AND OFF-yr(-1) as a limit is possible for some of these groups, but for DUTY SLEEP ON 8-HOUR AND 12-HOUR NIGHT SHIFTS IN A others it would prove difficult, (3) Fifty mSv yr( 1) and age in 10s SIMULATED CONTINUOUS OPERATIONS CONTROL ROOM of mSv appear reasonable for all hcensees, both in terms of the SETTING. BAKER,T.L. Institute for Circadium Physiology. April lifetime nsk of cancer and severe genetic effects to the most 1995.157pp. 9505030466. 83745:228.

highly exposed workers, and the practicality of operation. In This study of simulated 8-hour and 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> work shifts com-some segments of the industry, this acceptability is based on pares alertness, speed, and accuracy of subjects assigned to the adoption of a " grandfather clause" for those people ex-the two shift conditions. Twenty male subjects, ages 20 to 45, ceeding or close to exceeding the cumulative limit at this time.

vare randomly assigned to either an 8-hour or 12-hour shift pro-tucol, working in teams of two in a process control simulator. In NUREG/CR-6114 V02: AUXILIARY ANALYSES IN SUPPORT OF addition to the simulator monitoring task, subjects completed a PERFORMANCE ASSESSMENT OF A HYPOTHETICAL LOW-15-minute performance assessment battery and a vigor and LEVEL WASTE FACILITY.Two Phase Flow And Contaminant affect scale hourly. Throughout the simulated work shift, alert-Transport in Unsaturated Soils With Application To Low Level ness was monitred by recording electroencephalogram (EEG),

Radioactive Waste Disposal.

BINNING,P.;

CELIA.M.A.;

electrooculogram !EOG) and electromyogram (EMG) data At 2-JOHNSON.J.C. Pnneeton Univ., Pnneeton, NJ. May 1995.

hour intervals, subvW sleepiness-alertness level was as-139pp. 9506140130. 84299:214.

tests. Dunng off-shift hours, sub-A numencal model of multiphase air water flow and contami-sessed via standardized te a jocts lived in attached, self-contained apartments. Subjects nant transport in the unsaturated zone is presented. The multi-were restricted to bed for an 8-hour sleep period in total dark-phase flow equations are solved using the two-pressure, mixed ness one-hour after work shifts; EEG, EOG, AND EMG record-form of the equations with a modified Picard lineanzation of the ings were continued dunng sleep. Dunng days off between equations and a finite element spatial approximation. A volatile blocks of shifts, subjects left the facility, but kept detailed logs contaminant is assumed to be transported in either phase, or in of sleep-wake activities. No significant differences were found both phases simultaneously. The contaminant partitions be-between subjects on 8-hour and 12-hour night shifts in perform-tween phases with an equilibnum distribution given by Henry's ance on the simulator task, in length or quality of daytime sleep.

Law or via kinetic mass transfer. The transport equations are

Main Citations and Abstracts 9

solved using a Galerkin finite element method with reduced in-human error in the RAB system, a human factors team visited tegration to lump the resultant matnces The numencal model is 23 RAB treatment sites in the U.S. The team observed RAB applied to published experimental studies to examine the be-treatment planning and delivery, interviewed RAB personnel, havior of the air phase and associated contaminant movement and performed walk-throughs, during which staff demonstrated under water infiltration. The model is also used to evaluate a hy-the procedures and practices used in performing RAB tasks.

pothetical design for a low-level radioactive waste disposal facil-Factore leading to human error in the RAB system were identi-sty. The model has been developed in both one and two dimon-fied. The impact of those factors on the performance of RAB sions; documentation and computer codes are available for the was then evaluated and pnontized in terms of safety signifi-one-dimensional flow and transport model.

cance. Finally, the project identified and evaluated alternative i

approaches for resolving the safety significant problems related NUREG/CR 6116 V10: SYSTEL'9 ANALYSIS PROGRAMS FOR to human error.

HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SA.

PHIRE) VERSION 5.0. Data Loading Manual. VANHORN,R.L.;

NUREG/CR-6125 V02: HUMAN FACTORS EVALUATION OF

-WOLFRAM L.M.; FOWLER.R.D.; et al. Idaho National Engineer.

REMOTE AFTERLOADING BRACHYTHERAPY. Function And mg Laboratory. April 1995.1Mra. 9505180347. INEL 94/0039 Task Analysis CALLAN.J.R.; GWYNNE J.W.; KELLY,R.T.; et al.

83966:120.

Pacific Science & Engineenng Group, Inc. May 1995. 143pp.

i The Systems Analysis Programs for the Hands-on Integrated 9506140126. 84300:207.

Reliability Evaluations (SAPHIRE) suite of programs can be A human factors project on the use of nuclear by-product ma-used to organize and standardize in an electronic format infor-tenal to treat cancer using remotely operated afterloaders was mation from probabilistic risk assessments or individual plant undertaken by the Nuclear Regulatory Commission. The pur-examinationt The Models and Results Database (MAR-D) pro-pose of the project was to identify factors that contnbute to gram of the SAPHIRE suite serves as the repository for probabi-human error in the system for remote afterloading brachyther-hstic nsk assessment and individual plant examination data and apy (RAB). This report documents the findings from the first information. This report demonstrates by examples the common phase of tne project, which involved an extensive function and electronic and manual methods used to load these types of task analysis of RAB. This analysis identified the functions and data. It is not a mnd alone document but references docu-tasks in RAB, made preliminary estimates of the likelihood of ments that contributu information relative to the data loading human error in each task, and determined the skills needod to process. This document provides a more detailed discussion perform each RAB task. The findings of the function and task and instructions for using SAPHIRE 5.0 only when enough infor-analysis served as the foundation for the remainder of the mation on a specific topic is not provided by another available project, which evaluated four major aspects of the RAB system sourca linked to human error; human-system interfaces; procedures NUREG/CR 6119 V01:

MELCOR COMPUTER CODE and practices; training and qualifications of RAB staff; and orga-MANUALS Pnmer And User's Guides. Version 1.8.3 September nizational practices and policies. At its completion, the project 1994. SUMMERS.R.M.; COLE R.K.; SMITH R.C.; et al. Sandia identified and pnoritized areas for recommended NRC and in-National Laboratones. March 1995 708pp. 9505040396.

dustry attention based on all uf the evaluations and analyses.

SAND 93-2185. 83779:001.

NUREG/CR-6144 V06 P1: EVALUATION OF POTENTIAL MELCOR is a fully integrated, engineenng-level computer SEVERE ACCIDENTS DURING LOW POWER AND SHUT-code that models the progression of severe accidents in light DOWN OPERATIONS AT SURRY, UNIT 1. Evaluation Of Severe water reactor nuclear power plants. MELCOR is being devel-Accident Risk Dunng Mid-Loop Operations. Main Report JO.J.;

oped at Sandie Nation 6.1 Laboratones for the U.S. Nuclear Reg.

LIN,C.C.; NEYMOTIN.L.; et al. Brookhaven National Laboratcry.

ulatory Commissiori as a second-generation plant risk assess-ment tool and the successor to the Source Term Code Pack.

May 1995.

145pp.

9506220089.

BNL-NUREG 52399.

84390192.

age. A broad spectrum of severe accident phenomena in both This document contains the accident progression analysis of boiling and pressunzed water reactors is treated in MELCOR in internally initiated events for Surry, Unit 1 as it operates in mid-a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and loop operation dunng drained maintenance or a refueling outage. The report documents the methodology used during the confinemont buildings; core heatup, degradation, and relocation; analysis, describes the results from the application of the meth-core-concrete attack; hydrogen production, transport, and com-bustion; fission product release and transport; and the impact of odology, and compares the results with the results frorn a full power analysis performed on Surry as a part of the Nureg-1150 engineered safety features on thermal-hydraulic and radionu.

clide behavior. Current uses of MELCOR include estimation of study.

severe accident source terms and their sensitivities and uncer.

NUREG/CR-6144 V06 P2: EVALUATION OF POTENTIAL tainties in a vanety of applications.

SEVERE ACCIDENTS DURING LOW POWER AND SHUT-NUREG/CR-6119 V02:

MELCOR COMPUTER CODE DOWN OPERATIONS AT SURRY, UNIT 1. Evaluation Of Severe MANUALS. Reference Manuals Version 1.8.3 September 1994.

Accident Risk Dunng Mid-Loop Operations. Appendices. JO,J.;

SUMMERS.R.M.; COLE,R K.; SMITH,R.C. Sandia National Lab-LIN,C.C.; NEYMOTIN,L.; et al. Brookhaven National Laboratory.

oratones. March 1995. 865pp. 9505040402. SAND 93 2185.

May 1995.

275pp.

9507120287.

BNL-NUREG-52399.

83781:001.

84633:084.

See NUREG/CR 6119,V01 abrtract See NUREG/CR-6144,V06 P1 abstract.

NUREG/CR-6125 V01: HUMAN FACTORS EVALUATION OF NUREG/CR-6235: ASSESSMENT OF SHORT THROUGH-WALL REMOTE AFTERLOADING BRACHYTHERAPY. Human Error CIRCUMFERENTIAL CRACKS IN PIPES Experiments And And Cntical Tasks in Remote Afterloading Brachytherapy And Analysis, March 1990 - December 1994. BRUST,F.W.;

Approaches For improved System Performance. CALLAN J.R.;

SCOTT,P.; RAHMAN S.; et al. Battelle Memorial Institute, Co-KELLY,R.T.; OUE.ML; et al. Pacific Science & Engineenng lumbus Laboratones. April. 1995. 249pp. 9505040365. BMI-Group, Inc. May 1995. 205pp. 9506140119. 84300:001, 2179. 83784:190.

Remote Afterloading Brachytherapy (RAB) is a medical r%c-This topical report summarizes the work performed for the ess used in the treatment of cancer. RAB uses a compu% con-Nuclear Regulatory Commission's (NRC) research program enti-trolled device to remotely insert and remove radioactive sources tied "Short Cracks in Piping and Piping Welds" that specifically close to a target (or tumor) in the body. Some RAB problems focuses on pipes with short through-wall cracks. Previous NRC affecting the radiation dose to the patient have been reported efforts, conducted under the Degraded Piping Program, focused and attnbuted to human error. To determine the root cause of on understanding the fracture behavior of larger cracks in piping

1 l

10 Main Citations and Abstracts i

and fundamental ftacture mechanics developments necessary Thermal embnttlement of static-cast CF-8 6tainless stael for this technology. This report gives detai6 on: (i) material components from the decommissioned Shippingport reactor has property determinations (ii) pipe fracture expenments, and (iii) been characterized. Cast stainless steel matenals were ob-development, modification, and vahdation of fracture anatysis tained from four cold-leg check valves, three hot leg main shut-methods. The matenal property data required to anatyre the ex-off valves, and two pump volutes. The actual time-et-tempera-penmental results are included. Ihese data were also imple-ture for the materials was m13 y at m281 degrees C for the i

mented into the NRC's PIRFAC database. Three pipe experi-hot-leg components and m264 degrees C for the cold-leg com-ments with short through-wall cracks were conducted on targe ponents. Baseline mechanical properties for as-cast material diameter pipe. Also, expenments were conducted on a large-di-were determined from tests on either recovery-annealed materi-ameter uncracked pepe and a pipe with a moderate-size al or material from the cooler region of the component. The through-wall crack. The analysis results reported here focus on Shippingport matenals show modest decreases in fracture simple predective methods based on the J-Tearing theory as toughness and Charpy-impac9 properties and a small increase well as hmit-load and ASME Section XI analyses. Some of in tensile strength because of relatively low service tempera-these methods were improved for short-crack-length predic-tures and ferrite content of the steel The procedure and corre-tions. The accuracy of the various methods was determined by lations developed at Argonne National Laboratory for estimating comparisons with experimental results from this and other pro-mechanical properties of cast stainless steels predict accurate

grams, or slightly lower values for Charpy-impact energy, tensile flow NUREQ/CR-6251: STAINLESS STEEL SUBMERGED ARC WELD stress, fracture toughness J-R curve, and J(IC) of the materials.

FUSION LINE TOUGHNESS. ROSENFIELD,A.R.; HELD,P.R.;

The kinetics of thermal embrittlement and degree of embnttle-ment at saturation were established from materials that were WILKOWSKI,G.M. Battelle Memorial Institute, Columbus Labora-aged further a,n the laboratory. The results were consistent with tories. April 1995. 88pp. 9505190023. BMI-2180. 83980: t 97.

the estimates. The correlations successfully predicted the me-This effort evaluated the fracture toughness of austenitic steel submerged arc weld (SAW) fusion lines. The incentive was to chanical properties of the Ringhals 2 reactor hot-and cross-explain why cracks grow into the fusion line in many pipe tests over-leg elbows (CF-8M) after service of m15 y and the KRB reactor pump cover plate (CF-8) after m 8 y of service.

conducted with cracks initially centered in SAWS. The concern was that the fusion line may have a lower toughness than the NUREG/CR-6283: FIELD SITE INVESTIGATION: EFFECT OF SAW. It was found that the fusion line, J(ic) was greater than MINE SEISMICITY ON GROUNDWATER HYDROLOGY.

the SAW toughness but much less than the base metal. Of OFOEGBU,G.I.; HSIUNG,S-M.: CHOWDHURY,A.H.; et al.

greater importance may t:e that ;he crack growth resistance Center for Nuclear Waste Regulatory Analyses. April 1995.

(J(D)-R) of the fusion hne appeared to reach a steady state 103pp. 9505040377. CNWRA 94 017. 83783:158.

value, while the SAW had a continually increasing J(D)-R curve.

The results of a field investigation on the groundwater-hydro.

This explains why the cracks eventually turn to the fusion line in logc effect of mining-induced earthquakes are presented. The the pipe experiments. A method of incorporating these results investigation was conducted at the Lucky Friday Mine Idaho, the would be to use the weld metal J-R curve up to the fusion-li e groundwater pressure in three fracture zones was monitored steady-state J value. These results may be more important to over a 24-mo period. The magnitude, source socation, and asso-LBB analyses than the ASME flaw evaluation procedures, since ciated ground motions of mining-induced seismic events were there is more crack growth with through-wall cracks in LBB also monitored. Several seismic events of magnitude 1.0 or analyses than for surface cracks in pipe flaw evaluations.

larger were recorded, many of which caused a change in the NUREG/CR-6256 V01: FIELD LYSIMETER INVESTIGATIONS.

groundwater pressure. The magnitude of groundwater-pressure TEST RESULTS. Low Level Waste Data Base Program. Test Re-change vaned with the seismic-event magnitude and source dis-suits For Fiscal Years 1986, 1987.1988, And 1989, tance. The data was examined using regression analysis. The MCCONNELL,J.W.; ROGERS,R.D.; FINDLAY,M.W.; et al. Idaho statistical models obtained predicted the effects of smcli-magni-National Engineenng Laboratory. May 1995.

134pp.

tude seismic events more satisfactorily than those of larger 9506020457. INEL 95/0073. 84147:001.

ones. The observed change in groundwater pressure due to The Field Lysimeter investigations: Low-Level Waste Data seismic events of magnitude 3.0 or more were larger than those Base Development Program, funded by the U.S. Nuclear Regu.

predicted using the statistical model. Based on these results, it latory Commission (NRC), is (a) studying the degradation effects is suggested that the effect of earthquakes on groundwater flow in EPICOR-Il organic lon-exchange resins caused by radiation, may be better understood through mechanistic modehng. The (b) examining the adequacy of test procedures recommended in mechanscal processes and matenal behavior that would need to the Branch Technical Position on Waste Form to meet the ro-be incorporated in such a model are examined. They include a quirements of 10 CFR 61 using sohdified EPICOR-il resins, (c) description of the effect of stress change on the permeabihty obtaining performance information on sohdified EPICOR-Il ion.

and water storage capacity of a fractured rock mass; transient exchange resins in a disposal environment, and (d) determining fluid flow; and the generation and transmission of seismic the condition of EPICOR-il kners. Results of the first 4 years of waver, through the rock mass.

data acquisition from the field testing are presented and dis-NUREG/CR-6287: MANAGEMENT CONCEPTS AND SAFETY cussed. During the continuing field testing, both Portland type l-Il cement and Dow vinyt ester-styrene waste forms are being APPLICATIONS FOR NUCLEAR FUEL FACILITIES. EISNER,H'-

SCOTTI,R.S. George Washington Univ., Washington, DC.

tested in fysimeter arrays located at Argonne National Laborato-ry-East in Ilknois and at Oak Ridge National Laboratory. The ex.

DEllCATE.W.S. The KEVRIC Company, Inc. May 1995.131pp.

9506020467. 841471 37.

perimental equipment is described and results of waste form charactertration using tests revinmended by the NRC's " Tech-This report presents an overview of effectiveness of manage-nical Position on Waste Form" are presented. The study is de-runt control of safety. H resews sevwal modan rnanagement signed to provide continuous data on nuchde release and move-control theories as well as the general functions of manage-ment, as well as environmental conditions, over a 20-year mont and relates them to safety issues at the corporate and at period.

the process safety management (PSM) program level. Following these discussions, a formal and structured technique for as-NUREQ/CR-6275: MECHANICAL PROPERTIES OF THERMALLY sessing management of the safety function is suggested. Seven AGED CAST STAINLESS STEELS FROM SHIPPINGPORT RE-modern management control theories are summar 2ed, including ACTOR COMPONENTS. CHOPRA,0.K.; SHACK,W.J. Argonne business preess reengineering. the leaming organization, capa-National Laboratory. April 1995.170pp. 9506010453. ANL 94/

bility maturity, total quality management, quahty assurance and

37. 84121:001.

control, reliabihty centered maintenance, and industrial process

Main Citations and Abstracts 11 safety Each of these theories is examined for its pnncipal char-dustry to justify elimination of pipe whip restraints and jet im-actenstscs and impications for safety management. The five pingement shields which are present because of the expected general management functions of planning, organizing, direct.

dyname effects from pipe rupture. The application of the LBB ing, monitonng, and integrating, whch together provide control methodology frequently requires calculation of leak, rates. The over all company operations, are discussed. Under the broad leak rates depend on the crack-opening area of the through-categones of Safety Culture, Leadership and Commitment, and wall crack in the pipe. In addition to LBB analyses which Operating Excellence, key corporate safety elements and their assume a hypothetical flaw size, there is also interest in the in-subelements are examined. The three categories under which tegrity of actual leaking cracks corresponding to current leakage PSM program-level safety issues are described are Technology, detection requirements in NRC Regulatory Guide 1.45, or for as-5 Personnel, and Facilities, sessing temporary repair of Class 2 and 3 pipes that have leaks as are being evaluated in ASME Section XI. This study was re-NUREG/CR4297: FRACTURE EVALUATIONS OF FUSION LINE Quested by the NRC to review, evaluate, and refine current ana-CRACKS IN NUCLEAR PIPE BIMETALLIC WELDS. SCOTT,P.

FRANCINI,R.; RAHMAN,S.; et al. Battelle Memonal Institutg

% cal rnWs fw cacupemng-ama anahses of ms wim &

cumferential through-wall cracks. Twenty-five pipe experiments Columbus Laboratories. Apnl 1995.111pp. 9505030455. BMI were analyzed to determine the accuracy of the predictive in h

Rs' and PWRs there are many locations where models. hal pacMal SWs of cacWeg M at caMace pmssure, off center cracks, restraint of pressure-in.

carbon steel pipe or components are joined to stainless steel duced bending, cracks in thickness transition regions, weld re-pipe or components with a bimetalle weld. The objective of the al sWsm, cacbm@Wy Ms, aM MMWp I

research described in this report was to assess the accuracy of Ic anaysis, wem also investgaM current fracture analyses for the case of a crack along a carbon steel to austenste weld fusion hne. To achieve the program ob-NUREG/CR-6307:

SUMMARY

OF COMMENTS RECEIVED AT jective, material property data and data from a large-diameter WORKSHOP ON USE OF A SITE SPECIFIC ADVISORY pipe fracture experiment were developed to assess current ana-BOARD (SSAB) TO FACILITATE PUBLIC PARTICIPATION IN fytical methods. The bimetallic welds evaluated in this program DECOMMISSIONING CASES. CAPLIN.J.; PAGE,G.; SMITH.D.;

were bimetalle welds obtained from a cancelled Combustion et al. Advanced Systems Technology, Inc. June 1995.115pp.

Engineenng plant. The welds joined sections of the carbon steel 9507120259. 84634:190.

q cold-leg piping system to stainless steel safe ends that were to The Nuclear Regulatory Commission (NRC) is conducting an be welded to stainless steel pump housings. The major conclu-enhanced partcipatory rulemaking to establish radiological crite.

sion drawn as a result of these efforts was that the fracture be-na for the dacommissioning of NRC-licensed facilities. As part havior of the bimetalle weld evaluated in this program coc1 be of this rulemaking, on August 20,1994 the NRC pubbshed a evaluated with reasonable accuracy using the strength and proposed rule for public comment. Paragraph 20.1406(b) of the toughness properties of the carbon steel pipe material in con

• proposed rule would require that the hcensee convene a Site junction with conventional elaste-plaste fracture mechanics of Specife Advisory Board (SSAB) if the hcensee proposed re-limit. load analyses. This may not be generally true for all bime-lease of the site for restrcted use after decommissioning. To talhc welds, as discussed in this report-encourage comment the NRC held a workshop on the subject NUREG/CR-6299: EFFECTS OF TOUGHNESS ANISOTROPY of SSABs on December 6,7, and 8,1994. This report summa.

AND COMBINED TENSION, TORSION. AND BENDING LOADS rizes the 567 comments categorized from the transcript of the ON FRACTURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

workshop. The commenters at the workshop generally support.

MOHAN,R.; MARSCHALL,C.W.; KRISHNASWAMY,P.; et al. Bat.

ed public participation in decommissioning cases. Many partici-l telle Memonal Institute, Columbus Laboratories. Apol 1995.

pants favored promulgating requirements in the NRC's rules.

122pp. 9506020484. 84147:268.

Some industry participants favored relying on voluntary e9 This topical report summanzes the work on angled crack changes between the pubhc and the hcensees. Many partch growth and combined loading effects performed within the Nu-pants indcated that a SSAB or something functionally equiva-clear Regulatory Commissions's research program, entitled lent is needed in controversial decommissioning cases, but that "Short Cracks in Piping and Piping Welds". The major impetus some lesser undertaking can achieve meaningful public part6 for this work stemmed from the observation that initial circum-pation in other cases. No analysis or response to the comments ferential cracks in carbon steel pipes exhibited angular crack is included in this report.

1 growth. This failure mode was little understood, and the effect NUREG/CR-6308: AN OVERVIEW OF INSTABILITY AND FIN.

of angled crack growth from an initially circumferential crack GERING DURING IMMISCIBLE FLUID FLOW IN POROUS AND j

raised questons of how pipes under combined loading with tor-FRACTURED MEDIA. CHEN.G.; TANIGUCHI,M.; NEUMAN,S.P.

sional stresses would behave. There were three major conclu-Anzona, Univ. of, Tucson, AZ. April 1995,137pp. 9507060331.

sions from this work. The first was that virtually all f6mtc nucle-84532:043 ar pipes will have toughness anisotropy. The second was that Wetting front instabihty is an important phenomenon affecting the ratio of the normalized crack dnving force (as a function of fluid flow and contaminant transport in unsaturated soils and angle) to the normahzed toughness (also as a function of the rocks. It causes the development of fingers which travel faster angle of crack growth) showed that there was an equal likeh-than would a uniform front and thus bypass much of the hooo uf : racks growing at any angle between 25 and 65 de-medium. Water saturation and solute concentration in such fin-i grees. This agreed with the scatter of crack growth angles ob-gers tend to be higher than in the surrounding medium. During l

served in pipe tests. Third, for combined loads with torsional infiltraton, fingering may cause unexpectedly rapid arrival of streses, an effectrve moment allows pure bending analyses to water and solute at the water table. This notwithstanding, most be used up to crack initiaton. Crack opening area under com-models of subsurface flow and transport ignore instability and bined loads could also be determined in this manner.

fingering. In this report, we survey the hierature to assess the NOREG/CR4300: REFINEMENT AND EVALUATION OF CRACK.

extent to which this may or may not be justified. Our overview OPENING AREA ANALYSES FOR CIRCUMFERENTIAL covers expuiments, theoretical studies, and computer simula-THROUGH-WALL CRACKS IN PIPES.

RAHMAN,S.;

tions of instability and fingenng during immiscible two-phase BRUST,F.W.; GHADIAll,N.; et al. Battelle Memurial Institute, flow and transport, with emphasis on infiltration into soils and Columbus Laboratories. April 1995. 227pp. 9505030464. BMI-fractured rocks. Our descripton of instability in an ideal fracture 2184. 83745:001.

(Hele-Shaw cell) includes an extension of existing theory to Leak-before-break (LBB) analyses for circumferentially fractures and interfaces having arbitrary onentations in space.

cracked pipes are currently being conducted in the nuclear in-Our discussion of instability in porous media includes a slight

l t

l 12 Main Citations and Abstracts but important correction of existing theory for the case of an in-ments, Kr and Cs, were in good agreement with the ORNL-chned interface. We conclude by outlining some potential direc-Booth Model.

tions for future research. Among these, we single out the effect of soil and rock heterogeneities on instabihty and preferential NUREG/CR-6322: BUCKLING ANALYSIS OF SPENT FUEL flow as meriting special attention in the context of nuclear BASKET, LEE,A.S.; BUMPAS S.E. Lawrence Livermore National waste storage in unsatursted media.

Laboratory. May 1995. 60pp. 9505230342. UCRL-ID-119697.

84026:2a5.

NUREG/CR-6312: ASSESSMENT OF FIBER OPTIC PRESSURE The basket for a spent fuel shipping cask is subjected to SENSORS. HASHEMIAN,H.M.: BLACK,C.L.; FARMER,J.P. Anal-compressive stresses that may cause global instability of the ysis & Measurement Services Corp. April 1995. 132pp.

basket assemblies or local buckling of the individual members.

9506010456. 84121:170.

Adopting the common buckling design practice in which the sta-The pnnciple of operation of fiber optic pressure sensors and bility capacity of the entire structure is based on the perform-the potential of these sensors for use in nuclear power plants ance of the individual members of the assemblies, the typical are desenbed in this report. Also included is a review of current spent fuel basket, which is composed of plates and tubular research on fiber optic sensing technologies, a companson of structural members, can be idealized as an assemblage of col-fiber optic pressure sensors with conventional pressure sensors, umns, beam-columns and plates. This report presents the flex-a discussion on advantages and disadvantages of fiber optic ural buckhng formulas for five load cases that are common in pressure sensors, a review of failure modes of these sensors, the basket buckling analysis: column under axial loads, column and results of a survey of fiber optic sensor manufacturers.

under axial and bending loads, plates under uniaxial loads, plates under biaxial loadings, and plate under biaxial loads and NUREG/CR-6315: CANDU REACTORS, THEIR REGULATION IN lateral pressure. The acceptance criteria from the ASME Boiler CANADA, AND THE IDENTIFICATION OF RELEVANT NRC and Pressure Vessel Code are used to determine the adequacy SAFETY lSSUES. CHARAK,l.; KIER.P.H. Argonne National Lab-of the basket components. Special acceptance cnteria are pro-orstory. April 1995. 48pp. 9505180578. ANL 95/5. 83980:034.

posed to address the unique material charactenstics of austenit-Atomic Energy of Canada, Limited (AECL) and its subsidiP5 ic stainless steel, a matenal which is frequently used in the in the United States, are considering submitting the CANDi J basket assemblies.

design for standard design certification under 10 CFR Part 62.

CANDU reactors are pressurized heavy water power reactors.

NUREG/CR-6327: MODELS FOR EMBRITTLEMENT RECOVERY They have some substantially differern safety responses and DUE TO ANNEALING OF REACTOR PRESSURE VESSEL safety systems than the LWRs that the commercial power reac-STEELS. EASON,E.D.; WRIGHT,J.E.; NELSON.E.E.; et al. Mod-tor licensing regulations of the U.S. Nuclear Regulatory Com-eling & Computer Services. May 1995. 76pp. 9505190018. MCS mission (NRC) have been developed to deal with. In this report.

950302. 83982:001.

the authors discuss the basic design charactenstics of CANDU The irradiation embnttlement of the reactor pressure vessel in reactors, specifically of the CANDU 3 where possible, and some nuclear power plants can be reduced by thermal annealing at safety-related consequences of these charactenstics. The au-temperatures higher than the normal operating conditions. The thors also discuss the Canadian regulatory provisions, and the objective of this work was to analyze the pertinent data and de-CANDU safety systems that have evolved to satisfy the Canadi-velop quantitative models for estimating the recovery in 30 ft-lb an regulatory requirements as of December 1992. Finally, the (41 J) Charpy transition temperature and Charpy and Charpy authors identify NRC regulations, mainly in 10 CFR Parts 50 and upper shelf energy due to annealing. An analysis data base was 100, with issues for CANDU 3 reactor designs. In all, eleven developed, reviewed for completeness and accuracy, and docu-such regulatory issues are identified. They are: (1) the ATWS mented as part of this work. Independent variables considered rule (Section 50.62), (2) station blackout (Section 50.63); (3) in the analysis included matenal chemistries, anneahng time and conformance with Standard Review Plan (SRP); (4) appropnate-temperature, irradiation time and temperature, fluence, and flux.

ness of the source term (Section 50.34(f) & Section 100.11);(5)

To identify important variables and functional forms for predict-applicability of reactor coolant pressure boundary (RCPB) re-ing embnttlement recovery, pattern recognition, transformation querements (Section 50.55a, etc); (6) ECCS acceptance enteria analysis, and residual analysis were applied together with cur-(Section 50.46(b); (7) combustible gas control (Section 50.44, rent understanding of the mechanisms governing embnttlement etc); (8) power coefficient of reactivity (GDC 11); (9) seismic and recovery. Models were cahbrated using multivanable sur.

design (Part 100); (10) environmental impacts of the fuel cycle face-fitting techniques. The quality of fit was evaluated by con.

(Section 51.51); and (11) (standards Section 50.55a).

sidering both the Charpy anneahng data used for fitting and a surrogate hardness data base. Several iterations of model cali-NUREG/CR-6318: DATA

SUMMARY

REPORT FOR FISSION bration, evaluation with respect to mechanistic and statistical PRODUCT RELEASE TEST VI 7.

OSBORNE.M.F.;

considerations, and comparison with the trends in hardness LORENZ,R.A.; TRAVIS,J.R.; et al. Oak Ridge National Laborato-data produced improved correlation models for estimating ry. May 1995. 65pp. 9506220072. ORNL/TM-12937. 84394:001.

Charpy upper shelf energy and transition temperature after irra-Test VI-7 was the final test in the VI senes conducted in the diation and annealing.

vertical fumace. The fuel specimen was a 15.2-cm-long section of a fuel rod from the Monticello boihng water reactor (BWR).

NUREG/CR-6330: RESULTS OF REGULATORY IMPACT The fuel had experienced a burnup of -40 Mwd /kg U. It was SURVEY OF INDUSTRIAL AND MEDICAL MATERIALS Ll-heated in an induction fumace for successive 20-min periods at CENSEES OF THE OFFICE OF NUCLEAR MATERIALS 2000 and 2300 K in a moist air-hehum atmosphere. Integral re-SAFETY AND SAFEGUARDS.

LACH.D.;

MELBER B.;

leases were 69% for 85Kr. 52% for (125)Sb, 71% for both BRICHOUX,J.; et al Battelle Human Affairs Research Centers.

(134)Cs and (137)Cs, and 0.04% for (154)Eu. For the non-June 1995.100pp. G507060313. PNL 10548. 84533:007.

gamma-emitting species, release values for 42% for 1,4.1% for This report presents the findings of a regulatory impact survey Ba,5.3% for Mo, and 1.2% for Sr were determined. The total of nuclear materials licensees of the United States Nuclear mass released from the furnace to the collection system, includ-Regulatory Commission (NRC). Commissioners of the NRC di-ing fission products, fuel, and structural materials, was 0.89 g, rected staff to provide the Commission with first hand informa-with 37% being collected on the thermal gradieni tubes and tion from licensees that could be used to improve the overall 63% downstream on filters. Posttest examination of the fuel regulatory program. A self-administered, mail-out survey ques-specimen indicated that most of the cladding was completely tionnaire was used to collect data from a sample of licensees oxidized to ZrO(2), but that oxidation was not quite complete at who had interaction with the NRC dunng the previous 12 the upper end. The release behaviors for the most volatile ele-months. A total of 371 respondents of the 589 who were sent

Main Citations and Abstracts 13 quashonneres returned 6,uj surveys, for a response rate clear Regulatory Research for use in control room hatxtability of 63%. The body of the report presents the findogs of the assessments. The document includes a user's guide to the i

survey including a tmof introduction to the approach used, fol-coce, a descriptxm of the technical bases for the code, and a lowed by survey indings regardmg regulations, poices and reg-programmer's guule to the code. The ARCON95 code uses ulatory guidance, exponence with licensing applications, renew-hourly meteorological data and recently developed methods for als and amendments, inspectKme; reportmg requirements; and estimatmg despersson in tre voruty of buildogs to calculate rela-er* rom actions The appendices of the report Mude a teve concentratens at control room air intakes that would be ex-copy of the survey as admrestored to licensees, a fuller de-coeded no more than five percent of the time. These concentra-scription of the survey design and data collechon methods, and teons are calculated for averaging penods ranging from one hour detailed graphic material doecnbmg survey responses to 30 days in duration. Relative concentrations calculated by NURES/CR4831: ATMOSPHERIC RELATIVE CONCENTRA-ARCON95 are signifcantly lower than concentrations calculated TlONS IN BUILDING WAKES. RAMSDELL,J.V.; SIMONEN C.A.;

using the currently accepted procedure when winds are less SMYTH,S.B. Batteile Memortal Instrtute, Pacific Northwest Labo-than two meters per second. For higher wind speeds, l

retory May 1995.129pp. 9506220061. PNL 10521. 84394:066.

ARCON95 calculates about the senw concentrations as the This report documents the ARCON95 computer code devel-current procedure.

oped for the U.S. Nuclear Regulatory Commiseson Office of Nu-1 i

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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-referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.

SECONDARY REPORT NUMBER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER ANL-94/37 NUREG/CR4275 MCS 950302 NUREG/CR-6327 ANL 95/5 NUREG/CR4315 ORNL4713 NUREG/CR5857

/

P 4 MI 8=tl gig l8g sg8'8:=gPg4 a

BMi-2ir9 NuReG,CR4235 DMI-2180 NUREG/CR4251 ORNL/TM-11568 NUREG/CR5591 V05 N1 BMI-2182 NUREG/CR4297 ORNL/TM-12937 NUREG/CR4318 BMI 2184 NUREG/CR4300 ORNL/TM4789 NUREG/CR-6016 BNL-HUREG 51708 NUREG/CR3469 V08 ORNL/TM-9593 NUREG/CR-4219 V10 N2 BNL-NUREG 52399 NUREG/CR4144 V06 P1 PNL 10521 NUREG/CR4331 PNL 10548 NUREG/CR4330 BNL-NUREG-52399 NUREG/CR4144 V06 P2

[f8 DNL-NUREG 52410 NUREG/CR-5954 GC BNL/NUREG-52394 NUREG/CR6112 SAND 93-2078 NUREG/CR4109 CNWRA 94417 NUREG/CR6283 SAND 93 2185 NUREG/CR-6119 V01 INEL 94/0039 NUREG/CR4116 V10 SAND 93-2185 NUREG/CR-6119 V02 INEL-94/0278 NUREG/CR 5229 V07 UCAL-ID 118766 NUREG/CR-5657 INEL-95/0073 NUREG/CR4256 V01 UCRL-ID-119697 NUREG/CR4322 l

15

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Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agreement rcports in alphabetical order. Each narra 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.

ALLEN,M.D.

CALLAN,J.R.

NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE DIRECT CONTAINMENT HEATING IN SURRY.

AFTERLOADING BRACHYTHERAPY. Human Error And Cntical Tasks in Ftemote Afterloading Brachytherapy And Approaches For improved NUR$G CR-2850 V13: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREG CR 2 V 2: HUMAN FACTORS EVALUATION OF REMOTE RELEASES FROM NUCLEAR POWER PLANT S!TES IN 1991.

e AFTERLOADING BRACHYTHERAPY. Function And Task Analysis.

CAKER,0.C.

NUREG/CR.5975 RO1: INCENTIVE REGULATION OF INVESTOR-CAMP 9 ELL,P.L OWNED NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULA.

NUREG 1482: GUIDELINES FOR INSERVICE TESTING AT NUCLEAR TORS.

POWER PLANTS.

j SAKER,T.L CAPLIN,J.

NUREG/CR4046. ALERTNESS. PERFORMANCE, AND OFF-DUTY NUREG/CR-6307:

SUMMARY

OF COMMENTS RECEIVED AT WORK.

SLEEP ON 8-HOUR AND 12 HOUR NIGHT SHIFTS IN A SIMULATED SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO CONTINUOUS OPERATIONS CONTROL ROOM SETTING.

FACILITATE PUBLIC PARTICIPATION IN DECOMMISSIONING CARCH1,T.

NUREG 1415 V07 NO2: OFFICE OF THE INSPECTOR CELIA,M.A.

GENERAL Semiennual Report To Congress. October 1,1994 - March 31,1995-NUREG/CR4114 V02: AUXILIARY ANALYSES IN SUPPORT OF PER-t FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW-LEVEL BECK,8.T.

WASTE FACILITY.Two-Phase Flow And Contaminant Transport in Un-NUREGICR4116 V10: SYSTEMS ANALYSIS PROGRAMS FOR saturated Soils With Applecation To Low Level Radioactive Waste Dis-HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE) posat VERSION 5.0. Data Loading Manual.

CHARAK,1.

BERGERON,K.D.

NUREG/CR-6315. CANDU REACTORS. THEIR REGULATION IN NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY CANADA, AND THE IDENTIFICATION OF RELEVANT NRC SAFETY DIRECT CONTAINMENT HEATING IN SURRY.

ISSUES.

BINNING,P.

CHEN,G.

NUREG/CR4114 V02: AUXILIARY ANALYSES IN SUPPORT OF PER-NUREG/CR-6308. AN OVERVIEW OF INSTABILITY AND FINGERING FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW-LEVEL DURING IMMISCIBLE FLUID FLOW IN POROUS AND FRACTURED WASTE FACILITY.Two Phase Flow And Contanunant Transport in Un-MEDIA.

saturated Soils With Apphcation To Low. Level Radioactive Waste Dis-posal CHIN.E.

NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE UR$ /CR 6312: ASSESSMENT OF FIBER OPTIC PRESSURE SEN-A A N 8 Human m And CnMal Tads SORS' in Remote Afterloading Brachytherapy And Approaches For improved System Performance.

BLACK.S.C.

NUREG/CR4125 V02: HUMAN FACTORS EVALUATION OF REMOTE NUREG 1526: LESSONS LEARNED FROM EARLY fMPLEMENTATION AFTERLOADING BRACHYTHERAPY. Function And Task Analyses.

OF THE MAINTENANCE RULE AT NINE NUCLEAR POWER PLANTS.

CHOi,Y.H.

BRICHOUX,J.

NUREG/CR 6300: REFINEMENT AND EVALUATION OF CRACK-OPEN-NUREG/CR-6330: RESULTS OF REGULATORY IMPACT SURVEY OF ING AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH WALL INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE CRACKS IN PIPES.

OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS.

CHOPRA,0.K.

BRICKSTAD,5.

NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK OPEN-NUREG/CH4275. MECHANICAL PROPERTIES OF THERMALLY AGED ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL CAST STAINLESS STEELS FROM SHIPPINGPORT REACTOR COM-PONENTS.

CRACKS IN PIPES.

CHOWDHURY,A.H.

N R$d CR.6235: ASSESSMENT OF SHORT THROUGH-WALL CIR.

CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis. March SE S CITY O GON T

Y OLOG '

1990 December 1994 NUREG/CR-6299: EFFECTS OF TOUGHNESS ANISOTROPY AND COSLEN.

COMBINED TENSION. TORSION. AND BENDING LOADS ON FRAC-NUREG 1525: ASSESSMENT OF THE NRC ENFORCEMENT PRO.

TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

GRAM.

l NUREG/CR4300- REFINEMENT AND EVALUATION OF CRACK.OPEN.

I A A AN YSES FOR CIRCUMFERENTIAL THROUGH-WALL O

PM M MNh And User's Gudes. Version 1.8.3 September 1994.

90MPAS,S.E.

NUREG/CR4119 V02:

MELCOR COMPUTER CODE NUREG/CR4322: BUCKLING ANALYS!S OF SPENT FUEL BASKET.

MANUALS. Reference Manuals. Version 1.8.3 September 1994.

17 l

18 Personal Author index COLLINS.J.L GRIFFIN,J.l.

NUREG/CR4318: DATA

SUMMARY

REPORT FOR FISSION PRODUCT NUREG-1527: NRC'S OBJECT ORIENTED SIMULATOR INSTRUCTOR RELEASE TEST VI-7.

STATON.

CONGERA GRIFFIN,J.P.

NUREG/CR4330: RESULTS OF REGULATORY IMPACT SURVEY OF NUREG-1527; NRC'S OBJECT ORIENTED SIMULATOR INSTRUCTOR INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE STATON.

OFFICE OF NUCLE /.R MATERIALS SAFETY AND SAFEGUARDS.

GRODIN,M.

CORRELAAA NUREG 1415 V07 NO2: OFFICE OF THE INSPECTOR NUREG-1526: LESSONS LEARNED FROM EARLY IMPLEMENTATION GENERALSemiannual Report To Congress' October 1,1994 March OF THE MAINTENANCE RULE AT NINE NUCLEAR POWER PLANTS.

31,1995.

CORWIN,W.R.

NUREGICR 5591 V05 N1; HEAVY SECTION STEEL IRRADIATION NUREG CR 5954: EFFECT ON AGING ON PWR CHEMICAL AND PR A Semiannual Progress Report For September 1993 Through VOLUME CONTROL SYSTEM <

GWYNNE,J.W.

COX,0.F.

NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE NUREG/CR-5857: AGING OF TURBINE DRIVES FOR SAFETY-RELAT.

AFTERLOADING BRACHYTHERAPY. Human Error And Critcal Tasks ED PUMPS IN NUCLEAR POWER PLANTS.

NUREG/CR.6016: AGING AND SERVICE WEAR OF AIROPERATED in Remote Afterloading Brachytherapy And Approaches For improved System Performance.

VALVES USED IN SAFETY,RELATED SYSTEMS AT NUCLEAR NUREG/CR4125 V02: HUMAN FACTORS EVALUATION OF REMOTE POWER PLANTS.

AFTERLOADING BRACHYTHERAPY.Furction And Task Analysis.

DAVIS,E.C.

NUREG/CR4258 V01: FIELD LYS%'IER INVESTIGATONS TEST HARTFIELDAA.

RESULTS Low Level Weste N.a Base Program. Test Results For NUREG-0020 V19: LICENSED OPERATING REACTORS STATUS SUM.

MARY REPORT. Data As Of December 31,1994.(Gray Book 1)

Fiscal Years 1986, ilV 7,19% And 1989.

DELICATE,W.S.

HASMEMIAN,H.M.

NUREG/CR4297: MANAGEMENT CONCEPTS AND SAFETY APPLICA*

NUREG/CR4312: ASSESSMENT OF FIBER OPTIC PRESSURE SEN.

TONS FOR NUCLEAR FUEL FACluTIES.

SORS.

EASON,E.D.

HATTRUP,M.

l NUREG/CR4327. MODELS FOR EMBRITTLEMENT RECOVERY DUE NUREG/CR 6330: RESULTS OF REGULATORY IMPACT SURVEY OF TO ANNEAUNG OF REACTOR PRESSURE VESSEL STEELS-INDUSTRIAL AND MEDICAL MATERIALS UCENSEES OF THE OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS.

EISNER,H.

NUREG/CR4287: MANAGEMENT CONCEPTS AND SAFETY APPUCA-HELD P.R' CR.6251:

NUlkEG/

STAINLESS STEEL SUBMERGED ARC WELD TIONS FOR NUCLEAR FUEL FACluTIES.

FUSION UNE TOUGHNESS.

EMRITA NUREG 0933 S18. A PRIORITIZATION OF GENERIC SAFETY ISSUES.

HILTON,L.D.

NUREG/CR4256 V01: FIELD LYSIMETER INVESTIGATONS TEST FARMER,J.P.

RESULTS. Low-Level Waste Data Base Program. Test Results For NUREG/CR4312: ASSESSMENT OF FIBER OPTIC PRESSURE SEN.

Fiscal Years 1986,1987,1988, And 1989.

SORS.

FINDLAY,M.W.

HODGE.S.A.

NUREG/CR4256 V01: FIELD LYSIMETER INVESTIGATIONS - TEST NUREG/CR 6119 V01: MELCOR COMPUTER CODE MANUALS Pnmer RESULTS Low Level Waste Data Base Program. Test Results For And User's Guides. Version 1.8 3 September 1994.

Fiscal Years 1986,1987,1988, And 1989.

NUREG/CR4119 V02:

MELCOR COMPUTER CODE MANUALS Reference Manuals. Version 1.8.3 September 1994 FOWLER,RI.

NUREG/CR 0116 V10: SYSTEMS ANALYSIS PROGRAMS FOR HSIUNG.S M.

HANDSON INTEGRATED REUABlUTY EVALUATIONS (SAPHIRE)

NUREG/CR4283: FIELD SITE INVESTIGATION: EFFECT OF MINE VERSION 5 0. Data Loading Manual.

SEISMCITY ON GROUNDWATER HYDROLOGY.

FRANCINI,5-HUBER,0.

NUREG/CR 6235: ASSESSMENT OF SHORT THROUGH-WALL CIA.

NUREG 1415 V07 NO2: OFFICE OF THE INSPECTOR CUMFERENTIAL CRACKS IN PIPES.Expenments And Analysis. March GENERAL. Semiannual Report To Congress, October 1,1994. March 1990 December 1994-31,1995.

j FRANCINIA HUGHES,X NUREG/CR4297: FRACTURE EVALUATIONS OF FUSION UNE NUREG/CR4330: RESULTS OF REGULATORY IMPACT SURVEY OF CRACKS IN NUCLEAR PlPE BIMETALLIC WELDS INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS.

GERHARD,M.A.

NUREG/CR-5657: AUTOCASK (AUTOMATIC GENERATION OF 3-0 HYMAN.C.R CA S

crtx:omputer Based System For Shipping Cask And User's Guides. Version 1.8.3 September 1994.

NUREG/CR-6119 V02:

MELCOR COMPUTER CODE OHADIALIA MANUALS Reference Manuals. Version 1.8.3 September 1994.

NUREG/CR-4599 V04 N1; SHORT CRACKS IN PIPING AND PIPING WELDS Seventh Program Report March 1993 December 1994.

i NUREG/CR 8004: PROBABluSTIC PIPE FRACTURE EVALUATIONS JASTROW J.D.

NUREG/CR-5229 V07: FIELD LYSIMETER INVESTIGATONS: LOW-FOR LEAK. RATE-DETECTION APPUCATIONS.

l NUREG/CR4235: ASSESSMENT OF SHORT THROUGH-WALL CIR-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis. March FISCAL YEAR 1994. Annual Report.

NUREG/CR4256 VO1: FIELD LYSIMETER INVESTlGATONS TEST 1990 December 1994.

NUREG/CR-6299: EFFECTS OF TOUGHNESS ANISOTROPY AND RESULTS Low-Level Waste Data Base Program. Test Results For COMBINED TENSION, TORSON, AND BENDING LOADS ON FRAC.

Fiscal Years 1986,1987,1988, And 1989.

TURE BEHAVIOR OF FERRITC NUCLEAR PIPE.

NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK-OPEN-JO,J.

ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL NUREG/CR4144 V06 P1: EVALUATON OF POTENTIAL SEVERE AC-CRACKS IN PlPES.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONC AT I

1

Person:1 Auth:r index 19 SURRY, UNIT 1 Evaluation Of Severe Accxtent Risk Dunn0 M4 Loop NUREG/CR4144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC-Operations Main Report.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC.

SURRY, UNIT 1.Evaluaton Of Severe Accident Risk Dunng Mid-Loop CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Operations.Appendees.

SURRY, UNIT 1. Evaluation Of Severe Accident Risk Dunng Mid-loop Operations.Appendees.

LORENZ,R.A.

NUREG/CR4318 DATA

SUMMARY

REPORT FOR FISSION PRODUCT JOHNSON,J.C.

RELEASE TEST VI.7.

NUREG/CR4114 V02: AUxlLIARY ANALYSES IN SUPPORT OF PER-FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW-LEVEL MADER,E.V.

WASTE FACILITY.Two-Phase Flow And Contarrunant Transport in Un-NUREG/CR4327: MODELS FOR EMBRITTLEMENT RECOVERY DUE saturated boils With Appicaton To Low Level Radioactive Waste Dis-TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

posal.

MARSCHALL,C.W.

KASUMOVIC.J.

NUREG/CR4235 ASSESSMENT OF SHORT THROUGH-WALL CIR.

NUREG/CR 6125 V01: HUMAN FACTORS EVALUATION OF REMO1E CUMFERENTIAL CRACKS IN PIPES.Expenments And Analysis, March AFTERLOADING BRACHYTHERAPY. Human Error And Cntcal Tasks iggo. December 1994.

In Remote Afterloader:g Brachytherapy And Approaches For improved NUREG/CR4299. EFFECTS OF TOUGHNESS ANISOTROPY AhlD System Performance COMBINED TENSION, TORSION. AND BENDING LOADS ON FRAC.

TURE BEHAV:OR OF FERRITIC NUCLEAR PIPE.

y NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE MCCONNELL.J.W.

AFTERLOADING BRACHYTHERAPY Human Error Ana Cntcal Tasks T UGEG/CR-5229 V07: FIELD LYSIMETER INVESTIGATIONS: LOW.

In Remote Afterloading Brachytherapy And Approaches For improved LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR System Performance-FISCAL YEAR 1994. Annual Report.

NUREG/CR4125 V02: HUMAN FACTORS EVALUATION OF REMOTE NUREG/CR-6256 VOI: FIELD LYSIMETER INVESTIGATIONS TEST AFTERLOADING BRACHYTHERAPY.Functon And Task Analysis FIESULTS Low-Level Waste Data Base Prograrn. Test Results For Ascal Years M.198WE W 19%.

KHAN.T.A.

NUREG/CR 3469 V08. OCCUPATIONAL DOSE REDUCTION AT NU-MCELHANEY,K.L.

CLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY OF SELECT.

NUREG/CR4016: AGING AND SERVICE WEAR OF AIR-OPERATED ED READINGS IN RADIATION PROTECTION AND ALARA.

VALVES USED IN SAFETY-RELATED SYSTEMS AT NUCLEAR POWER PLANTS.

KlER,P.H.

NUREG/CR-6315. CANDU REACTORS. THEIR REGULATION IN MCKINNEY,M.D CANADA, AND THE IDENTIFICATION OF RELEVANT NRC SAFETY NUREG/CR 5975 ROI: INCENTIVE REGULATION OF INVESTOR-ISSUES.

OWNED NUCLEAR POWER PLANTS BY PUBLIC UTIUTY REGULA-TORS.

KILINSKI.T.

NUREG/CR-6235 ASSESSMENT OF SHORT THROUGH-WALL CIR-ME C

CUMFE TI CRACKS IN PIPES Experunents And Analyssa, March CENSED ACTIVITIES. Maior 1ssues in The implementation Of ICRP/

KNUDSON.D.L NCRP Dose Limit Recornmendations Final Report.

NUREG/CR 6109 THE PROBABILITY OF CONTAINMENT FAILURE BY DIRECT CONTAINMENT HEATING IN SURRY.

MELBER,S.

NUREGICR-6330. RESULTS OF REGULATORY IMPACT SURVEY OF i

KRISHNASWAMY,P.

INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS.

WELDS Seventh Program Report March 1973. December 1994.

NUREG/CR 6235: ASSESSMENT OF SHORT THROUGH-WALL CIR-MERRITT.C.R.

CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis March NUREG/CR-5975 RO1: INCENTIVE REGULATION OF INVESTOR-1990. December 1991 OWNED NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULA.

NUREGICR-6299 EFFECTS OF TOUGHNESS ANISOTROPY AND TORS.

COMBINED TENSION. TORSION. AND BENDING LOADS ON FRAC-TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

MlURA,N.

NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK OPEN-NUREG/CR4235. ASSESSMENT OF SHORT THROUGH. WALL CIR-ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis. March CRACKS IN PIPES 1990. December 1994.

LACH.D.

MOHAN,R.

NUREG/CR4330: RESULTS OF REGULATORY IMPACT SURVEY OF NUREG/CR4299 EFFECTS OF TOUGHNESS ANISOTROPY AND INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE COMBINED TENSION, TORSION, AND BENDING LOADS ON FRAC.

OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

LE E,A.S.

MONTELEONE,S.

NUREG/CR-6322: BUCKLING ANALYSIS OF SPENT FUEL BASKET.

NUREG/CP 0140 V01: PROCEEDINGS OF THE TWENTY SECOND WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses-LEPAGE R.P.

se;n, Advanced instrurrentaoon & Cor: trol Hardware & Software, NUREG/CR4125 VOI: HUMAN FACTORS EVALUATION OF REMOTE Human Faclors Research,IPE & PRA.

AFTERLOADING BRACHYTHERAPY. Human Error And Cntcal Tasks NUREG/CP4140 V02: PROCEEDINGS OF THE TWENTY-SECOND In Remote Afterloading Brachytherapy And Approaches For improved WATER REACTOR SAFETY INFORMATION MEETING. Severe Acci.

System Performance.

dont Research, Tharmal Hydrauke Research For Advanced Passive NUREG/CR 6125 V02: HUMAN FACTORS EVALUATION OF REMOTE LWRs.

h.Burnup Fuel Behawor.

AFTERLOADING BRACHYTHERAPY. Function And Task Analysis NUREG/ -0140 V03: PROCEEDINGS OF THE TWENTY.SECOND LIE 8ERMAN.J.

WATER REACTOR SAFETY INFORMATION MEETING Pnmary Sys-NUREG 1525: ASSESSMENT OF THE NRC ENFORCEMENT PRO.

tens integnty, Stnictural And Seismc Engineenng. Aging Research.

GRAM.

Products And Appleations.

LIN.C.C.

MOORE R.A.

NUREG/CR-6144 V06 P1: EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT AFTERLOADING BRACHYTHERAPY. Human Error And Cntcal Tasks SURRY, UNIT 1 Evaluation Of Severe Accident Risk Dunng Med. Loop in Remote Afterloading Brachytherapy And Approaches For improved Operations Main Report.

System Performance.

20 Personal Author index MUSAYl,V.

NUREG/CR-0200 V3 R04: SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR4144 V06 PI: EVALUATION OF POTENTIAL SEVERE AC-PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CENSING EVALUATION. Mescellaneous.

SURRY, UNIT 1. Evaluation Of Severe Accdent Risk Dunng Md-Loop Operations Main Report.

PAUL,0.

NUREG/CR4144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR4004: PROBABlUSTIC PIPE FRACTURE EVALUATIONS CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT FOR LEAK-RATE-DETECTION APPLICATIONS.

SURRY, UNIT 1. Evaluation Of Severe Accdent Risk Dunng Md. Loop UREG/ 4219 V10 N2: HEAVY SECTION STEEL TECHNOLOGY MUCKLER.F.A.

PROGRAM Semiannual Progress Report For Apr!LSeptember 1993.

NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY. Human Error And Cntscal Tasks PETRONE.C.D.

In Remote Afterloading Brachytherapy And Approaches For improved NUREG 1526: LESSONS LEARNED FROM EARLY IMPLEMENTATION S stem Performance.

OF THE MAINTENANCE RULE AT NINE NUCLEAR POWER PLANTS.

NU EG/CR4125 V02: HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY. Function And Task Analysis.

REG /CR-6283: FIELD SITE INVESTIGATION: EFFECT OF MINE NEILSON,R.M.

SEISMICITY ON GROUNDWATER HYDROLOGY.

NUREG/CR.6266 V01: FIELD LYSIMETER INVESTIGATIONS - TEST NUR'EG R4109 THE PROBABILITY OF CONTAINMENT FAILURE BY Year 98 ' 9

,A 1 9 DIRECT CONTAINMENT HEATING IN SURRY.

NELSON.E.E.

NUREG/CR4327: MODELS FOR EMBRITTLEMENT RECOVERY DUE QUICK,K.S.

TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY DIRECT CONTAINMENT HEATING IN SURRV.

NEUMAN,S.P.

NUREG/CR-6308 AN OVERVIEW OF INSTABILITY AND FINGERING OUINN,M.L DURING IMMISCIBLE FLUID FLOW IN POROUS AND FRACTURED NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE MEDIA.

AFTERLOADING BRACHYTHERAPY. Human Error And Cntical Tasks in Remote Afterloading Brachytherapy And Approaches For improved NEYMOTIN L System Performance.

NUREG/CR4144 V06 P1: EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT RAHMAN S.

SURRY, UNIT 1 Evaluation Of Severe Accdent Risk During Md-loop NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING Operations Main Report.

WELDS Seventh Program Report March 1993. December 1994.

NUREG/CR4144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC.

NUREG/CR4004: PROBABluSTIC PIPE FRACTURE EVALUATIONS CIDENTS OURING LOW POWER AND SHUTDOWN OPERATIONS AT FOR LEAK.AATE. DETECTION APPLICATIONS.

SURRY, UNIT 1. Evaluation Of Severe Accident Risk Dunng Md-Loop NUREG/CR4235: ASSESSMENT OF SHORT THROUGH-WALL CIR-Operations. Appendices.

CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis. March 1990 - December 1994.

NORTON,L NUREG/CR4297: FRACTURE EVALUATIONS OF FUSION LINE WUREG-1415 V07 NO2: OFFICE OF THE INSPECTOR CRACKS IN NUCLEAR PIPE BlMETALUC WELDS.

GENERAL. Semiannual Report To Congress. October 1,1994. March NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACKOPEN-31,1995.

ING. AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL CRACKS IN PIPES.

O'DONNELL,E.

NUREG/C44918 V08: CONTROL OF WATER INFIL1 RATION INTO RAMSDELL,J.V.

NEAR SURFACE LLW DISPOSAL UNITS. Progress Report Of Field Ex.

NUREG/CR4331: ATMOSPHERIC RELATIVE CONCENTRATIONS IN penments At A Humed Region Site.Beltsville. Maryland.

BUILDING WAKES.

ODETTE,0.R.

RIDKY.R.W.

fdUREG/CR-6327: MODELS FOR EMBRITTLEMENT RECOVERY DUE NUREG/CR-4918 V08. CONTROL OF WATER INFILTRATION INTO TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

NEAR SURFACE LLW DISPOSAL UNITS. Progress Report Of Field Ex-penments At A Humid Region Sita.Beltsville. Maryland.

NUREG/CR4283: FIELD SITE INVESTIGATION: EFFECT OF MINE ROGERS,R.D.

SEISMICITY ON GROUNDWATER HYDROLOGY, NUREG/CR-5229 V07: FIELD LYSIMETER INVESTIGATIONS: LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR ORNSTEIN,H.L FISCAL YEAR 1994. Annual Report.

NUREG 1275 VII: OPERATING EXPERIENCE FEEDBACK REPORT -

NUREG/CR.6256 V01. FIELD LYSIMETER INVESTIGATIONS. TEST TURBINE-GENERATOR OVERSPEED PROTECTION RESULTS Low Level Waste Data Base Program. Test Results For SYSTEM Commercial Power Reactors.

Fiscal Years 1986,1987,1988. And 1989 OS80RNE.M.F.

ROSENFIELD,A.R.

NUREG/CR4318; DATA

SUMMARY

REPORT FOR FISSION PRODUCT NUREG/CR4251: STAINLESS STEEL SUBMERGED ARC WELD RELEASE TEST VI 7.

FUSION LINE TOUGHNESS.

NUREG/CR4297: FRACTURE EVALUATIONS OF FUSION LINE PAGE.G.

CRACKS IN NUCLEAR PIPE BIMETALLIC WELDS.

NUREG/CR-6307:

SUMMARY

OF COMMENTS RECElVED AT WORK.

SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO RUDLAND,D.

FACILITATE PUBLIC PARTICIPATION IN DECOMMISSIONING NUREG/CR.4599 V04 Nt: SHORT CRACKa, =. PIPING AND PIPING CASES.

WELDS Seventh Program Report March 1993 December 1994.

PARKS.C.V.

SANDERS R.L NUREG/CR-0200 V1 R04: SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR.6119 V01: MELCOR COMPUTER CODE MANUALS Pnmer PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-And User's Guides. Versson 18.3 September 1994.

CENSING EVALUATION Control Modules.

NUREGICA 6119 V02:

MELCOR COMPUTER CODE NUREG/CR4200 V2P1R4: SCALE: A MODULAR CODE SYSTEM FOR MANUALS. Reference Manusla Version 1.8.3 September 1994.

PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-CENSING EVALUATION Functional ModuM1-F8.

SANFORD W.E.

NUREG/CR0200 V2P2R4: SCALE: A MOD)TR CODE SYSTEM FOR NUREG/CR-5229 V07: FIELD LYSIMETER INVESTIGATIONS. LOW.

PERFORMING STANDARDlZED COMPUTER ANALYSES FOR Lt.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR CENSING EVALUATION Functional Modules F9.F16.

FISCAL YEAR 1994. Annual Report.

l

Personal Author index 21 SAUNDERS,W.M.

STADLER,L NUREG/CR-6125 V01: HUMAN FACTORS EVALUATON OF REMOTE NUREG 1350 V07: NUCLEAR REGULATORY COMMISSON INFORMA.

AFTERLOADING BRACHYTHERAPY Human Error And Cntcal Tasks TlON DIGEST.1995 Eston.

In Remote Afterloadng Brachytherapy And Approaches For improved System Performance, STAMPS.D.W.

NUREG/CR4125 V02: HUMAN FACTORS EVALUATON OF REMOTE NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY AFTERLOADING BRACHYTHERAPY. Function And Tar.k Analysis.

DIRECT CONTAINMENT HEATING IN SURRY.

SCHOENFELD L STAUNTON,R.H.

NUREG/CR4125 VOI: HUMAN FACTORS EVALUATION OF REMOTE NUREG/CR4018. AGING AND SERVICE WEAR OF AIR OPERATED AFTERLOADING BRACHYTHERAPY. Human Error And Cntcal Tasks VALVES USED IN SAFETY-RELATED SYSTEMS AT NUCLEAR in Remote Afterloadng Brachytherapy And Approaches For improved POWER PLANTS System Performance.

NUREG/CR4125 V02: HUMAN FACTORS EVALUATION OF REMOTE STRUCKMEYER,R.

AFTERLOADING BRACHYTHERAPY. Function And Task Analysis.

NUREG-0837 V15 N01: NRC TLD DIRECT RADIATON MONITORING NETWORK. Progress Report. January-March 1905.

NUREG/CR-4918 V08: CONTROL OF WATER INFILTRATION INTO STUART,D.S.

NEAR SURFACE LLW DISPOSAL UNITS. Progress Report Of Field Ex.

NUREG/CR4119 V01. MELCOR COMPUTER CODE MANUALS Pnmer penments At A Humed Region Site.Beltselle. Maryland.

And User's Guides. Verseon 1.8.3 September 1994.

NUREG/CR4119 V02:

MELCOR COMPUTER CODE SCOTT.P.

MANUALS. Reference Manuals Version 1.8.3 September 1994.

NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING WELDS Seventh Program Report March 1993 December 1994.

SULUVAN.S.G.

NUREG/CR4235: ASSESSMENT OF SHORT THROUGH-WALL CIR.

NUREG/CR-3469 V08: OCCUPATIONAL DOSE HEDUCTION AT NU-CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis. March CLEAR POWER PLANTS: ANNOTATED BIBUOGRAPHY OF SELECT.

1990 December 1994.

ED READINGS IN RADIATION PROTECTON AND ALARA.

NUREG/CR4297: FRACTURE EVALUATONS OF FUSION LINE CRACKS IN NUCLEAR PIPE BIMETALUC WELDS.

SULUVAN,T.M.

NUREG/CR 5229 V07: FIELD LYSIMETER INVESTIGATONS: LOW.

SCOTTLR.S.

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR-6287: MANAGEMENT CONCEPTS AND SAFETY APPUCA-FISCAL YEAR 1994. Annual Report.

TIONS FOR NUCLEAR FUEL FACILITIES.

SUMMERS,R.M.

SEELY.H.E.

NUREG/CR.6119 V01: MELCOR COMPUTER CODE MANUALS.Pnmer NUREG/CR-5975 ROI: INCENTIVE REGULATON OF INVESTOR-And User's Guides. Version 18 3 September 1994.

OWNED NUCLEAR POWER PLANTS BY PUBUC UTluTY REGULA.

NUREG/CR4119 V02:

MELCOR COMPUTER CODE TORS.

MANUALS. Reference Manuals Version 1.8.3 September 1994.

SERIG,DJ.

TADIOS,E.L NUREG/CR4125 V01: HUMAN FACTORS EVALUATON OF REMOTE NUREG/CR4109: THE PROBABluTY OF CONTAINMENT FAILURE BY i

j AFTERLOADING BRACHYTHERAPY. Human Error And Cntcal Tasks DIRECT CONTAINMENT HEATING IN SURRY.

In Remote Afterloading Brachytherapy And Approaches For improved System Performance.

TAM.P.S.

NUREG/CR4125 V02: HUMAN FACTORS EVALUATON OF REMOTE NUREG 0847 S15: SAFETY EVALUATION REPORT RELATED TO THE AFTERLOADING BRACHYTHERAPY. Function And Task Analysis.

OPERATON OF WATTS BAR NUCLEAR PLAN 1, UNITS 1 AND

2. Docket Nos. 50-390 And 50 391 (Tennessee Valley Authority)

(

SHACK W.J.

NUREG/CR4275: MECHANICAL PROPERTIES OF THERMALLY AGED TANIGUCHl,M.

CAST STAINLESS STEELS FROM SHIPPINGPORT REACTOR COM.

NUREG/CR 6308. AN OVERVIEW OF INSTABluTY AND FINGERING PONENTS.

DURING IMMISCIBLE FLUID FLOW IN POROUS AND FRACTURED MEDIA.

SIMONEN,C.A.

NUREG/CR4331: ATMOSPHERIC RELATIVE CONCENTRATIONS IN THOMPSON,$.L BUILDING WAKES.

NUREG/CR4119 VOI: MELCOR COMPUTER CODE MANUALS. Primer And User's Guides. Version 1.8 3 September 1994.

SMITH,C.L.

NUREG/CR4119 V02:

MELCOR COMPUTER CODE NUREG/CR-6116 V10: SYSTEMS ANALYSIS PROGRAMS FOR MANUALS Referenew Manuals. Version 1.8.3 September 1994.

HANDSON INTEGRATED REUABluTY EVALUATIONS (SAPHIRE)

VERSION 5.0 Data Loading Manual.

TRAVIS,J.R.

NUREG/CR4316 DATA

SUMMARY

REPORT FOR FISSION PRODUCT SMITH.D.

RELEASE TEST VI 7.

NUREG/CR4307:

SUMMARY

OF COMMENTS RECEIVED AT WORK.

SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO TRAVIS,R.J.

FACluTATE PUBUC PARTICIPATION IN DECOMMISSIONING NUREG/CR-5954: EFFECT ON AGING ON PWR CHEMICAL AND CASES.

VOLUME CONTROL SYSTEM.

I SMITH,R.C.

VANHORN,R.L NUREG/CR4119 V01: MELCOR COMPUTER CODE MANUALS Pnmer NUREG/CR4116 V10: SYSTEMS ANALYSIS PROGRAMS FOR And User's Guides. Version 1.8.3 tomber 1994.

HANDS-ON INTEGRATED REUABluTY EVALUATONS (SAPHIRE)

NUREG/CR4119 V02:

MEL COMPUTER CODE VERSION 5.0 Deta Loading Manual.

MANUALS Reference Manuals Version 1.8.3 September 1994.

WESSTER,C.S.

SMYTH,S.S.

NUREG/CR4318: DATA

SUMMARY

REPORT FOR FISSION PRODUCT NUREG/CR4331: ATMOSPHERIC RELAT!VE CONCENTRATIONS IN RELEASE TEST VI-7.

BUILDING WAKES.

WIBUN,C.

l SOMMER,S.C.

NUREG/CR4307:

SUMMARY

OF COMMENTS RECElVED AT WORK.

NUREG/CR-5657: AUTOCASK (AUTOMATIC GENERATION OF 3-D SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO CASK MODELS).A Microcomputer Based System For Shipping Cask FACluTATE PUBUC PARTICIPATON IN DECOMMISSONING Design Review Analysis.

CASES.

SPENCER.S.W.

WILKOWSKI,G.M.

NUREG/CR4109: THE PROBABluTY OF CONTAINMENT FAILURE BY NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING j

DIRECT CONTAINMENT HEATING IN SURRY.

WELDS. Seventh Program Report March 1993 December 1994.

22 Personal Author index NUREG/CR4004: PROBA86USTIC PIPE FRACTURE EVALUATIONS WOLPRAM,LM.

FOR LEAKRATE DETECTION APPUCATIONS-NUREG/CR-6116 V10: SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR4235: ASSESSMENT OF SHORT THROUGH-WALL CIR-HANDSON INTEGRATED REUABluTY EVALUATONS (SAPHIRE)

CUMFERENTiti CRACKS IN PIPES.Expenments And Analysis, March VERSION 5.0.Deta Lomeng Manuel.

1990. December 1994.

NUREG/CR4251: STAINLESS STEEL SUBMERGED ARC WELD WRNJ.E.

NUREG/CR4327: MODELS FOR EMBRITTLEMENT RECOVERY DUE NURE CR 297 FRA T RE EVALUATONS OF FUSION UNE TO ANNEAUNG OF REACTOR PRESSURE VESSEL STEELS.

CRACKS IN NUCLEAR PIPE BIMETALUC WELDS.

NUREG/CR4299: EFFECTS OF TOUGHNESS ANISOTROPY AND E d'**

COMBINED TENSION, TORSION, AND BENDING LOADS ON FRAC-NUREG/CR-3469 V08: OCCUPATIONAL DOSE REDUCTION AT NU-TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

CLEAR POWER PLANTS: ANNOTATED BIBUOGRAPHY OF SELECT-NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK OPEN-ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGHWALL ED READINGS (N RADIATION PROTECTION AND ALARA.

CRACKS !N PlPES.

B l

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

ACR$ Report 86 metallic Wood NUREG-1125 V16: A COMPILATON OF REPORTS OF THE ADVISORY NUREG/CR4297: FRACTURE EVALUATONS OF FUSION LINE COMMITTEE ON REACTOR SAFEGUARDS 1994 Annual.

CRACKS IN NUCLEAR PIPE BIMETALLIC WELDS.

ALARA Brachytherapy NUREG/CR 3469 V08. OCCUPATIONAL DOSE REDUCTION AT NU-NUREG/CR4125 V01: HUMAN FACTORS EVALUATON OF REMOTE CLEAR POWER PLANTS ANNOTATED BIBLOGRAPHY OF SELECT-AFTERLOADING BRACHYTHERAPY. Human Error And Cntical Tasks ED READINGS IN RADIATON PROTECTION AND ALARA.

In Remote Afterloading Brachytherapy And Approaches For improved System Performance.

ASME Code NUREG/CR4125 V02: HUMAN FACTORS EVALUATON OF REMOTE NUREG 1482: GUIDELINES FOR INSERVICE TESTING AT NUCLEAR AFTERLOADING BRACHYTHERAPY. Function And Task Analysis.

POWER PLANTS.

Buckl6ng Analyelo AUTOCASK NUREG/CR4322: BUCKLING ANALYSIS OF SPENT FUEL BASKET.

NUREG/CR 5657: AUTOCASK (AUTOMATIC GENERATON OF 3-D j

CASK MODELS).A Microcomputer Based System For Shipping Cask Build 6ng Wake Design Review Analysis.

NUREG/CR4331: ATMOSPHERIC RELATIVE CONCENTRATIONS IN BUILDING WAKES.

NUREG 1280 R01: STANDARD FORMAT AND CONTENT ACCEPT-CANDU Reactor ANCE CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNT-NUREG/CR4315: CANDU REACTORS, THEIR REGULATON IN ING (MC&A) REFORM AMENDMENT.

CANADA AND THE IDENTIFICATION OF RELEVANT NRC SAFETY Accounting NUREG 1280 R01: STANDARD FORMAT AND CONTENT ACCEPT

• Cap 614ery Barrier ANCE CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNT.

NUREG/CR-4918 V08: CONTROL OF WATER INFILTRATION INTO ING (MC&A) REFORM AMENDMENT-NEAR SURFACE LLW DISPOSAL UNITS. Progress Report Of Field Ex.

penments At A Humid Region SittBeweWaM Advanced Reactor NUREG/CR4312: ASSESSMENT OF FIBER OPTIC PRESSURE SEN-Circumferential Crack SORS.

NUREG/CR4235: ASSESSMENT OF SHORT THROUGH-WALL CIR-CUMFERENTIAL CRACKS IN PIPES.Expenments And Analysis, March UREG/CR 5857. AGING OF TURBINE DRIVES FOR SAFETY-RELAT.

NUR G/C FECTS OF TOUGHNESS ANISOTROPY AND 8 ED MSW, WSC% AW MM MS m NC NURE 5 54 FFE AGI G PWR CHEMICAL AND TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

VOLUME CONTROL SYSTEM NUREG/CR4016: AGING AND SERVICE WEAR OF AIR-OPERATED VALVES USED IN SAFETY-RELATED SYSTEMS AT NUCLEAR NUR 25: ASSESSMENT OF THE NRC ENFORCEMENT PRO-POWER PLANTS.

GRAM.

Aging Research Code System NUREG/CP 0140 V03: PROCEEDINGS OF THE TWENTY SECOND NUREG/CR 0200 V1 R04: SCALE: A MODULAR CODE SYSTEM FOR WATER REACTOR SAFETY INFORMATON MEETING.Pnmary Sys.

PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-tems Integnty, Structural And Seismic Engineenng, Aging Research, CENSING EVALUATION. Control Modules.

Products And Applications.

NUREG/CR4200 V2PIR4: SCALE: A MODULAR CODE SYSTEM FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-Alr-Operated Valve CENSING EVALUATION. Functional Modules F1-F8.

NUREG/CR4016; AGING AND SERVICE WEAR OF AIR OPERATED NUREG/CR 0200 V2P2R4: SCALE A MODULAR CODE SYSTEM FOR VALVES USED IN SAFETY RELATED SYSTEMS AT NUCLEAR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-POWER PLANTS.

CENSING EVALUATON. Functional Modules F9-F16.

NUREG/CR4200 V3 R04: SCALE: A MODULAR CODE SYSTEM FOR Alertnese PERFORMING STANDARDtZED COMPUTER ANALYSES FOR LI-NUREG/CR4046. ALERTNESS. PERFORMANCE, AND OFF-DUTY CENSING EVALUATION. Miscellaneous.

SLEEP ON 8-HOUR AND 12 HOUR NIGHT SHIFTS IN A SIMULATED CONTINUOUS OPERATONS CONTROL ROOM SETTING.

Computer Analyses NUREG/CR 0200 V1 A04: SCALE: A MODULAR CODE SYSTEM FOR Annealing PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-f NUREG/CR4327: MODELS FOR EMBRITTLEMENT RECOVERY DUE CENSING EVALUATION Control Modules.

TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

f NUREG/CR-0200 V2PIR4: SCALE: A MODULAR CODE SYSTEM FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-I Atmospheric Dieperolon l

NUREG/CR4331: ATMOSPHERIC RELATIVE CONCENTRATIONS IN CENSING EVALUATION. Functional Modules F1-F8.

NUREGICR4200 V2P2R4: SCALE: A MODULAR CODE SYSTEM FOR BUILDING WAKES.

PERFORMING STANDARDIZED COMPUTER ANALYSES FOR L1-Austenitec Steel CENSING EVALUATION, Functional Modules F9-F16.

NUREG/CR4235; ASSESSMENT OF SHORT THROUGH-WALL CIR-NUREG/CR-0200 V3 R04: SCALE: A MODULAR CODE SYSTEM FOR CUMFERENTIAL CRACKS IN PIPES.Expenments And Anatysis, March PERFORMING STANDARDt2ED COMPUTER ANALYSES FOR L1-1990 December 1994.

CENSING EVALUATON. Miscellaneous.

23

24 Sut$ect index Contelnment Failure Fatigue NUREG/CR4100: THE PROBA81LITY OF CONTAINMENT FAILURE BY NUREG/CR4048: ALERTNESS, PERFORMANCE, AND OFF-DUTY DIRECT CONTAINMENT HEATING IN SURRY.

SLEEP ON 8-HOUR AND 12 HOUR NIGHT SHIFTS IN A SIMULATED CONTINUOUS OPERATIONS CONTROL ROOM SETTING.

y,,,,,,,,

NUREG/CR4114 V02 AUXILIARY ANALYSES IN SUPPORT OF PER-FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW LEVEL NUREG/CR4312: ASSESSMENT OF FIBER OPTIC PRESSURE SEN.

WASTE FACILITY.Two Phase Flow And Contaminent Transport in Un-SORS.

esturated Soils With Application To Low-Level Radioactwo Weste Dis-P***

Field Lysimeter Contred Reem NUREG/CR 5229 V07; FIELD LYSIMETER INVESilGATIONS: LOW-NUREG/CR4048: ALERTNESS, PERFORMANCE, AND OFF DUTY LEvD. WASTE DATA BASE DEVELOPMENT PROGRAM FOR SLEEP ON 8-HOUR AND 12 HOUR NIGHT SHIFTS IN A SIMULATED FISCAL YEAR 1994. Annual Report.

CONTINUOUS OPERATIONS CONTROL ROOM SETTING.

NUREG/CR-8258 VOI: FIELD LYSIMETER INVESTIGATIONS TEST NUREG/CR4331 ATMOSPHERIC RELATIVE CONCENTRATIONS IN RESULTS. Low-Level Weste Data Base Program. Test Resulte For BUILDING WAKES.

Fiscal Years 1988,1987,1988, And 1989.

Cooient Cloenup System Final Environmental testement NUREG/CR 5964: EFFECT ON AGING ON PWR CHEMICAL AND NUREG 0498 S01: FINAL ENVIRONMENTAL STATEMENT RELATED VOLUME CONTROL SYSTEM.

TO THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 Creeg AND 2. Docket Nos. 50-390 And 50-391.(Tennessee Valley Authortty)

NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK.OPEN-Finenoiel Statement ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL CRACKS IN PIPES.

NUREG-1470 V04: FINANCIAL STATEMENT FOR FISCAL YEAR 1994.

(

Data Sununary Report Fleelan Product Relsone NUREG/CR4318 DATA

SUMMARY

REPORT FOR FISSION PRODUCT NUREG/CR4318: DATA

SUMMARY

REPORT FOR FISSION PRODUCT RELEASE TEST VI-7.

RELEASE TEST VI-7.

Decommiseloning Fracture NUREG/CR4307:

SUMMARY

OF COMMENTS RECEIVED AT WORK-NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO WELDS. Seventh Program Report March 1993 - December 1994.

FACILITATE PUBUC PARTICIPATION IN DECOMMISSIONING NUREG/CR4299: EFFECTS OF TOUGHNESS ANISOTROPY AND CASES.

COMBINED TENSION, TORSION, AND BENDING LOADS ON FRAC-Direct Containment Hosting TURE BEHAvlOR OF FERRITIC NUCLEAR PIPE.

NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK OPEN.

DIRECT CONTAINMENT HEATING IN SURRY.

ING AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL CRACKS IN PIPES, Does Commitment NUREG/CR-2850 V13: DOSE COMMITMENTS DUE TO RADIOACTIVE Fracture Flow RELEASES FROM NUCLEAR POWER PLANT SITES IN 1991.

NUREG/CR4308: AN OVERVIEW OF INSTABILITY AND FINGERING DURING IMMISCIBLE FLUID FLOW IN POROUS AND FRACTURED Doelmstry MEDIA' NUREG/CR4112: IMPACT OF REDUCED DOSE LIMITS ON NRC Lt.

l CENSED ACTIVITIES. Maior leeues in The Irnplementation Of ICRP/

Fracture Mechanico NCRP Doce Urrwt Recommendatione Fanel Report.

NUREG/CR4004. PROBABILISTIC PIPE FRACTURE EVALUATIONS EPICOR-Ig FOR LEAK-RATE-DETECTION APPLICATIONS.

NUREG/CR-5229 V07; FIELD LYSIMETER INVESTIGATIONS: LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR Fracture Toughnese FISCAL YEAR 1994. Annual Report.

NUREG/CR4275: MECHANICAL PROPERTIES OF THERMALLY AGED NUREG/CR4258 V01: FIELD LYSIMETER INVESTIGATIONS - TEST CAST STAINLESS STEELS FROM SHIPPINGPORT REACTOR COM-j RESULTS. Low-Level Weste Data Base Program. Test Results For PONENTS.

I Flecal Years 1988,1987,1988, And 1989.

Fractured Media j

Earthegushe NUREG/CR4308: AN OVERVIEW OF INSTABILITY AND FINGERING i

NUREG/CR4283: FIELD SITE INVESTIGATION: EFFECT OF MINE DURING IMMISCIBLE FLUID FLOW IN POROUS AND FRACTURED SEISMICITY ON GROUNDWATER HYDROLOGY-MEDIA.

Embrittlement Fractured Zone NUREG/CR4275: MECHANICAL PROPERTIES OF THERMALLY AGED NUREG/CR4283: FIELD SITE INVESTIGATION: EFFECT OF MINE CAST STAINLESS STEELS FROM SHIPPINGPORT REACTOR COM-PONENTS SEISMICITY ON GROUNDWATER HYDROLOGY.

NUREG/CR4327: MODELS FOR EMBRITTLEMENT RECOVERY DUE TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

U CR 8318: DATA

SUMMARY

REPORT FOR FISSION PRODUCT Enforcement Action RELEASE TEST VI-7.

NUREG 0940 V14 N1 P1: ENFORCEMENT ACTIONS: SIGNIFICANT AC.

TIONS RESOLVED, REACTOR LICENSEES.Ouarterly Progress Fundamental Nucteer Meterial Control Report, January-March 1995.

NUREG-1280 R01: STANDARD FORMAT AND CONTENT ACCEPT-NUREG 0940 V14 N1 P2: ENFORCEMENT ACTIONS: SIGNIFICANT AC-ANCE CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNT.

TIONS RESOLVED, MEDICAL LICENSEES.Ouarterly Progrese ING (MC&A) REFORM AMENDMENT.

NUR 4

P3 ORCEMENT ACTIONS: SIGNIFICANT AC.

Fusion Line Crack TIONS

RESOLVED, MATERIAL LICENSEES (NON-NUREG/CR4297: FRACTURE EVALUATIONS OF FUSION LINE MEDICAL) Quarterly Progrees Report, January-March 1995.

CRACKS IN NUCLEAR PIPE BIMETALLIC WELDS.

h Pr$ gram f

NUREG 1525: ASSESSMENT OF THE NRC ENFORCEMENT PRO-G 093 A PRIORITIZATION OF GENERIC SAFETY ISSUES.

Eseminor Stenderde Groundwater NUREG-1478 R01: NON-POWER REACTOR OPERATOR LICENSING NUREG/CR4283: FIELD SITE INVESTIGATION: EFFECT OF MINE EXAMINER STANDARDS.

SEISMICITY ON GROUNDWATER HYDROLOGY.

l

Subject index 25 Heavy-Section irradiation Program Lessons Learned NUREG/CR-5591 V05 N1: HEAVY-SECTION STEEL 1RRADIATION NUREG 1526. LESSONS LEARNED FROM EARLY IMPLEMENTATION PROGRAM. Semiannual Progress Report For September 1993 Through OF THE MAINTENANCE RULE AT NINE NUCLEAR POWER PLANTS.

March 1994, Licensed Operat6ng Reactors Heavy Section Steel Technology Program NUREG 0020 V19: LICENSED OPERATING REACTORS STATUS SUM-NUREG/CR-4219 V10 N2: HEAVY-SECT!ON STEEL TECHNOLOGY MARY REPORT. Data As Of Decemtw 51,1941 Gray Book l)

PROGRAM. Semiannual Progress Report For Apro September 1993.

Licensing Evaluation Human Factor NUREG/CR-0200 V1 R04: SCALE: A MODULAR CODE SYSTEM FOR NUREG/CP-0140 V01: PROCEEDINGS OF THE TWENTY SECOND PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses-CENSING EVALUATION Control Modules.

son, Advanced instrumentation & Control Hardware & Software, NUREG/CR0200 V2P1R4: SCALE: A MODULAR CODE SYSTEM FOR Human Factors Hesearch, IPE & PRA.

PERFORMING STANDARDIZED COMPUTER ANALYSES FOR LI-NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE CENSING EVALUATION Functonal Modules F1 F8.

AFTERLOADING BRACHYTHERAPY. Human Error And Cntical Tasks NUREG/CR 0200 V2P2R4: SCALE: A MODULAR CODE SYSTEM FOR in Rernote Aftertoading Brachytherapy And Approaches For improved PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-System Performance.

CENSING EVALUATUN Functional Modules F9-F16.

NUMEG/CR-6125 V02: HUMAN FACTORS EVALUATION OF REMOTE NUREG/CR-0200 V3 R04: SCALE. A MODULAR CODE SYSTEM FOR AFTERLOADING BRACHYTHERAPY.Functon And Task Analysis.

PERFORMING STANDARDlZED COMPUTER ANALYSES FOR Ll-CENSING EVALUATION Miscellaneous.

NUREG/CR-4918 V08. CONTROL OF WATER INFILTRATION INTO Low Power NEAR SURFACE LLW DISPOSAL UNITS Progress Report Of Field Ex-NUREG/CR-6144 V06 P1: EVALUATION OF POTENTIAL SEVERE AC-pentnents At A Humid Region Site.Beltsville. Maryland.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SURRY, UNIT 1.Evaluaton Of Severe Accident Risk Dunng Mid-Loop 1RRAS Operatons. Main Report.

NUREG/CR-6116 VIO: SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR-6144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC.

HANDS ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT VERSION 5.0. Data Loading Manual SURRY, UNIT 1. Evaluation Of Severe Accident Risk Dunng Mid-Loop atons %dces.

imm6scible Displacement NUREG/CR-6308. AN OVERVIEW OF INSTABILITY AND FINGERING Low-Levet Radioactive Waste Disposal DURING IMMISCIBLE FLUID FLOW IN M ROUS AND FRACTURED NUREG/CR-6114 V02: AUXILIARY ANALYSES IN SUPPORT OF PER.

l MEDIA-FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW LEVEL WASTE FACILITY.Two-Phase Flow And Contaminant Transport in Un-NU E 3 V07: NUCLEAR REGULATORY COMMISSION INFORMA.

saturated Soils With Applicaton To Low-level Radcactive Waste Dis-TION DlGEST.1995 Editon.

posal Low-Level Waste Data Base inserv6ce Testing NUREG 1482: GUIDELINES FOR INSERVICE TESTING AT NUCLEAR NUREG/CR-5229 V07. FIELD LYSIMETER INVESTIGATIONS: LOW-POWER PLANTS, LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR FISCAL YEAR 1994. Annual Report.

Instructor Station NUREG/CR-6256 V01: FIELD LYSIMETER INVESTIGATIONS TEST NUREG 1527: NRC'S OBJECT-OR!ENTED SIMULATOR INSTRUCTOR RESULTS Low-Level Waste Data Base Program. Test Results For STATION.

Fiscal Years 1988.1987,1988. And 1989.

Irradiated Reactor Fuel Low-Level Waste Disposal NUREG-0725 R10: PUBLIC INFORMATION CIRCULAR FOR SHIP.

NUREG/CR-4918 V08. CONTROL OF WATER INFILTRATION INTO MENTS OF IRRADIATED REACTOR FUEL.

NEAR SURFACE LLW DISPOSAL UNITS Progress Report Of Field Ex-penments At A Humid Re0 ion Site,Beltsvdle. Maryland.

l NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING MELCOR Computer Code l

WELDS Seventh Program Report March 1993 December 1994.

NUREG/CR-6119 V01: MELCOR COMPUTER CODE MANUALS.Pnmer i

NUREG/CR-6297: FRACTURE EVALUATIONS OF FUSION LINE And User's Guides. Verson 1.8.3 September 1994.

l CRACKS IN NUCLEAR PIPE BIMETALLIC WELDS NUREG/CR 6119 V02:

MELCOR COMPUTER CODE NUREG/CR4300. REFINEMENT AND EVALUATION OF CRACK-OPEN-MANUALS Reference Manuals.Verseon 1.8.3 September 1994.

ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL CRACKS IN PIPES.

Maintenance Rule NUREG 1526: LESSONS LEARNED FROM EARLY IMPLEMENTATION Leak-Before-Break OF THE MAINTENANCE RULE AT NINE NUCLEAR POWER PLANTS.

NUREG/CR4004. PROBABILISTIC PIPE FRACTURE EVALUATIONS FOR LEAK-RATE DETECTION APPLICATIONS.

Material Control NUREG/CR4235: ASSESSMENT OF SHORT THROUGH-WALL CIR-NUREG 1280 ROI: STANDARD FORMAT AND CONTENT ACCEPT.

COMFERENTIAL CRACKS IN PIPES Expenments And Anatysis. March ANCE CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNT.

1990 December 1994.

ING (MC&A) REFORM AMENDMENT.

NUREG/CR-6251: STAINLESS STEEL SUBMERGED ARC WELD FUSION LINE TOUGHNESS.

Mid-Loop Operation NUREG/CR4299-EFFECTS OF TOUGHNESS ANISOTROPY AND NUREG/CR4144 V06 P1: EVALUATION OF POTENTIAL SEVERE AC-COMBINED TENSION. TORSION. AND BENDING LOADS ON FRAC-CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

SURRY, UNIT 1.Evoluaton Of Severe Accident Risk Dunng Mid-Loop NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK OPEN-Operations Main Report.

ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL NUREG/CR-6144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC-l CRACKS IN PIPES.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT I

SURRY, UNIT 1.Evaluaten Of Severe Accident Risk Dunng Mid-Loop l

Legallosuances Operstons. Appendices.

}

NUREG 0750 V41 101: INDEXES TO NUCLEAR REGULATORY COM-MISSION ISSUANCES. January-March 1995 Mine Seismicity NUREG-0750 V41 NO2: NUCLEAR REGULATORY COMMISSION IS-NUREG/CR4283: FIELD SITE INVESTIGATION: EFFECT OF MINE SUANCES FOR FEBRUARY 1995. Pages 71178 SEISMICITY ON GROUNDWATER HYDROLOGY.

f."JREG4750 V41 NO3' NUCLEAR REGULATORY COMMISSION IS-SUANCES FOR MARCH 1995 Pages 179-243.

Nuclear Fuel Facility NUMEG 0750 V41 N04: NUCLEAR REGULATORY COMMISSION IS-NUREG/CR4287: MANAGEMENT CONCEPTS AND SAFETY APPLICA-i l

SU ANCES FOR APRIL 1995 Pages 245-319.

TIONS FOR NUCLEAR FUEL FACILITIES.

____________-_-____m

26 Subject index Nuclear Materiale Liceneses Probabilistic R6ek Assosoment NUREG/CR4330: RESULTS OF REGULATORY IMPACT SURVEY OF NUREG/CR-6119 V01: MELCOR COMPUTER CODE MANUALS.Pnmer INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE And User's Guides. Vernon 1.8.3 September 1994.

OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS.

NUREG/CR4119 V02:

MELCOR COMPUTER CODE MANUALS. Reference Manuals Verson 1.8.3 September 1994.

NUREG/CR 5975 R01: INCENTIVE REGULATION OF INVESTOR-Proceeding OWNED NUCLEAR POWER PLANTS BY PUBUC UTILITY REGULA-NUREG/CP 0140 V01: PROCEEDINGS OF THE TWENTY-SECOND TORS.

WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses-son, Advanced Instrumentaten & Control Hardware & Software, Occupat6onal Esposure NUREG/CR-3469 V08. OCCUPATIONAL DOSE REDUCTION AT NU-Human Factors Research, IPE & PRA.

CLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY OF SELECT-NUREG/CP 0140 V02: PROCEEDINGS OF THE TWENTY SECOND WATER REACTOR SAFETY INFORMATION MEETING. Severe Aces-ED READINGS IN RADIATION PROTECTION AND ALARA.

NUREG/CR-6112: IMPACT OF REDUCED DOSE UMITS ON NRC Li-dent Research, Thermal Hydraulic Research For Advanced Passive CENSED ACTIVITIES. Major issues in The implementation Of ICRP/

LWRs, High-Burnup Fuel Behaver.

NCRP Dose Umst Recommendatons Final Report.

NUREG/CP-0140 V03. PROCEEDINGS OF THE TWENTY SECOND WATER REACTOR SAFETY INFORMATION MEETING. Primary Sys-Office Of The inspector General tems integnty, Structural And Seismic Ergineenng, Aging Research.

NUREG-1415 V07 NO2: OFFICE OF THE INSPECTOR Products And Applicatons.

GENERALSemiannual Report To Congress, October 1.1994 - March 31,1995.

Public informat6on Circular NUREG-0725 RIO: PUBUC INFORMATION CIRCULAR FOR SHIP.

Operating Esperience Feedback Repwt MENTS OF IRRADIATED REACTOR FUEL NUREG 1275 VII: OPERATING EXPERIENCE FEEDBACK REPORT -

TURBINE GENERATOR OVERSPEED PROTECTION Public Utility Comm6eelon SYSTEM. Commercial Power Rea:Fors.

NUREG/CR-5975 R01: INCENTIVE REGULATION OF INVESTOR-OWNED NUCLEAR POWER PLANTS BY PUBLIC UTIUTY REGULA-OperMor LicenWng NUREG 1478 R01: NON POWER REACTOR OPERATOR LICENSING TORS.

EXAMINER STANDARDS-p,,

Overspeed Protection Byetem NUREG-1482: GUIDEUNES FOR INSERVICE TESTING AT NUCLEAR NUREG 1275 V11: OPERATING EXPERIENCE FEEDBACK REPORT -

POWER PLANTS.

TURBINE-GENERATOR OVERSPEED PROTECTION NUREG/CR-5857; AGING OF TURBINE DRIVES FOR SAFETY RELAT.

SYSTEM Commercial Power Reactors.

ED PUMPS IN NUCLEAR POWER PLANTS.

PRA Data Loading Radiation Dose NUREG/CR4116 V10: SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR-3469 V08: OCCUPATIONAL DOSE REDUCTION AT NU.

HANDSON INTEGRATED REUABluTY EVALUATIONS (SAPHIRE)

CLEAR POWER PLANTS: ANNOTATED BIBUOGRAPHY OF SELECT.

VERSION 5 0. Data Loading Manual.

ED READINGS IN RADIATION PROTECTION AND ALARA.

NUREG/CR4112: IMPACT OF REDUCED DOSE LIMITS ON NRC U-CENSED ACTIVITIES. Major lasues in The implementaten Of ICRP/

NUREG/CR 5954: EFFECT ON AGING ON PWR CHEMICAL AND Dose W %mma2nshal Rem VOLUME CONTROL SYSTEM.

NUREG/Cf.6109. THE PROBABluTY OF CONTAINMENT FAILURE BY DIRECT CONTAINMENT HEATING IN SURRY'

/CR 3 9 V08: OCCUPATIONAL DOSE REDUCTION AT NU-Performance CLEAR POWER PLANTS: ANNOTATED BIBUOGRAPHY OF SELECT.

NUREG/CR-6046; ALERTNESS, PERFORMANCE. AND OFF-DUTY ED READINGS IN RADIATION PROTECTION AND ALARA.

SLEEP ON 8-HOUR AND 12 HOUR NIGHT SHIFTS IN A SIMULATED CONTINUOUS OPERATIONS CONTROL ROOM SETTING.

Rad 6oactive Release NUREG/CR-2850 V13: DOSE COMMITMENTS DUE TO RADIOACTIVE Performance incentive RELEASES FROM NUCLEAR POWER PLANT SITES IN 1991, NUREG/CR 5975 R01: INCENTIVE REGULATION OF INVESTOR.

OWNED NUCLEAR POWER PLANTS BY PUBUC UTIUTY REGULA-Radiolog6 cal Criteria TORS.

NUREG/CR-6307:

SUMMARY

OF COMMENTS RECEIVED AT WORK.

SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO UREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING CASES.

WELDS Seventh Program Report March 1993 December 1994.

NUREG/CR-6004: PROBABILISTIC PIPE FRACTURE EVALUATIONS actw Inshumentam FOR LEAK. RATE DETECTION APPUCATIONS.

NUREG/CR4235: ASSESSMENT OF SHORT THROUGH-WALL CIR.

NUREG/CP0140 V01: PROCEEDINGS OF THE TWENTY SECOND CUMFERENTIAL CRACKS IN PIPES Expenmonts And Analysis. March WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses.

1990 - December 1994.

sion, Advanced instrutnentaten & Control Hardware & Software, NUREG/CR4251: STAINLESS STEEL SUBMERGED ARC WELD Human Factors Research, IPE & PRA.

FUSION UNE TOUGHNESS NUREG/CR-6297: FRACTURE EVALUATIONS OF FUblON LINE Reactor Pressure Vessel CRACKS IN NUCLEAR PlPE BIMETALUC WELDS.

NUREG/CR4327: MODELS FOR EMBRITTLEMENT RECOVERY DUE NUREG/CR4299: EFFECTS OF TOUGHNESS ANISOTROPY AND TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

COMBINED TENSION, TORSION, AND BENDING LOAD 3 ON FRAC-TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

Reactor Safety NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK OPEN-NUREG/CP-0140 V01: PROCEEDINGS OF THE TWENTY SECOND ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses.

CRACKS IN PIPES.

son, Advanced Instrumentaten & Control Hardware & Software, Pressure Senew Human Factors Research. IPE & PRA.

NUREG/CP 0140 V02: PROCEEDINGS OF THE TWENTY SECOND NUREG/CR4312: ASSESSMENT OF FIBER OPT!C PRESSURE SEN-SORS.

WATER REACTOR SAFETY INFORMATION MEETING. Severe Acci-dont Research, Thermal Hydrauhc Research For Advanced Passive Prosaurtsed Water Reector LWRs, High-Burnup Fuel Behavior.

NUREG/CR4954: EFFECT ON AGING ON PWR CHEMICAL AND NUREG/CP-0140 V03: PROCEEDINGS OF THE TWENTY SECOND VOLUME CONTROL SYSTEM WATER REACTOR SAFETY INFORMATION MEETING Pnmary Sys-NUREG/CR4109: THE PROBABluTY OF CONTAINMENT FAILURE BY tems Integnty, Structural And Seismic Engineenng, Agtng Research, DIRECT CONTAINMENT HEATING IN SURRY, Products And Apphcatons.

Subject index 27 Regulation NUREG/CR-6119 V02.

MELCOR COMPUTER CODE NUREG/CR-6975 Rot: INCENTIVE REGULATION OF INVESTOR-MANUALS Reference Manuals Vernon 1.8.3 September 1994.

OWNED NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULA-NUREG/CR4144 V06 P1: EVALUATION OF POTENTIAL SEVERE AC-TGRS.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR4315: CANDU REACTORS. THElR REGULATION IN SURRY, UNIT 1 Evoluation Of Severe Accident Fhsk Dunng M4 Loop CANADA, AND THE IDENTIFICATION OF RELEVANT NRC SAFETY Operations Main Report.

ISSUES.

NUREG/CR-6144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Regulatory impact SurveF SURRY, UNIT 1.Evaluahon Of Severe Accident Risk Dunng Mid-Loop NUREG/CR4330: RESULTS OF REGULATORY IMPACT SURVEY OF Operatons. Appendices INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS-Shiftwork NUREG/CR-6046. ALERTNESS. PERFORMANCE, AND OFF-DUTY Remote Ahortoseng SLEEP ON 8-HOUR AND 12-HOUR NIGHT SHIFTS IN A SIMULATED NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF REMOTE CONTINUOUS OPERATIONS CONTROL ROOM SETTING.

AFTERLOADING BRACHYTHERAPY. Human Error And Critical Tasks in Remote Afterloadeng Brachytherapy And Approaches For improved Shipment System Performance.

NUREG4725 RIO: PUBLIC INFORMATION CIRCULAR FOR SHIP-NUREG/CR4125 V02: HUMAN FACTORS EVALUATION OF REMOTE

'MENTS OF 1RRADIATED REACTOR FUEL AFTERLOADING BRACHYTHERAPY. Function And Task Analysis

.m Shipping Caek

/CR 6330: NISULTS OF REGULATORY IMPACT SURVEY OF

- 65L AMG @NE MMM & M I

R INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE Des naly NUREbn Rev ew OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS.

/CR 6322: BUCKLING ANALYSIS OF SPENT FUEL BASKET.

Reeln m.P[UEEYC 42 5 MECHANICAL PROPERTIES OF THERMALLY AGE

,.__ m NUREG/CA-5229 V07: FIELD LYSIMETER INVESTIGATIONS: LOW.

~~

LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR CAST STAINLESS STEELS FROM SHIPPINGPORT REACTOR COM-FISCAL YEAR 1994 Annual RepM PONENTS-NUREG/CR 6256 V01: FIELD LYSIMETER INVESTIGATIONS - TEST RESULTS Low-Level Weste Data Base Program. Test Results For Short Crack Fiscal Years 1986,1987,1988, And 1989.

NUREG/CR 4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING SApHIRE WELDS Seventh Program Report March 1993 - December 1994.

NUREG/CR-6116 V10: SYSTEMS ANALYSIS PROGRAMS FOR Shutdown Operat6on HANDS-ON INTEGRATED REUABluTY EVALUATIONS (SAPHIRE)

NUREG/CR4144 V06 P1: EVALUATION OF POTENTIAL SEVERE AC.

VERSION 5.0 Data Loading Manual.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT SCALE SURRY, UNIT 1. Evaluation Of Severe Accident Risk Dunng Mid-Loop NUREG/CR-0200 V1 R04: SCALE: A MODULAR CODE SYSTEM FOR Operatons. Main Report.

PERFORMING STANDARDtZED COMPUTER ANALYSES FOR Ll.

NUREG/CR 6144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC-CENSING EVALUATION Control Modules.

CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR 0200 V2P1R4: SCALE: A MODULAR CODE SYSTEM FOR SURRY, UNIT 1. Evaluation Of Severe Accedent Risk Dunng Mid-Loop PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-Operations. Appendices.

CENSING EVALUATION Functional Modules F1-F8 NUREG/CR 0200 V2P2R4: SCALE: A MODULAR CODE SYSTEM FOR Simulator PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll.

NUREG-1527: NRC'S OBJECT-ORIENTED SIMULATOR INSTRUCTOR CENSING EVALUATION Functonal Modules F9-F16 STATION.

NUREG/CR-0200 V3 R04: SCALE: A MODULAR CODE SYSTEM FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Lt.

Site Speciflc Advisory Board CENSING EVALUATION. Miscellaneous.

NUREG/CR4307:

SUMMARY

OF COMMENTS RECEIVED AT WORK-SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO Safety Appl 6 cat 6on FACILITATE PUBLIC PARTICIPATION IN DECOMMISSIONING NUREG/CR4287: MANAGEMENT CONCEPTS AND SAFETY APPLICA-CASES.

TIONS FOR NUCLEAR FUEL FACILITIES.

Spent Fuel Basket Safety Evaluation Report NUREG/CR4322: BUCKLING ANALYSIS OF SPENT FUEL BASKET.

NUREG-0847 S15: SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND Stainless Steel

2. Docket Nos. 50-390 And 50-391.(Tennessee Valley Authonty)

NUREG/CR4251: STAINLESS STEEL SUBMERGED ARC WELD FUSION LINE TOUGHNESS.

Safety leaves NUREG/CR4275: MECHANICAL PROPERTIES OF THERMALLY AGED NUREG/CR4315: CANDU REACTORS. THEIR REGULATION IN CAST STAINLESS STEELS FROM SHIPPINGPORT REACTOR COM-CANADA. AND THE IDENTIFICATION OF RELEVANT NRC SAFETY PONENTS.

ISSUES.

Standard Technical Specificatione Safety "_. _ at NUREG-1430 V01 R01: STANDARD TECHNICAL SPECIFICATIONS NUREG/CR-6287: MANAGEMENT CONCEPTS AND SAFETY APPLICA-BABCOCK AND WILCOX PLANTS Specificatons.

TlONS FOR NUCLEAR FUEL FACILITIES.

NUREG 1430 V02 RO1: STANDARD TECHNICAL SPECIFICATIONS BABCOCK AND WILCOX PLANTS. Bases (Sections 2.0 3.3).

Scloty-Reisted System NUREG 1430 V03 RO1: STANDARD TECHNICAL SPECIFICATIONS NOREG/CR4016: AGING AND SERVICE WEAR OF AIR-OPERATED BABCOCK AND WILCOX PLANTS Bases (Sections 3.4 3.9).

VALVES USED IN SAFETY-RELATED SYSTEMS AT NUCLEAR NUREG 1431 V01 R01: STANDARD TECHNICAL SPECIFICATIONS POWER PLANTS.

WESTINGHOUSE PLANTS. Specifications.

NUREG-1431 V02 RO1: STANDARD TECHNICAL SPECIFICATIONS Severe Accident WESTINGHOUSE PLANTS Bases (Sections 2.0 - 3.3).

NUREG/CP-0140 V02: PROCEEDINGS OF THE TWENTY SECOND NUREG-1431 V03 RO1: STANDARD TECHNICAL SPECIFICATIONS WATER REACTOR SAFETY INFORMATION MEETING Severe Acci-WESTINGHOUSE PLANTS Bases (Sections 3 4 - 3 9)-

dont Research Thermal Hydraulic Research For Advanced Passive NUREG-1432 V01 ROI: STANDARD TECHNICAL SPECIFICATIONS LWRs, Hegl>Burnup Fuel Behavior.

COMBUSTION ENGINEERING PLANTS _Specificeions.

NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY NUREG-1432 V02 R01: STANDARD TECHNICAL SPECIFICATIONS DIRECT CONTAINMENT HEATING IN SURRY.

COMBUSTION ENGINEERING PLANTS Bases (Sections 2.0 3.3).

NUREG/CR4119 VOI: MELCOR COMPUTER CODE MANUALS Pnmer NUREG-1432 V03 R01: STANDARD TECHNICAL SPECIFICATIONS And User's Guides. Versson 1.8.3 September 1994.

COMBUSTION ENGINEERING PLANTS Bases (Sectons 3.4 3.9).

a

38 Subject Index NUREG 1433 V01 RO1 - STANDARD TECHNICAL SPECIFICATIONS NUREG-0540 V17 NO3 TITLE LIST OF UOCUMENTS MADE PUBLICLY GENERAL ELECTRIC PLANTS BWR/4 Specifications AVAILABLE March 1 31,1995 NUREG-1433 V02 Rot: STANDARD TLCHNICAL SPECIFICATIONS NUREG-0540 V17 N04. TITLE UST OF DOCUMENTS MADE PUBLICLY AVAILABLE. Aprd 1 30,1995.

GENERAL Et.ECTRIC PL ANTS BWR/4 Bases (Sections 2 0 - 3 3) ONS NUREG 1433 V03 ROI: STANDARD TECHNICAL SPECIFICATI GENERAL ELECTRIC PLANTS BWR/4 Bases (Sectons 3 4 - 310)

Turbine Drtve NUREG 1434 V01 ROI: STANDARD TECHNICAL SPECIFICATIONS NUREG/CR-5857: AGING OF TURSINE DRIVES FOR SAFETY-RELAT-GENERAL ELECTRIC PLANTS, BWR/6 Specifcations ED PUMPS IN NUCLEAR POWER PLANTS.

NUREG 1434 V02 Roi: STANDARD TECHNICAL SPECIFICATIONS Turb6ne-Generator GENERAL ELECTRIC PLANTS, BWR/6 Bases (Sectons 2 0 3 3.)ONS NUREG-1434 V03 ROI: STANDARD TECHNICAL SPECIFICATI NUREG-1275 VII: OPERATING EXPERIENCE FEEDBACK REPORT.

GENERAL ELECTRIC PLANTS, BWR/6 Bases 3 4 3.10).

TURBINE-GENERATOR OVERSPEED PROTECTION Structural Analys6e NUREG/CR-5657. AUTOCASK (AUTOMATIC GENERATION OF 3D Two-Phase Flow CASK MODELS) A Mcrocomputer Based System For Shipping Casit NUREG/CR-6114 V02: AUXILIARY ANALYSES IN SUPPORT OF PER-Design Review Analysis.

FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW LEVEL WASTE FACILITY.Two-Phase Flow And Contaminant Transport in Un-saturated Soils With Appicaton To Low-Level Radioactive Waste Dis-NUREG/

1 0 V03. PROCEEDINGS OF THE TWENTY-SECOND p sal WATER REACTOR SAFETY INFORMATION MEETING Pnmary Sys-tems Integnty, Structural And Seismic Engineenng, Aging Research.

Unsaturated Soll Products And Appicatons.

NUREG/CR-6114 V02: AUXILIARY ANALYSES IN SUPPORT OF PER.

FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW LEVEL WASTE FACIUTY Two-Phase Flow And Contaminant Transport in Un-UREG-0837 Vt5 NOI: NRC TLD DIRECT RADIATION MONITORING saturated Soils With Application To Low-Level Radioactive Waste Dis-NETWORK Progress Report January-March 1995.

posal.

Thermal Aging Valve NUREG/CR-6275: MECHANICAL PROPERTIES OF THERMALLY AGED CAST STAINLESS S1 EELS FROM SHIPPINGPORT REACTOR COM-POWER PLANTb,DELINES FOR INSERVICE TESTING AT NUCLEAR NUREG-1482: GUI PONENTS.

vendorinspecuon Thermal-Hydrauhc NUREG-0040 V19 NOI: LICENSEE CONTRACTOR AND VENDOR IN-NUREG/CP-0140 V02. PROCEEDINGS OF THE TWENTY-SECOND SPECTION STATUS REPORT. Quarterly Report. January-March WATER REACTOR SAFETY INFORMATION MEETING. Severe Acc,.

1995 (White Book) dent Research, Thermal Hydraulic Research For Advanced Passive 5

L WRa, H Fuel Behavior Y'Oiat on NUREG/Cdi h.BurnukROBABILISTIC PIPE FRACTURE EVALUATIONS 6004 N E FOR LEAK-RATE-DETECTION APPLICATIONS NUREG/CR-6119 V01: MELCOR COMPUTER CODE MANUALS Pnmer GRAM.

And User's Guides Verson 18 3 September 1994 NUREG/CR 6119 V02 MELCOR COMPUTER CODE Water Infiltration NUREG/CR 4918 V08 CONTROL OF WATER INFILTRATlON INTO MANUALS Reference Manuals Version 18 3 September 1994.

NEAR SURF ACE LLW DISPOSAL UNITS. Progress Report Of Feld Ex-Thermoluminescent Dosimeter penments At A Humed Region Site.Beltsvdle, Maryland NUREG-0837 V15 NOI, NRC TLD DIRECT RADIATION MONITORING Weld NETWORK. Progress Report January March 1995.

l Title List WELDS Seventh Program Report March 1993 December 1994.

l NUREG 0540 V17 NO2. TITLE LIST OF DOCUMENTS MADE PUBLICLY NUREG/CR-6251 STAINLESS STEEL SUBMERGED ARC WELD AVAILABLE. February 1-28,1995 FUSION LINE TOUGHNESS.

NRC Originating Organization Index (Staff Reports)

This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by major NRC organizations (e.g., program offices) and then by sub-sections of these (e.g., divisions, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s). If further information is needed, refer to the main citation by NUREG number.

EDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS AIVISORY COMMITTEE (S)

DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST ACRS ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUREG 1125 V16: A COMPILATION OF REPORTS OF THE ADVISO-870729)

RY COMMITTEE ON REACTOR SAFEGUARDS.1994 Annual.

NUREG 0725 RIO: PUBLIC INFORMATION CIRCULAR FOR SHIP-MENTS OF IRRADIATED REACTOR FUEL OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)

OPERATIONS BRANCH REGON 1 (POST 820201)

NUREG/CR-8125 VOI: HUMAN FACTORS EVALUATION OF NUREG 0837 V15 NC1: NRC TLD DIRECT RADIATON MONITORING REMOTE AFTERLOADING BRACHYTHERAPY. Human Error And NETWORK. Progress Report. January-March 1995 Cntical Tasks in Remote Afterloading Brachytherapy And Approach-WALNUT CREEK FIELD OFC, R4 (POST 940404) es For improved System Performance.

NUREG-1525. ASSESSMENT OF THE NRC ENFORCEMENT PRO-NUREG/CR 6125 V02: HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY. Function Ard Task GRAM.

OFC OF ENFORCEMENT (POST 870413)

Analysis.

NUREG-0940 Vid N1 P1: ENFORCEMENT ACTIONS. SIGNIFICANT DIVISION OF FUEL CYCLE SAFETY & SAFEGUARDS (POST 930207)

ACTIONS RESOLVED, REACTOR LICENSEESOuarterly Progress NUREG 1280 RO1: STANDARD FORMAT AND CONTENT ACCEPT.

ANCE CRITERIA FOR THE MATERIAL CONTROL AND ACCOUNT.

Report. January-March 1995 NUREG0940 V14 N1 P2: ENFORCEMENT ACTIONS: SIGNIFICANT ING (MC&A) REFORM AMENDMENT.

ACTIONS RESOLVED, MEDICAL LICENSEES.Ouarterly Progress U.S. NUCLEAR REGULATORY COMMISSION Report. January-March 1995.

NUREG-0940 V14 N1 P3. ENFORCEMENT ACTONS: SIGNIFICANT OFFICE OF THE INSPECTOR GENERAL (POST 890417)

ACTIONS

RESOLVED, MATERIAL LICENSEES (NON.

NUREG 1415 V07 NO2: OFFICE OF THE INSPECTOR GENERALSemianrNal Report To Congress. October 1, 1994 -

MEDICAL) Ouarterly Progress Report January-March 1995.

NUREG-1525: ASSESSMENT OF THE NRC ENFORCEMENT PRO-March 31,1995 GRAM.

EDO OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)

DIVISION OF ENGINEERING TECHNOLOGY (POST 941217)

EDO OFFICE OF ADMINISTRATION (PRE 870413 & POST 890205)

NUREG-0933 S18: A PRIORITiZATION OF GENERIC SAFETY DIVISION OF FREEDOM OF INFORMATON & PUBLICATIONS SERV.

ISSUES.

ICES (POST 940714 WASTE MANAGEMENT BRANCH (POST 941217)

NUREG-0540 V17 NO2: TITLE LIST OF DOCUMENTS MADE PUBLIC.

NUREG/CR-4918 V08: CONTROL OF WATER INFILTRATION INTO LY AVAllABLE. February 1-28,1995 NEAR SURFACE LLW DISPOSAL UNITS. Progress Report Of Field NUREG-0540 V17 NO3: TITLE LIST OF DOCUMENTS MADE PUBLIC.

Expenments At A Humid Region Site,Beltsvdle, Maryland.

NUREG-0540 V17 N04: TITLE LIST OF DOCUMENTS MADE PUBLIC.

NUREG/CR-6283: FIELD SITE INVESTIGATION: EFFECT OF MINE LY AVAILABLEMarch 1 31,1995.

SElSM) CITY ON GROUNDWATER HYDROLOGY.

LY AVAILABLE. Aprd 1 30,1995.

CONTROL, INSTRUMENTATION & HUMAN FACTORS BRANCH (POST NUREG-0750 V41601: INDEXES TO NITLEAR REGULATORY COM.

941217)

MISSION ISSUANCES. January-March 1995.

NUREG/CR 6125 VOI: HUMAN FACTORS EVALUATION OF NUREG-0750 V41 NO2: NUCLEAR REGULATORY COMMISSION IS.

REMOTE AFTERLOADING BRACHYTHERAPY. Human Error And SUANCES FOR FEBRUARY 1995. Pages 71178.

Cntical Tasks in Remote Afterloading Brachytherapy And Approach-NUREG-0750 V41 NO3-NUCLEAR REGULATORY COMMISSION IS.

es For improved System Performance SUANCES FOR MARCH 1995.Pages 179-243 NUREG4750 V41 N04: NUCLEAR REGULATORY COMMISSION IS.

NUREG/CR 6125 V02: HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY, Function And Task SUANCES FOR APRIL 1995.Pages 245-319.

Analysis.

EDO OFFICE OF THE CONTROLLER (PRE 820418 & POST 890205)

EDO. OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)

OFFICE OF THE CONTROLLER (POST 890205)

NUREG 1470 V04: FINANCIAL STATEMENT FOR FISCAL YEAR OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)

NUREG-0040 V10 NOI: LICENSEE CONTRACTOR AND VENDOR IN-SPECTION STATUS REPORT. Quarterly Report. January-March 1994 DIVISION OF BUDGET & ANALYSIS (POST 890206)

NUREG 1350 V07: NUCLEAR REGULATORY COMMISSION INFOR-1995 (White Book)

NUREG 1430 V01 R01: STANDARD TECHNICAL SPECIFICATIONS MATION DIGEST.1995 Edition.

BABCOCK AND WILCOX PLANTS. Specifications.

EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG-1430 V02 RO1: STANDARD TECHNICAL SPECIFICATONS BABCOCK AND WILCOX PLANTS. Bases (Sections 2.0 3.3).

DATA NUREG-1430 V03 ROI: STANDARD TECHNICAL SPECIFICATONS TECHNICAL TRAINING CENTER BABCOCK AND WILCOX PLANTS. Bases (Sections 3.4 3.9).

NUREG-1527: NRC*S OBJECT. ORIENTED SIMULATOR INSTRUC-NUREG-1431 V01 RO1: STANDARD TECHNICAL SPECIFICATIONS TOR STATION OlVISON OF SAFETY PROGRAMS (POST 870413)

WESTINGHOUSE PLANTS. Specificatons.

NUREG-1275 V11: OPERATING EXPERIENCE FEEDBACK REPORT.

NUREG-1431 V02 R01: STANDARD TECHNICAL SPECIFICATIONS TURBINE GENERATOR OVERSPEED PROTECTION WESTINGHOUSE PLANTS. Bases (Se:-teons 2.0 3.3).

NUREG-1431 VO3 R01: STANDARD TECHNICAL SPECIFICATIONS SYSTEM Commercia! Power Reactors WESTINGHOUSE PLANTS Bases (Sections 3.4 3.9).

EDO. OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM NUREG-1432 V01 RO1: STANDARD TECHNICAL SPECIFICATONS COMBUSTION ENGINEERING PLANTS. Specifications.

(POST 881108)

OFFICE OF INFORMATION RESOURCES MANAGEMENT (POST NUREG 1432 V02 R01: STANDARD TECHNICAL SPECIFICATONS COMBUSTION ENGINEERING PLANTS Basas (Sections 2.0 3.3).

890205)

NUREG 0020 V19. LICENSED OPERATING REACTORS STATUS NUREG 1432 V03 RO1: STANDARD TECHNICAL SPECIFICATONS

SUMMARY

REPORT. Data As Of December 31,1994.(Gray Book 1)

COMBUSTION ENGINEERING PLANTS. Bases (Sections 3.4 + 3.9).

29

30 NRC Originating Organization index (Stcff Reports)

NUREG 1433 V01 R01: STANDARD TECHNICAL SPECIFICATIONS NUREG 1526: LESSONS LEARNED FROM EARLY IMPLEMENTA.

GENERAL ELECTRIC PLANTS BWR/4 Spec,festons.

TION OF THE MAINTENANCE RULE AT NINE NUCLEAR POWER NUREG 1433 V02 RO1: STANDARD TECHNICAL SPECIFICATIONS PLANTS.

GENERAL ELECTRIC PLANTS BWR/4. Bases (Sectone 2.0 - 3.3).

DIVISION OF REACTOR PROJECTS I/Il (DRPE) POST 941001)

NUREG 1433 V03 R01: STANDARD TECHNICAL SPECIFICATIONS NUREG-0847 S15: SAFETY EVALUATION REPORT RELATED TO GENERAL ELECTRIC PLANTS BWR/4. Bases (Sections 3.4 - 3.10).

THE OPERATION OF WATTS BAR NUCLEAR PLANT. UNITS 1 AND NUREG 1434 V01 R01: STANDARD TECHNICAL SPECIFICATIONS k E RE-EbT ASS T D EC F A ED GENERAL ELECTRIC PLANTS. BWR/6 Speedcatons.

NUREG-1434 V02 R01: STANDARD TECHNICAL SPECIFICATIONS NEWAL (ADAR) (POST NUREG-0498 S01: FINAL ENVIRONMENTAL STATEMENT RELATED GENERAL ELECTRIC PLANTS, BWR/6. Bases (Sectons 2.0 3.3).

TO THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 NUREG 1434 V03 R01: STANDARD TECHNICAL SPECIFICATIONS AND 2. Docket Nos. 50-390 And 50-391.(Tennessee Valley Authonty)

GENERAL ELECTRIC PLANTS, BWR/6. Bases 3.4 3.10).

OFFICE OF NUCLEAR REACTOR REGULATION, DIRECTOR (POST NUREG 1478 RO1: NON-POWER REACTOR OPERATOR LICENSING 870411)

EXAMINER STANDARDS.

NUREG 1482: GUIDELINES FOR INSERVICE TESTING AT NUCLEAR POWER PLANTS.

I

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., divisions, branches) where appropriate. Each cntry is followed by a NUREG number and title of the report (s). If further information is n:eded, refer to the main citation by NUREG number.

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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 by 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) arepared by that organi-zation. If further information is needed, refer to the main citation by 11e NUREG/CR number.

EDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG/CR-4918 V08: CONTROL OF WATER INFILTRATION INTO DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST NEAR SURFACE LLW DISPOSAL UNITS Progress Report Of Field 870729)

Expenments At A Humed Region Site.Beltsville. Maryland.

NUREG/CR4200 V1 R04 SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR 5229 V07: FIELD LYSIMETER INVESTIGATIONS: LOW-PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR CENSING EVALUATION Control Modules FISCAL YEAR 1994 Annual Report.

NUREG/CR-0200 V2P1R4 SCALE: A MODULAR CODE SYSTEM NUREG/CR4112; IMPACT OF REDUCED DOSE LIMITS ON NRC LI-FOR PERFORMING STANDARDlZED COMPUTER ANALYSES FOR CENSED ACTIVITIES. Maior issues in The implementaton Of ICRP/

LICENSING EVALUATON Functional Modules F1-F8.

NUREG/CR-0203 V2P2R4: SCALE: A MODULAR CODE SYSTEM NCRP Dose Limit Rw.ic mons. Final Report.

j FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR NUREG/CR-6114 V02: AUXILIARY ANALYSES IN SUPPORT OF PER.

i LICENSING EVALUATION Functonal Modules F9-F16.

FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW LEVEL NUREG/CR 0200 V3 R04: SCALE: A MODULAR CODE SYSTEM FOR WASTE FACILITY.Two-Phase Flow And Contaminant Transport in PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-Unsaturated Soils With Applicadon To Low Level Radioactive Waste CENSING EVALUATION Miscellaneous-Disposal NUREG/CR-5657. AUTOCASK (AUTOMATIC GENERATION OF 3.-D NUREG/CR4256 V01: FIELD LYSIMETER INVESTIGATIONS - TEST CASK MODELS) A Microcomputer Based System For Shipping Cask RESULTS Low-Level Waste Data Base Program. Test Results For

^

bllELD S N EST ATION: EFFECT OF MINE 3

UL S RE TA A

RVEYO NU

/

28 INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF 'THE' SEISMICITY ON GROUNOWATER HYDROLOGY, NUREG/CR4307:

SUMMARY

OF COMMENTS RECEIVED AT WORK.

OFFICE OF NUCLEAR MATERIALS SAFET/ AND SAFEGUARDS OlVISION OF FUEL CYCLE SAFETY & SAFEGUARDS (POST 930207)

SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB)

NUREG/CR4287: MANAGEMENT CONCEPTS AND SAFETY APPL 1-TO FACILITATE PUBLIC PARTICIPATION IN DECOMMISSIONING CATIONS FOR NUCLEAR FUEL FACILITIES-CASES.

DIVISION OF SYSTEMS TECHNOLOGY (POST 941217)

II NUREG/CR4046. ALERTNESS, PERFORMANCE. AND OFF DUTY j

FFI FN E R RLG TORY ESE R S

2 NUREG/CR4331: ATMOSPHERIC RELATIVE CONCENTRATIONS IN SLEEP ON 8-HOUR AND 12 HOUR NIGHT SHIFTS IN A SIMULAT.

ED CONTINUOUS OPERATIONS CONTROL ROOM SETTING.

BUILDING WAKES OlVISION OF ENGINEERING TECHNOLOGY (POST 941217)

NUREG/CR4109-THE PROBABILITY OF CONTAINMENT FAILURE NUREG/CR-4219 V10 N2: HEAVY-SECTION STEEL TECHNOLOGY BY DIRECT CONTAINMENT HEATING IN SURRY.

PROGRAM Semiannual Prooress Report For Apni-September 1993.

NUREG/CR4116 VIO: SYSTEMS ANALYSIS PROGRAMS FOR NUREG/CR-4599 V04 N1: SHORT CRACKS IN PIPING AND PIPING HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE)

WELDS Seventh Program Report March 1993 December 1994.

VERSION 5 0 Data Loading Manual NUREG/CR-5591 V05 N1: PcA/Y-SECTON STEEL 1RRADIATION NUREG/CR-6119 V01.

MELCOR COMPUTER CODE OGRAM nnual Progress Report For September 1993 MANUALS Pnmer And User's Guides. Verson 1.8.3 September NURE 5857: AGING OF TURBINE DRIVES FOR SAFETY-RE.

189d-LATED PUMPS IN NUCLEAR POWER PLANTS.

NUREG/CR4119 V02:

MELCOR COMPUTER CODE NUREG/CR 5954: EFFECT ON AGING ON PWR CHEMICAL AND MANUALS Reference Manuals.Verseon 1.8.3 September 1994.

VOLUME CONTROL SYSTEM NUREG/CR4125 V01: HUMAN FACTORS EVALUATION OF l

NUREG/CR-6004. PHOBABILISTIC PIPE FRACTURE EVALUATIONS REMOTE AFTERLOADING BRACHYTHERAPY. Human Error And FOR LEAK-RATE DETECTON APPLICATIONS.

Cntical Tasks in Remote Afterloading Brachytherapy And Approaclu NUREG/CR4016: AGING AND SERVICE WEAR OF AIR-OPERATED es For improved Systern Ps'formen.e VALVES USED IN SAFET(-RELATED SYSTEMS AT NUCLEAR NUREG/CR41d V02. HUMAN FACTORS EVALUATON CF REMOTE AFTERLOADING BRACHYTHERAPY.Functon And Task NU E / R4 5: ASSESSMENT OF SHORT THROUGH-WALL CIA.

MFERENT A C CK IN PIPES.Expenments And NUR R4144 V06 P1: EVALUATION OF POTENTIAL SEVERE NURE /CR4251: STAINLESS STEEL' SUBMERGED ARC WELD ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER-FUSION LINE TOUGHNESS.

ATIONS AT SURRY, UNIT 1.Evaluaton Of Severe Accident Risk NUREG/CR 6275: MECHANICAL PROPERTIES OF THERMALLY Dunng Mid-Loop Operatons. Main Report.

AGED CAST STAINLESS STEELS FROM SHIPPINGPORT REAC.

NUREG/CR4144 V06 P2: EVALUATION OF POTENTIAL SEVERE TOR COMPONENTS.

ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.

NUREG/CR4297; FRACTURE EVALUATONS OF FUS'ON LINE ATIONS AT SURRY, UNIT 1.Evaluaton Of Severe Accident Risk CRACKS IN NUCLEAR PIPE BIMET/ LLIC WELDS.

Dunng M4 Loop Operations. Appendices.

NUREG/CR-6299. EFFECTS OF TO,GHNESS AN%0TROPY AND NUREG/CR-6312: ASSESSMENT OF FIBER OPTIC PRESSURE SEN-COMBINED TENSION, TORSION, AND BENOWG LOADS ON SORS

-6M NU UNS, NM MWM W NU EG RE ENT ND E LUAT N OF CRACK.

CANADA. AND THE IDENTIFICATION OF RELEVANT NRC SAFETY OPENING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH.

ISSUES.

WALL CRACKS IN PIPES NUREG/CR4318. DATA

SUMMARY

REPORT FOR FISSION PROD-j NUREG/CR4327: MODELS FOR EMBRITTLEMENT RECOVERY DUE TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

UCT RELEASE TEST VI-7.

DIVISION OF REGULATORY APPLICATONS (POST 941217)

DIVISION OF RISK ANALYSIS & OPERATONS (840429-860720)

NUREG/CR-3469 V08: OCCUPATONAL OCSE REDUCTION AT NU.

NUREG/CR-6308. AN OVERVIEW OF INSTABILITY AND FINGERING CLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY OF SE-DURING IMMISCIBLE FLUID FLOW IN POROUS AND FRACTURED LECTED READINGS IN RADIATION PROTECTION AND ALARA.

MEDIA.

33

34 NRC Contract Sponsor index EDO OFFICE OF NUCLEAR MACTOR MOULATION (POST 400428)

LICENSE RENEWAL & ENVIRONMENTAL REVIEW PROJECT DIREC.

OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)

TORATE (POLR) (POST NUREG/CR-2650 V13: DOSE COMMITMENTS DUE TO RADICAC.

NUREG/CR-5975 RO1: INCENTIVE REGULATION OF INVESTOR-TfvE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1991.

OWNED NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGU.

LATORS.

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

s ADVANCED SYSTEMS TECHNOLOGY, INC.

dent Research Thermal Hydraulic Research For Advanced Passive NUREG/CR4307:

SUMMARY

OF COMMENTS RECEIVED AT WORK-LWRs. High-Bt nup Fuel Behavior.

i SHOP ON USE OF A SITE SPECIFIC ADVISORY BOARD (SSAB) TO NUREG/CP0140 V03: PROCEEDINGS OF THE TWENTY-SECOND FACILITATE PUBLIC PARTICIPATION IN DECOMMISSIONING WATER REACTOR SAFETY INFORMATION MEETING.Pnmary Sys-CASES.

tems integnty, Structural And Seismic Engneenng, Aging Research, j

i Products And Apphcations.

ANALYSIS & MEASUREMENT SERVICES CORP, NUREG/CR-3469 V08: OCCUPATIONAL DOSE REDUCTION AT NU-l NUREG/CR 6312: ASSESSMENT OF FIBER OPTIC PRESSURE SEN-CLEAR POWER PLANTS. ANNOTATED BIBLIOGRAPHY OF SELECT-a SORS-ED READINGS IN RADIATION PROTECTION AND ALARA.

1 NUREG/CR-5954: EFFECT ON AGING ON PWR CHEMICAL AND I

i ARGONNE NATIONAL LABORATORY SY8 OLU, E 109 THE PROBABILITY O NTAINMENT FAILURE BY EG CT F REDUCED DOSE LIMITS ON NRC Ll-D RE NTMN NUREG/CR4275: MECHANICAL PROPERTIES OF THERMALLY AGED CENSED ACTIVITIES. Major lasues in The implementation Of ICRP/

CAST S1 AINLESS STEELS FROM SHIPPINGPORT REACTOR COM.

NCRP Dose Limit Recommendations. Final Report.

PONENTS.

NUREG/CR4144 V06 P1: EVALUATION OF POTENTIAL SLVERE AC-NUREG/CR4315: CANDU REACTORS. THEIR REGULATION IN CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT CANADA, AND THE IDENTIFICATION OF RELEVANT NRC SAFETY SURRY, UNIT 1 Evaluaten Of Severe Accident Risk Dunng Mid-Loop ISSUES.

Operations. Main Report.

NUREG/CR4144 V06 P2: EVALUATION OF POTENTIAL SEVERE AC-ARIZONA, UNIV. OF, TUCSON, AZ CIDENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT 4

NUREG/CR4308. AN OVERVIEW OF INSTABILITY AND FINGERING SURRY, UNIT 1, Evaluation Of Severe Acesdent Risk Dunng Mid-Loop DURING IMMISCIBLE FLUlO FLOW IN POROUS AND FRACTURED Operatons. Appendices.

MEDIA.

BATTELLE HUMAN AFFAIRS RESEARCH CENTERS NUREG/CR 4918 V08: CONTROL OF WATER INFILTRATION INTO NUREG/CR4330: RESULTS OF REGULATORY IMPACT SURVEY OF NEAR SURFACE LLW DISPOSAL UNITS Progress Report Of Field Ex-s INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS.

penments At A Humid Region Sste,Beltsville, Maryland.

CATTELLE MEMORIAL INSTITUTE COLUMBUS LABORATORIES CALIFORNIA, UNIV. OF, SAN OlEGO, CA NUREG/CR-4599 V0d Nt: SHORT CRACKS IN PIPING AND PIPING NUREG/CR-6125 V01: HU'AAN FACTORS EVALUATION OF REMOTE WELDS. Seventh Program Report March 1993 - December 1994 AFTERLOADING BRACHYTHERAPY. Human Error And Cnticsi lasks d

NUREG/CR-6004: PROBABILISTIC PIPE FRACTURE EVALUATIONS in Remon Afterloading Brachytherapy And Approaches For improved j

FOR LEAK-RATE-DETECTION APPLICATIONS System Performance NUREG/CR 4235: ASSESSMENT OF SHORT THROUGH-WALL CIR-NUREG/CR 6125 V02: HUMAN FACTORS EVALUATION OF REMOTE CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis. March AFTERLOADING BRACHYTHERAPY. Function And Task Analysis.

1990. December 1994.

l NUREG/CR-6251: STAINLESS STEEL SUBMERGED ARC WELD CALIFORNIA, UNIV. OF, SANTA 8AR8 ARA, CA REN6327: WM M EMBEEN ENM WE NU 97: RA E EVALUATIONS OF FUSION LINE TO ANNEALING OF F.EACTOR PRESSURE VESSEL STEELS l

CRACKS IN NUCLEAR PIPE BIMETALLIC WELDS.

NUREG/CR4299: EFFECTS OF TOUGHNESS ANISOTROPY AND CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES COMBINED TENSION, TORSION, AND BENDING LOADS ON FRAC.

l TURE BEHAVIOR OF FERRITIC NUCLEAR PIPE.

NUREG/CR-6283 FIELD SITE INVESTIGATION: EFFECT OF MINE j

NUREG/CR-6300: REFINEMENT AND EVALUATION OF CRACK-OPEN-SEISMICITY ON GROUNDWATER HYDROLOGY.

ING AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH WALL f

CRACKS IN PIPES.

CENTRAL RESEARCH INSTITUTE OF ELECTRIC POWER INDUSTRY j

NUREG/CR-6235; ASSESSMENT OF SHORT THROUGH-WALL CIR-r BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST CUMFERENTIAL CRACKS IN PIPES Expenments And Analysis. March j

LABORATORY 1990. December 1994.

NUREG/CR-2850 V13. DOSE COMMITMENTS DUE TO RADIOACTIVE l

RELEASES FROM NUCLEAR POWER PLANT SITES IN 1991, GEORGE WASHINGTON UNIV., WASHtNGTON, DC NUREG/CR 5975 RO1: INCENTIVE REGULATION OF INVESTOR-NUREG/CR4287: MANAGEMENT CONCEPTS AND SAFETY APPLICA-OWNED NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULA-TIONS FOR NUCLEAR FUEL FACILITIES.

TORS.

NUREG/CR4330: RESULTS OF REGULATORY IMPACT SURVEY OF IDAHO NATIONAL ENGINEERING LABORATORY INDUSTRIAL AND MEDICAL MATERIALS LICENSEES OF THE NUREG/CR4229 V07: FIELD LYSIMETER INVESTIGATIONS: LOW-OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS d

NUREG/CR4331: ATMOSPHERC RELATIVE CONCENTRATIONS IN LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR BUILDING WAKES.

FISCAL YEAR 1994 Annual Report NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY OROOKHAVEN NATIONAL LABORATORY DIRECT CONTAINMENT HEATING IN SURRY.

1 NUREG/CP4140 V01: PROCEEDINGS OF THE TWENTY SECOND NUREG/CR4116 V10: SYSTEMS ANALYSIS PROGRAMS FOR WATER REACTOR SAFETY INFORMATION MEETING Pienary Ses.

HANDS-ON INTEGRATED RELIABILITY EVALUATIONS (SAPHIRE) eion Advanced instrumentation & Control Hardware & Software, VERSION 5.0. Data Loading Manual.

Human Factors Research, IPE & PRA.

NUREG/CR4256 V01: FIELD Lt31 METER INVESTIGATIONS TEST NUREG/CP-0140 V02 PROCEEDINGS OF THE TWENTY SECOND RESULTSlow Level Wastr-Data Base Program. Test Results For WATER REACTOR SAFETY INFORMATION MEETING. Severe Acci-Fiscal Years 1986,1987,1988, And 1989.

35 rn"'

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36 Contractor index d

INSTITUTE FOR CIRCADIUM PHYSIOLOGY NUREG/CR-5857: AGING OF TURBINE DRIVES FOR SAFETY-RELAT.

NUREG/CR4046: ALERTNESS. PERFORMANCE. AND OFF DUTY ED PUMPS IN NUCLEAR POWER PLANTS.

SLEEP ON 8-HOUR AND 12-HOUR NIGHT SHIFTS IN A SIMULATED NUREG/CR4016: AGING AND SERVICE WEAR OF AIR OPERATED CONTINUOUS OPERATIONS CONTROL ROOM SETTING.

VALVES USED IN SAFETY RELATED SYSTEMS AT NUCLEAR POWER PLANTS.

KOREA INSTITUTE OF NUCLEAR SAFETY NUREG/CR4119 V01: MELCOR COMPUTER CODE MANUALS.Pnmer NUREG/CR 6300: REFINEMENT AND EVALUATION OF CRACK OPEN-And User's Guides. Version 18.3 September 1994.

ING AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL NUREG/CR4119 V02:

MELCOR COMPUTER CODE CRACKS IN PIPES, MANUALS. Reference Manuals.Versson 1.8.3 September 1994.

NUREG/CR4318: DATA

SUMMARY

REPORT FOR FISSION PRODUCT LAWRENCE UVERMORE NATIONAL LABORATORY RELEASE TEST Vl-7.

NUREG/CR-5657; AUTOCASK (AUTOMATIC GENERATION OF 3-D CASK MODELS) A Merocomputer Based System For Shipping Cask PACIFIC SCIENCE & ENGINEERING GROUP,INC.

NUREG/CR4125 VOI: HUMAN FACTORS EVALUATION OF REMOTE Design Revew Analysis.

NUREG/CR-6322: BUCKLING ANALYSIS OF SPENT FUEL B ASKET.

AFTERLOADING BRACHYTHERAPY. Human Error And Cntical Tasks

./. I mote Afterloading Brachytherapy And Approaches For trnproved M ARYLAND. UNIV. OF, COLLEGE PARK, MD System Performance.

NUREG/CR 4918 VOS: CONTROL OF WATER INFILTRATION INTO NUREG/CR-6125 V02: HUMAN FACTORS EVALUATION OF REMOTE NEAR SURFACE LLW DISPOSAL UNITS Progress Report Of Field Ex-AFTERLOADING BRACHYTHERAPY. Function And Task Analysis, penments At A Humid Region Site.Beltsville, Maryland.

PRINCETON UNIV., PRINCETON, NJ MODEUNG & COMPUTER SERVICES NUREG/CR4114 V02: AUXILIARY ANALYSES IN SUPPORT OF PER.

NUREG/CR-6327: MODELS FOR EMBRITTLEMENT RECOVERY DUE FORMANCE ASSESSMENT OF A HYPOTHETICAL LOW-LEVEL TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

WASTE FACILITY,Two-Phase Flow And Contaminant Transport in Un-CAK RIDGE NATIONAL LABORATORY g

NUREG/CR 0200 V1 R04: SCALE: A MODULAR CODE SYSTEM FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-SANDIA NATIONAL LABORATORIES CENSING EVALUATION Control Modules.

NUREG/CR4109: THE PROBABILITY OF CONTAINMENT FAILURE BY NUREG/CR 0200 V2P1R4 SCALE: A MODULAR CODE SYSTEM FOR DIRECT CONTAINMENT HEATING IN SURRY.

PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-NUREG/CR4119 V01: MELCOR COMPUTER CODE MANUALS.Pnmer CENSING EVALUATION Functional Modules F1 F8.

And User's Guides. Version 1.8.3 September 1994.

NUREG/CR-0200 V2P2R4. SCALE: A MODULAR CODE SYSTEM FOR NUREG/CR4119 V02:

MELCOR COMPUTER CODE PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Li-MANUALS Reference Manuals.Versson 1.8.3 September 1994.

CENSING EVALUATION. Functional Modules F9-F18.

NUREG/CR 0200 V3 A04: SCALE: A MODULAR CODE SYSTEM FOR SWEDEN, GOVT. OF l

PERFORMING STANDARDIZED COMPUTER ANALYSES FOR Ll-NUREG/CR4300: REFINEMENT AND EVALUATION OF CRACK-OPEN-I CENSING EVALUATION. Miscellaneous.

ING-AREA ANALYSES FOR CIRCUMFERENTIAL THROUGH-WALL l

NUREG/CR-4219 VIO N2: HEAVY-SECTION STEEL TECHNOLOGY CRACKS IN PIPES.

PROGRAM Semiannual Progress Report For Apnt September 1993.

NUREG/CR 5591 V05 N1: HEAVY SECTION STEEL IRRADIATION THE KEVRIC COMPANY,1NC-PROGRAM Semaannual Progress Report For September 1993 Through NUREG/CR-6287: MANAGEMENT CONCEPTS AND SAFETY APPLICA.

March 1994.

TIONS FOR NUCLEAR FUEL FACILITIES.

I I

l 9

International Organization Index This index lists, in alphabetical order, the countries and performing organizations that pre-pired the NUREG/lA reports listed in this compilation. Listed below each country and per-forming organization are the NUREG/lA numbers and titles of their reports. If further infor-m: tion,s needed, refer to the main citation by the NUREG/lA number.

i he wem no NUREG1A mpos puteWud estg te quww I

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Licensed Facility index This index lists the facilities that were the subject of NRC staff or contractor reports. The f:cility 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.

52406 CANDU 30 AECL Technstopes, Inc.,

NUREG/CR4315 S 300 Wens Bar Nuciser Plant, Unn 1, Tennessee NUREG4498 901 Saso say Pouer siston, Umt 1, Viryne Elects & NUREG/CR4100 Veter Autonly Power Co.

S 300 Wens Bar Nucieer Plant, Une 1. Tenneeses NUREG4847 $15 S 300 Say Pouer Siemon, Umt 1. Vepne Eiscenc & NUREG/CR4144 VDS P1 Vessy Authoney Power Co.

S 391 Wens Bar Nucteer Plant, Unil 2, Tennessee NUREG4498 801 S 300 Sey Pouer Bishon, Umt 1, Vepms Electnc & NUREG/CR4144 V06 P2 VeAsy W S 201 Say Power Sisten, List 2. Vogne Electnc & NUREG/CR4100 easy Aushoney

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NRC FORM 336 U.S. NUCLEAR REGULATORY COMMISS4ON

1. REPORT NUMBER (2 80)

(Ams6gned by NRC, Add Vol.,

NRCM 1102, Supp., Rev., and Addendum Num-320i, 3202 BIBUOGRAPHIC DATA SHEET

" " ' * - d *"Y 1 (se. in.iructions on the rever.ei NUREG-4304 Vol. 20, No. 2

2. T Tu: mD SUeTaLE l

3. DATE REPORT PUBUSHED Regulatory and 7bchnical Reports (Abstract Index Journal) l YEAR MONTH i

Compilation for Second Quarter 1995 September 1995 April-June

d. ru OR GRmT NuusER i

5. AUTHOR (5)

6. TYPE OF REPORT Reference 4

f F. PERIOD COVERED (inclusive Dates) i April-Junc

6. PE.-JORMING OHGANIZATION - NAME AND ADDRESS (if t#4C, provide Division Office or Region, U.S. Nuclear Regulatory Commission, and malling address; if contractor, provide name and malling address.)

Division of Freedom of Information and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 5

9. SPONSOHNG ORGANIZATION - NAME AND ADDRESS (tf NRC, type "Same as above"; if contractor, provide NRC Divlelon, Office or Region, U.0, Nuclear Fwgulatory Commleekin, and malling address.)

d Same as 8, above.

10. SUPPLEMENTARY NOTES 11 ABSTRACT (200 words or less)

'Ihis journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceed-ings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by titic and abstract, secondary repon number, personal author, subject, NRC orgamzation for st:.fi and international agreements, contractor, interna'ional organization, and licensed facility.

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13. AVAR.A84UTY STATEMENT

12. KEY WORDS/DESCRIPTORS (Ust words or phrases that will assist researchers ln locatin0 the report.)

Unlimited

***"""* ' * * * ' " ^ * ' "

ibtion abstract index Unclassified (This Report)

Unclassified

16. NUMBER OF PAGES

16. PRICE i

NRC FORM 336 (2-40)

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