ML20100F929
| ML20100F929 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1996 |
| From: | NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V20-N03, NUREG-304, NUREG-304-V20-N3, NUDOCS 9602220246 | |
| Download: ML20100F929 (48) | |
Text
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Vol. 20, No. 3 l
- Regulatory and Technical Reports
- (Abstract Index Journal) l 4
Compilation for l
Third Quarter 1995 July - September 4
U.S. Nuclear Regulatory Commission Omcc of Administration l
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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 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, informat!on 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-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 Atomic Energy Commission, forerunnet agency to the Nuclear Regulatory Commission.
Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register 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 written 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 originating organization or, if they are American National Standards, from the American National Standards Institute,1430 Broadwsy, New York, NY 10018-3308, A year's subscription of this report consists of four quarterly issues.
Vol. 20, No. 3 Regulatory and Technical Reports (Abstract Index Journal)
Compilation for Third Quarter 1995 July - September Date Published: January 1996 Publications Branch Division of Freedom ofInformation and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 d
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t CONTENTS Preface......................................................
v Index Tab
. Main Citations and Abstracts.....................................................
1 1
'e Staff Reports l
e Conference Proceedings e Contractor Reports e Grant Reports t
e intemationcl Agreement Reports Secondary Report Number index..................
2 Personal Author index.............
3 Subject index......................
4 i
NRC Originating Organization index (Staff Reports)..
5 l
NRC Originating Organization index (International Agreernents)......
6 NRC Contract Sponsor index (Contractor Reports).....
7 i
Contractor index..............................
8 intemational Organization index....................
9 Licensed Facility index......................
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PREFACE This compilation consists of bibilographic data and abstracts for the formai regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and 1o cumulate it annually. Your comments will be appreciated. Please send them to:
Technical Publications Section Publications Branch Division of Freedom of Information and Publications Services T-6 E7 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/lA-XXXX. These precede the following indexes:
Secondary Report Number index Personal Authorindex Subject index NRC Originating Organization index (Staff Reports)
NRC Originating Organization Index (International Agreements)
NRC Contract Sponsor index (Contractor Reports)
Contractor index Intemational Organization Index Ucensed Facility Index A detailed explanation of the entries precedes each index.
The bibliographic elements of the main citations are the following:
l Staff Report NUREG-0808 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 report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the microfiche address (for intemal NRC use).
Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABILITY ENGINEERING IN NUCLEAR REGULATION. JANERP, J.S. Argonne National Laboratory. May 1981.141 pp.
8105280299. ANL-81-3. 08632:070.
Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization, (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, RR. 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 internal use).
Grant Report NUREG/GR-0013: APPUCATIONS OF A NEW MAGNETIC MONITORING TECHNIQUE TO IN SITU EVALUA-TION OF FATIQUE DAMAGE IN FERROUS COMPONENTS. JILES, D.C.; B:NER, S.B.; GOVINDARAJU, M.; et al. Iowa State Univ., Ames, lA. 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-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 1986. 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 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 R - revision S - supplement V - volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Government Printing Office (GPO)(T romtheNationalTechnicallnformationService, Springfield, Virginia 22161. Topurchasedocuments from of9 RPO, send a check or money order, payable to the Superintendent of Documents, to the following addiers:
Superintendent of Documents U.S. Government Printing Office Post Office Box 37082 l
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 International Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.
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1 NRC Rrport Codes The NUREG designation, NUREG-XXXX, Indicates that the document is a formal NRC staff-generated report.
Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX This type of identification replaces contractor-established codes such as ORNL/NUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship or the work being reported, in addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference pro-ceedings NUREG/GR is used for NRC grant reports, and NUREG/lA is used for international agreement
- reports, All these report codes are controlled and assigned by the staff of the Technical Publications Section of the NRC Division of Freedom of Information and Publications Services.
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i Main Citations and Abstracts The report listings in this compilation are arranged by report number, where NUREG-XXXX is an NRC staff-originated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CR-XXXX is an NRC contractor-prepared report, and NUREG/lA-XXXX is an inter-national agreement report, The bibliographic information (see Preface for details) is followed by a brief abstract of this report.
NUREG-0040 V19 N02: LICENSEE CONTRACTOR AND NUREG-0304 V20 N01: REGULATORY AND TECHNICAL RE-VENDOR INSPECTION STATUS REPORT. Quarterly PORTS (ABSTRACT INDEX JOURNAL). Compilation For First Report,Apnt-June 1995 (White Book)
- Office of Nuclear Reac-Quarter 1995, January-March.
- Division of Freedom of informa-tor Regulation (Post 941001). August 1995. 181pp.
tion & Publications Services (Post 940714). July 1995. 48pp.
9500070144.85398:116.
9508160248. 85041:277.
This periodscal covers the results of inspections performed by This journal includes all formal reports in the NUREG series the NRC's Special Inspection Branch, Vendor inspection Sec-prepared by the NRC staff and contractors; proceedings of con-tion, that have been dist,ibuted to the inspection organizations ferences and workshops; as well as international agreement re-dunng the penod from April through June 1995.
ports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, NUREG-0090 V17 N04: REPORT TO CONGRESS ON ABNOR-subject, NRC organization for staff and international agree.
MAL OCCURRENCES. October December 1994.
- Office for ments, contractor, international organization, and licensed facili-Analysis & Evaluation of Operational Data, Director. May 1995.
ty.
39pp. 9511140069. 86174.317.
NUREG-0325 R18: U.S. NUCLEAR REGULATORY COMMISSION Section 208 of the Energy Reorganization Act of 1974 identi.
ORGANIZATION CHARTS AND FUNCTIONAL fies an abnormal occurrence (AO) as an unscheduled incident or event that the Nuclear Regulatory Commission determines to STATEMENTS. July 23,1995.
- Ofc of Personnel (Post 870413).
be significant from the standpoint of pubhc health or safety and July 1995. 67p 9511060194.8 94 255 requires a quarterly report of such occurrences to be made to Congress. This report provides a desenption of those incidents Nuclear Regulatory Commission offices, divisions, and branches and events that have been determined to be AOs dunng the are presented.
penod of October 1 through December 31, 1994. The report NUREG-0525 V02 R03: SAFEGUARDS
SUMMARY
EVENT LIST addresses four Aos at NRC-licensed facilities. These occur.
(SSEL). January 1,
1990 Through December 31, 1994.
rences involved the following: a genenc concern relating to core FADDEN,M.; YARDUMIAN.J. Ooerations Branch. July 1995.
shroud cracking in boiling water reactors; recumng incidents of 140pp. 9511060198. 86103:096.
administenng higher doses than procedurally allowed for diag-The Safeguards Summary Event List provides brief summa-nostic imaging at a single facility; one medical teietherapy mis-rios of hundreds of safeguards-related events involving nuclear administration and one medical brachytherapy misadministra-material or facilities regulated by the U.S. Nuclear Regulatory tion. Agreement States submitted four AO reports. These four Commission. Events are desenbed under the categories: Bomb-occurrences involved the following: one major contamination at related, intrusion, MissirWAllegedly Stolen, Transportation-relat-a commercial facility; two medical brachytherapy misadministra-ed. Tampenng/Vandalisrn, Arson, Firearms-related Radiological
~
tions; and one medical teletherapy misadministratan. The report Sabotage, Non-radiological Sabotage, and Miscellaneous. Be-also contains updates of seven AOs previously reported by the cause of the public interest, the Miscellaneous category also in.
Agreement States. Two "Other Events of Interest" are also ciudes events reported involving source material, byproduct ma-being reported. These occurrences involved the operability of tenal, and natural uranium, which are exempt from safeguards safety relief valves at a nuclear powerplant, and an error in the requirements. Information in the vent desenptions was obtained installation process of a Leksell Gamma Knife " Teletherapy from official NRC sources.
unit that resulted in an operational failure.
NUREG-0540 V17 N05: TITLE LIST OF DOCUMENTS MADE NUREG-0090 V18 N01: REPORT TO CONGRESS ON ABNOR*
PUBLICLY AVAILABLE.May 1 31, 1995.
- Division of Freedom MAL OCCURRENCES. January March 1995.
- Office for Analy-of information & Pubhcations Services (Post 940714). July 1995.
ses & Evaluation of Operational Data Director. July 1995.25pp-300pp. 9511140075. 86175:001.
9507250296. 84831:118-This document is a monthly publication containing descrip.
Section 208 of the Energy Reorganization Act of 1974 ident
tions of information received and generated by the U S. Nuclear fies an abnormal occurrence (AO) as an unscheduled incident Regulatory Commission (NRC). This information includes (1) or event that the Nuclear Regulatory Commission determines to docketed material associated with civilian nuclear power plants be significant from the standpoint of public health or safety and and other uses of radioactive materials, and (2) nondocketed requires a quarterly report of such occurrences to be made to material received and generated by NRC pertinent to its role as Congress. This report provides a description of those incidents a regulatory agency. The following indexes are included: Per-and events that have been determined to be AOs dunng the sonal Author, Corporate Source, Report Number, and Cross period of January 1 through March 31, 1995. This report ad-Reference of Enclosures to Principal Documents.
dresses one AO at an NRC-heensed facility which involved a medical brachytherapy misadministration. The report also con-NUREG-0540 V17 N06: TITLE LIST OF DOCUMENTS MADE tains updates of one AO previously repor1ed by an NRC hcens-PUBLICLY AVAILABLE. June 1 30, 1995.
- Division of Freedom
)
ee and three AOs previously reported by the Agreement States.
of Information & Publications Services (Post 940714). August No "Other Events of Interest" items are being reported.
1995. 276pp. 9508160276. 85041:001.
1
2 Main Citations and Abstracts This document is a monthly publication containing descrip-NUREG-0940 V14 N2 P1:
ENFORCEMENT tions of information received and generated by the U.S. Nuclear ACTIONS:SIGNIFICANT ACTIONS RESOLVED,1NDIVIDUAL Regulatory Commission (NRC). This information includes (1)
ACTIONS.Ouarterly Progress Report. April-June 1995.
- Ofc of docketed material associated with civilian nuclear power plants Enforcement (Post 870413). August 1995. 226pp. 9509080019.
and other uses of radioactrve materials, and (2) nondocketed 85404:138.
material received and generated by NRC pertinent to its role as This compilation summarizes significant enforcement actions a regulatory agency. The following indexes are included. Per-that have been resolved during one quarterly period (April.
sonal Author, Corporate Source, Report Number, and Cross June 1995) and includes copies of Orders sent by the Nuclear Reference of Enclosures to Principal Documents.
Regulatory Commission to individuals with respect to these en-forcement actions. It is anticipated that the information in this NUREG-0540 V17 NG7: TITLE LIST OF DOCUMENTS MADE publication will be widely disseminated to managers and em-PUBLICLY AVAILABLE. July 1-31, 1995.
- Division of Freedom ployees engaged in activities licensed by the NRC. The Com-of Information & Pubhcations Services (Post 940714) Septem-mission believes this information may be useful to licensees in ber 1995. 27Bpp. 9510030198. 85664:001.
making employment decisions.
See NUREG 0540,V17,N06 abstract.
NUREG-0940 V14 N2 P2:-
ENFORCEMENT NUREG-0750 V40: NUCLEAR REGULATORY COMMISSION ACTIONS:SIGNIFICANT ACTIONS RESOLVED, REACTOR ISSUANCES. Opinions And Decisions Of The Nuclear Regula-LICENSEES.Ouarterly Progress Report April-June 1995.
- Ofc tory Commission With Selected Orders. July-December 1994.
- of Enforcement (Post 870413). August 1995. 189pp.
Divis,on of Freedom of Information & Publications Services 9509080016.85405:016.
(Post 940714). July 1995. 400pp. 9508300374. 85286:001.
This compilation summarizes significant enforcement actions Legal issuances of the Commission, the Atomic Safety are Li-that have been resolved during one quarterfy penod (April -
censing Board Panel, the Administrative Law Judgos, and NRC June 1995) and includes copies of letters, Notices, and Orders Program Offices are presented.
sent by the Nuclear Regulatory Commission to reactor licens-eos with respect to these enforcement actions. It is anticipated NUREG-0750 V41102: INDEXES TO NUCLEAR REGULATORY that the information in this publication will be widely disseminat-COMMISSION ISSUANCES. January-June 1995.
- Division of ed to managers and employees engaged in activities licensed Freedom of information & Pubhcations Services (Post 940714).
by the NRC, so that actions can be taken to improve safety by September 1995. 65pp. 9510180192. 85849:001.
avoiding future violatons similar to those desenbed in this pubil-Digests and indexes for issuances of the Commission, the caton.
Atomic Safety and Licensing Board Panel, The Administratwe Law Judges, the Directors' Decisions, and the Decisions on Pe-NUREG-0940 V14 N2 P3: ENFORCEMENT ACTIONS: SIGNIF1-titions for Rulemaking are presented.
CANT ACTIONS RESOLVED MATERIAL LICENSEES.Ouarterly Progress Report April-June 1995.
- Ofc of Enforcement (Post NUREG-0750 V41 N05: NUCLEAR REGULATORY COMMISSION 870413). August 1995. 223pp. 9509130141. 85432:111.
ISSUANCES FOR MAY 1995.Pages 321-380.
- Division of Freedom of Information & Publications Services (Post 940714).
This compilation summarizes significant enforcement actions July 1995. 68pp. 9507250293. 84831:050.
that have been resolved during one quarterly period (April -
June 1995) and includes copies of letters, Notices, and Orders t
See NUREG.0750,V40 abstract.
sent by the Nuclear Regulatory Commission to material heens-NUREG-0750 V41 N06: NUCLEAR REGULATORY COMMISSION ees with respect to these enforcement actions. It is anticipated l
ISSUANCES FOR JUNE 1995.Pages 381-496.
- Division of that the information in this publication will be widely disseminat-Freedom of Informat,on & Pubhcations Services (Post 940714).
ed to managers and employees engaged in activities licensed August 1995.1240p. 9509080022. 85405:146.
by the NRC, so that actions can be taken to improve safety by See NUREG 0750,V40 abstract.
avoiding future violations similar to those described in this publi-cation.
NUREG-0750 V42 N01: NUCLEAR REGULATORY COMMISSION ISSUANCES FOR JULY 1995.Pages 145.
- Division of Free.
NUREG-1123 R01: KNOWLEDGE AND ABILITIES CATALOG dom of Information & Publications Services (Post 940714).
FOR NUCLEAR POWER PLANT OPERATORS: BOILING August 1995. 53pp. 9509080026. 85405:270.
WATER REACTORS.
- Office of Nuclear Reactor Regulation See NUREG-0750,V40 abstract.
(Post 941001). August 1995. 412pp. 9509250374. 85579:001.
This document provides the basis for the development of NUREG-0837 V15 NO2: NRC TLD DIRECT RADIATION MON!-
content-valid licensing examinations for reactor operators and TORING NETWORK. Progress Report. April-June 1995.
senior reactor operators. The examinations developed using the STRUCKMEYER,R. Region 1 (Post 820201). August 1995.
BWR catalog will cover those topics listed under Title 10, Code 230pp. 9508300331. 85287:060.
of Federal Rogulatons, Part 55. The BWR catalog contains ap.
This report provides the status and results of the NRC Ther-proximately 7,000 knowledge and abihty (K/A) statements for moluminescent Dosimeter (TLD) Direct Radiation Monitonng reactor operators and senior reactor operators. Each K/A state-Network. It presents the radiation levels measured in the vicinity ment has been rated for its importance to safe operation of the of NRC licensed facihties throughout the c:wtry for the second plant in a manner ensunng personnel and public health and quarter of 1995, safety. The BWR K/A catalog is organized into six major sec-tions: Organizaten of the Catalog; Plant Wide Genenc Knowl-NUREG-0938 V14 N01:
NRC REGULATORY edge and Abilities; Plant Systems Grouped by Safety Fur.csons; AGENDA. Semiannual Report, January-Jure 1995.
- Division of Emergency and Abnormal Plant Evolutions; Components; and l
Freedom of Informaton & Pubhcations Services (Post 940714).
Theory.
l September 1995. 56pp. 9510030203. 85663:193.
l The NRC Regulatoiy Agenda is a compilation of all rules on NUREG-1145 V11: U.S. NUCLEAR REGULATORY COMMISSION which the NRC has recently completed action, or has proposed 1994 ANNUAL REPORT.
- Office of Administration, Director action, or is considenng action, and all petitions for rulemaking (Post 940714). June 1995. 300pp. 9507170098. 84671:001.
which have been received by the Commission and are pending This report covers the major activities, events, decisions, and disposition by the Commission. The Regulatory Agenda is up-planning that took place dunng Fiscal Year 1994 within the U.S.
dated and issued semiannually.
Nuclear Regulatory Commission (NRC) or involving the NRC.
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NUREG-1286 V09: NRC SAFETY RESEARCH IN SUPPORT OF license from the Nuclear Regulatory Commission. This report REGULATION FY 1994.
- Office of Nuclear Regulatory Re-sets out the Panel's caseload during the year and summertzes, 1
search (Post 941217). June 1995. 100pp. 9507200206.
highlights, and analyzes how the wide-ranging issues raised in 84750:001, those proceedings were addressed by the Panel's judges and 7
This report, the tenth in a series of annual reports, was pre-licensing boards.
j pared in response to congressional inquines concerning how i
nuclear regulatory research is used. It summarizes the accom.
NUREG-1423 V06: A COMPILATION OF REPORTS OF THE AD-phshments of the Office of Nuclear Regulatory Research during VISORY COMMITTEE ON NUCLEAR WASTE. July 1993 June FY 1994. The goal of the Office of Nuclear Regulatory Re-1995.
- Advisory Committee on Nuclear Waste. August 1995.
l search (RES) is to ensure the availability of sound technical 75pp. 9509130173. 85433:144.
i bases for timely rulemaking and related decisions in support of This compilation contains 13 reports issued by the Advisory i
1 NRC regulatory / licensing / inspection activities. RES also has re-Committee on Nuclear Waste (ACNW) during the sixth and sev-l sponsibilities related to the resolution of generic safety issues enth years of its operaten. The reports were submitted to the
{
and to the review of licensee submittals regarding individual Chairman and Commissioners of the U.S. Nuclear Regulatory i
plant examinations. It is the responsibility of RES to conduct the Commission. All reports prepared by the Committee have been j
NRC's rulemaking process, including the issuance of regulatory made available to the public through the NRC Public Document guides and rules that govern NRC licensed activities.
Room and the U.S. Library of Congress.
NUREG 1272 V00 N02: OFFICE FOR ANALYSIS AND EVALUA-NUREG-1506 DRFT FC: A NONPARAMETRIC STATISTICAL TION OF OPERATIONAL DATA.1993 Annual Report Nuclear METHODOLOGY FOR THE DESJGN AND ANALYSIS OF l
Materials.
- Office for Analysis & Evaluation of Operational 4
FINAL STATUS DECOMMISSIONING SURVEYS. Draft Report 1
Data, Director. May 1995.122pp. 9511140066. 86176:001.
For Comment. GOGOLAK C.V. Energy, Dept.of, Environmental The annual report of the U.S. Nuclear Regulatory Commis-Measurements Laboratory. HUFFERT,A.M.; POWERS,G.E. Divi-sion's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during 1993. The sion of Regulatory Applications (Post 941217). August 1995.
216pp. 9509200281. 85541:080.
report is published in two separate parts. NUREG-1272, Vol. 8, l.
No.1, covers power reactors and presents an overview of the This report describes a nonparametric statistical methodology operating experience of the nuclear power industry from the for the design and analysis of final status decommissioning sur-NRC perspective, including comments about the trends of some Veys in support of the proposed rulemaking on decommission-4 key performance measures. The report also includes the princi.
ing. The techniques described are attematives to the existing i
pal findings and issues identified in AEOD studies over the past parametric statistical methodology in NRC draft NUREG/CR-(
year and summanzes information from such sources as licensee 5849, " Manual tor Conducting Radiological Surveys in Support event reports, diagnostic evaluatons, and reports to the NRC's of License Termination." Proposed nonparametric statistical Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear methods for testing compliance with decommissioning criteria 1
materials and presents a review of the events and concerns are provided for radionuclides which occur in natural back-j during 1993 associated with the use of licensed material in non-ground and for those that do not occur in natural background.
reactor applications, such as personnel overexposures and The tests considered apphcable are the Wilcoxon Signed Ranks med<.al mesadministrations. Note that the subtitle of No. 2 has test, Sign test, and Quantile test for the analysis of a single been changed from "Nonreactors" to " Nuclear Materials." Both data set, and the Wilcoxon Rank Sum test and a Quantile test reports also contain a discussion of the incident investigation for comparing two independent data sets. An Elevated Meas-Team program and summarize both the incident investigation urement Companson is also described to deal with any unusual-i Team and Augmented inspection Team reports. Each volume ly high observations. This report contains information on the contains a hst of the AEOD reports issued for 1981 1993.
Data Quahty Objectives process as it relates to the planning and analysis of final site surveys. The proposed process in-I HUREG 1307 ROS:
REPORT ON WASTE BURIAL cludes methods for determining the number of samples needed CHARGES. Escalation Of Decommissioning Waste Deposal to obtain statistically valid comparisons with decommissioning i
Costs At Low-Level Waste Burid Facihties.
- Division of Regula-criteria and the methods for conducting the statistical tests with tory Apphcations (Pos! 941217). August 1995. 59pp.
the resulting sample data.
9509070078.85404 079.
One of the reekements placed upon nuclear power reactor NUREG-1506 DRFT FC: MEASUREMENT METHODS FOR RAD!.
licensees by the U.S. Nuclear Regulatory Commission (NRC) is OLOGICAL SURVEYS IN SUPPORT OF NEW DECOMMIS-4 for the hcensees to penodically adjubt the estimate of the cost SlONING CRITERIA. Draft Report For Comment. HUFFERT,A.M.
of decommissioning their plants, en dollars of the current year' Division of Regulatory Applications (Post 941217). MILLER.K.M.
as part of the process to provido reasonable assurance that Energy, Dept.of, Environmental Measurements Laboratory.
adequate funds for decommissioning will be available when August 1995. 78pp. 9509200363. 85541:001.
needed. This report, which is scheduled to be revised periods-This report dnscribes proposed methodologies for measuring i
cally, contains the development of a formula for escalating de-low-level radiation and radioactivity that could be used in con-commissioning cost estimates that is acceptable to the NRC, ducting surveys associated with decommissioning of heensed a
and contains values for the escalation of radioa9tive waste NRC facilities. Guidance on survey planning within the context 4
burial costs, by site and by year. The hcensees may u0e the for-of tM Data Quahty Objective approach and on specific instru-i mula, the coefficients, and the burial escalation from tha report mentation for measurements of gross and nuchde-specific rad >-
in their escalation analyses, or they may use an escalatien rate ation and radioactivity is given. Scanning, direct measurements, at least equal to the escalation approach presented hereir.
and sampkng are discussed in terms of the application to par-4 NUREG 1363 V06: ATOMIC SAFETY AND LICENSING BOARO t:cular measurement locations. The basic survey meter tech-PANEL BIENNIAL REPORT. Fiscal Years 1993 1994.* Atomic nilues that are commonly used at present are outhned and Safety & Licensing Board Panel. August 1995. 54pp.
more detailed iriformation is given on the capabihties and apph-9509070103. BIENNIAL 85398:297.
cation of in situ spectrometnc techniques for providing high sen-In Fiscal Year 1993, the Atomic Safety and Licensing Board sitivity for individual photon-emitting radionuchdes. The use of j
Panel ("the ParwJ") handled 30 proceedings. In Fiscal Y3ar vanous techniques in concert is recommended, as the different 1994, the Panel handled 36 proceedings. The cases addressed measurements, taken co'lectively, serve as a quahty control issues in the construction, operation, and maintenance of com-check. The methodologies described provide the means to mercial nuclear power reactors and other activities requiring a measure residual radionuchdes at coticentrations corresponding 5
4
J 4
Main Citations and Abstracts to the proposed decommissioning criteria which are in the range vision of Engineenng of the Office of Nuclear Reactor Regula-of 3 to 15 mrem per year for unrestricted release of a facility.
tion. For the containment structures most of the information re-lated to the degraded conditions came from the hcensees as NUREG-1507 DRFT FC: MINIMUM DETECTABLE CONCENTRA-part of the Licensing Event Report System (10 CFR 50.73), or TiONS WITH TYPICAL RADIATION SURVEY INSTRUMENTS as part of the requirement under limiting condition of operation FOR VARIOUS CONTAMINANTS AND FIELD of the plant specific Technical Specsfications. Most of the infor-CONDITIONS. Draft Report For Comment. HUFFERT A.M. Divp mation related to the Jegradation of other structures and civil seon of Regulatory Apphcations (Post 941217).
ABELOutST.E.W. Oak Ridge Associated Universities.
engineenng features was extracted from the industry survey, the BROWN W.S. Brookhaven National Laboratory. August 1995.
reported incidents, and the plant visits. The report discusses the 160pp. 9509200367,85540:156.
condition of the structures and civil engineering features at op-This report desenbes and quantitatively evaluates the effects erating nuclear power plants and provides information that of vanous factors on the detection sensitivity of commercially would help detect, alleviate, and correct the degraded condi-available portable field instruments being used to conduct radio-tions of the structures and civil engineering features.
j logical surveys in support of decommissioning. NRC is currently NUREG 1600: GENERAL STATEMENT OF POLICY AND PROCE.
involved in a rulemaking effort to establish residual contamina-tion entena for release of facilities for restricted or unrestricted DURE FOR NRC ENFORCEMENT ACTIONS. Enforcement use. in support of that rulemaking, NRC has prepared a draft Policy.
- Ofc of Enforcement (Post 870413). July 1995. 35pp.
Generic Environmental Impact Statement (GEIS), consistent 9507250299. 84831:142.
with the National Environmental Pokcy Act. The effects of this This document includes the U.S. Nuclear Regulatory Commis-new rulemaking on the overall cost of decommissioning are sion's (NRC's or Commission's) revised General Statement of arnong the many factors considered in the GEIS. The overall Policy and Procedure for Enforcement Actions (Dforcement cost includes the costs of decontamination, waste disposal, and Policy) as it was published in the Federal Register on June 30, radiological surveys to demonstrate comphance with the appli-1995 (60 FR 34381). This document also includes the notice cable guidelines. An important factor affecting the costs of such announcing the removal of the Enforcement Policy from the surveys is the minimum detectable concentrations (MDCs) of Code of Federal Regulations (60 FR 34380; June 30,1995).
field survey instruments in relation to the residual contamination The Enforcement Pokcy is a general statement of policy ex-guidelines. The purpose of this study was two-fold. First, the laining the NRC's policies and procedures in initiating enforce-data were used to determine the vahdity of the theoretical ment actions, and of the presiding officers and the Commission MDCs used in the draft GEIS. Second, the results of the study, in reviewing these actions. This policy statement is applicable to published herein, provide guidance to hcensees for (a) selection enforcement in matters involving the radiological health and and proper use of portable survey instruments and (b) under.
safety of the public, including employees' health and safety, the standing the field conditions and the extent to which the capa.
common defense and secunty, and the environment. This state-bikties of those instruments can be hmited. Such instruments as gas proportional, Geiger Mueller, zinc sulfide, and tndium iodide ment of general policy and procedure is published as NUREG-1600 to provide widespread dissemination of the Commission's detectors were evaluated.
me w
a s a p% swant aM nd NUREG 1519: SURFACE INTERACTIONS OF CESIUM AND a mgdah De @msssen may hate hm Ws sWent BORIC ACID WITH STAINLESS STEEL GROSSMAN,N. Drw-of policy and procedure as appropnate under the circumstances sion of Systems Technology (Post 941217). August 1995.
of a padicular casa 104pp. 9509130158. 85432:009 in this report, the effects of cesium hydroxide and bonc acid NUREG/CP-0142 V01: PROCEEDINGS OF THE 7TH INTERNA.
on oxidized stainless steel surfaces at high temperatures and TIONAL MEETING ON NUCLEAR REACTOR THERMAL-HY-near one atmosphere of pressure are investigated. This is the DRAULICS (NURETH-7). Sessions 1-5. BLOCK,R.C.; FEINER,F, first experimental investigation of this chemical system. The ex-Amencan Nuclear Socie'Y-September 1995-509pp-penmental investigations were performed using a mass spec-9509110196.85399:001.
trometer and a mass electrobalance. Surfaces from the different This volume includes papers presented at the 7th Internation-experiments were examined using a scanning electron micro.
al Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-7) scope to identify the presence of deposited species, and elec.
tron spectroscopy for chemical analysis to identify the species September 10-15,1995 at Saratoga Spnngs, N.Y. The following deposited on the surface. The analysis couples vaponzation, subjects are discussed progress in analytical and experimental deposition, and desorption of the compounds formed under work on the fundamentals of nuclear thermal-hydraulics, the de-conditions similar to what is expected during certain nuclear re-velopment of advanced mathematical and numerical methods, actor accidents. Cesium deposits on an oxidized stainless steel and the apphcation of advancements in the field in the develop-surf ace at temperatures between 1000 and 1200 Kelvin and on ment of novel reactor concepts. Also combined issues of ther-stainless steel surfaces coated with bonc oxide in the same mal-hydraulics and reactor / power plant safety, core neutronics temperature ranges. The mechanism for such deposition in-and/or radiation.
volved the cherncal reaction between cesium and chromate.
Some revaporization in the cesium hydroxide-bonc acid system NUREG/CP-0142 V02: PROCEEDINGS OF THE 7TH INTERNA.
was observed. Under the conditions given, boric acid will react TIONAL MEETING ON NUCLEAR REACTOR THERMAL-HY-with cesium hydroxide to form cesium metaborate. A model is DRAULICS (NURETH-7). Sessions 6 11.
BLOCK,R.C.;
proposed for tlws chemical reaction.
FEINER.F. Amencan Nuclear Society. September 1995.806pp.
9509110202. 85402:001, NUREG-1522: ASSESSMENT OF INSERVICE CONDITIONS OF SAFETY-RELATED NUCLEAR PLANT STRUCTURES.
See NUREG/CP-0142,V01 abstract.
ASHAR,H.; BAGCHl,G. Office of Nuclear Reactor Regulation NUREG/CP-0142 V03: PROCEEDINGS OF THE 7TH INTERNA-(Post 941001). June 1995.116pp. 9508230244. 85127:001.
TIONAL MEETING ON NUCLEAR REACTOR THERMAL HY.
The report is a compilation from a number of sources of infor.
mation related to the condition of structures and civil engineer-DRAULICS (NURETH-7). Sessions 12-16.
BLOCK R.C.;
ing features at operating nuclear pcwer plants in the U.S. The FEINER.F. American Nuclear Society. September 1995.916pp.
most significant information came from the hands-on inspection 9509110205. 85386:001.
of the six old plants (licensed prior to 1977) performed by the See NUREG/CP-0142,V01 abstract.
staff of the Civil Engineenng and Geosciences Branch in the Di-
Main Citations and Abstracts 5
NUREG/CP-0142 V04: PROCEEDINGS OF THE 7TH INTERNA-manes of invited papers concerning nuclear safety issues from TtONAL MEETING ON NUCLEAR REACTOR THERMAL HY-U S. govemment laboratones, the electric utilities, the nuclear DRAULICS (NURETH-7) Sessions 17 24.
BLOCK.R.C.;
industry, and from foreign governments and industry are also in-FEINER.F. American Nuclear Society. September 1995. 845pp.
cluded. The summanes have been compiled in one report to 9509110210. 85396:001.
provide a basis for meaningful discussion and information ex-See NUREG/CP-0142,V01 abstract.
change dunng the course of the meeting and are gven in the NUREG/CP-0144 V01: A WORKSHOP ON DEVELOPING RISK order of their presentation in each session.
ASSESSMENT METHODS FOR MEDICAL USE OF RADIOAC-NUREG/CR-2907 V13: RADIOACTIVE MATERIALS RELEASED TIVE MATERIAL. Summary. TORTORELLI,J.P. Idaho National FROM NUCLEAR POWER PLANTS. Annual Report 1932.
Engineering Laboratory. August 1995. 122pp. 9508230352.
TICHLER.J.; DOTY,K.; LUCADAMO,K. Brookhaven National o t was held at the Idaho National Engineenng Labo-If85430 ratory, August 16-18, 1994, on the topic of risk assessment on Releases of radioactive materials in airborne and liquid ef-medical devices that use radioactrve isotopes its purpose was fluents from commercial light water reactors dunng 1992 have to review past efforts to develop a nsk assessment methodolo-been compiled and reported. Data on solid waste shipments as gy to evaluate these devices and to develop a program plan weh as selected operating information have been included. This and scoping document for future development. This report pre-report supplements earlier annual reports issued by the former sents a summary of that workshop, related technical papers
- Atomic Energy Commission and the Nuclear Regulatory Com-presentation material, and a transcnpt of the workshop. Partics-niission. The 1992 release data are summanzed in tabular form.
pants included experts in the fields of radiation oncology, med!-
Data covenng specific radionuclides are summarized.
cal physics, risk assessment, human-error analysis, and human factors. Staff from the U.S. Nuclear Regulatory Commission NUREG/CR-4667 V19: ENVIRONMENTALLY ASSISTED CRACK-(NRC) associated with the regulation of medical uses of radio-ING IN LIGHT WATER REACTORS. Semiannual Report. April-active materials and with research into risk-assessment meth-September 1994. CHOPRA.O.K.; CHUNG,H.M.; GAVENDA,D.J.;
ods participated in the workshop. The workshop participants et al. Argonne National Laboratory. September 1995. 67pp.
concurred in NRC's intended use of nsk assessment as an im-9510030169. ANL 95/25. 85688:172.
portant technology in the development of regulations for the This report summarizes work performed by Argonne National medical use of radioactive material and encouraged the NRC t Laboratory (ANL) on fatigue and environmentally assisted crack-proceed rapidly with a pilot study. Specific recommendations ng (EAC) in light water reactors from April to September 1994.
are included in the executive summary and the body of this Topics that have been investigated include (a) fatigue of carbon report and low-alloy steel used in piping and reactor pressure vessels.
NUREG/CP-0144 V02: A WORKSHOP ON DEVELOPING RISK (b) EAC of austenitic stainless steels (SSs) and Alloy 600, and ASSESSMENT METHODS FOR MEDICAL USE OF RADIOAC-(c) irradiation-assisted stress corrosion cracking (IASCC) of TlVE MATERIALSupporting Documents. TORTORELLI.J.P.
Type 304 SS. Fatigue tests have been conducted on A106-Gr B Idaho National Engineering Laboratory. August 1995. 330pp.
and A533 Gr B steels in oxygenated water to determine wheth-9508230354. INEL-94/0111. 85119.001, er a slow strain rate apphed dunng different portions of a ten-See NUREG/CP-0144,V01 abstract.
sile-loading cycle are equally effective in decreasing fatigue hfe.
NUREG/CP-0146: PROCEEDINGS OF THE WORKSHOP ON Crack growth data were obtained on fracture-mechanics speci-mens of SSs and Alloy 600 to investigate EAC in simulated boil-GATE VALVE PRESSURE LOCKING AND THERMAL BINDING.
BROWN.E.J. Dwision of Safety Programs (Post 870413). July ing water reactor (BWR) and pressunzed water reactor environ-ments at 289 degrees C. The data were compared with predic-1995. 268pp. 9508090040, 84964'00 f.
tions from crack growth correlations developed at ANL for SSs The purpose of the Workshop on Gate Valve Pressure Lock-in water and from rates in air from Sectico XI of the ASME ing and Thermal Binding was to discuss pressure locking and Code. Microchemical changes in high-and commercial-punty thermal binding issues that cculd lead to inoperable gate valves Type 304 SS specimens from control-blade absorber tubes and in both boiling water and prescurized water reactors. The goal a control-blade sheath from operating BWRs were studied by was to foster exchange of information to deve;op the technical Auger electron spectroscopy and scanning electron microscopy bases to understand the phenomena, identify the components to determine whether trace impurity elements may contnbute to that are susceptible, discuss actual events, discuss the safety lASCC of these matenals.
significance, and illustrate known corrective actions that can prevent or hmit the occurrence of pressure locking or thermal NUREG/CR 5535 V01: RELAPS/ MOD 3 CODE MANUAL. Code binriing. The presentations were structured to cover U.S. Nucle.
Structure. System Models, And Solution Methods.
- Idaho Na-ar Regulatory Commission staff evaluation of operating experi-tional Engineenng Laboratory. August 1995.
412pp.
ence and planned regulatory actrvity; industry discussions of 9509150284. INEL-95/0174. 85495:001, specific events, including foreign expenence, and efforts to de-The RELAPS/ MOD 3 computer code has been developed for termine causes and alleviate the affects; and valve vendor ex-best-estimate simulation of hght water reactor coolant systems penence and recommended corrective action. The discussions dunng postulated accidents. The code models the coupled be-sndicated that identifying valves susceptible to pressure locking havior of the reactor coolant system and the core for loss-of-and thermal banding was a complex process involving knowl-coolant accidents and operational transients such as anticipated edge of components, systems, and plant operations. The cor.
transient without scram, loss of offsite power, loss of feedwater, rectwe action options are vaned and straightforward.
and loss of flow. A genenc modeling approach is used that per-NUREG/CP-0148: TRANSACTIONS OF THE TWENTY-THIRD mits simulating a vanety of thermal-hydraulic systems. Control WATER REACTOR SAFETY INFORMATION MEETING.
system and secondary system components are included to MONTELEONE,S. Brookhaven National Laboratory. September permit modeling of plant controls, turbines, condensers, ano 1995. 76pp. 9510060240. 85746:182.
secondary feedwater systems. RELAP5/ MOD 3 code documen-This report contains summanes of papars on reactor safety tation is divided into seven volumes: Volume i presents model-research to be presented at the 23rd Water Reactor Safety in-ing theory and associated numerical solution schemes; Volume formation Meeting at the Bethesda Marriott Hotel, Bethesda, il details instructions for code applicatinn and input data prepa.
Maryland, October 23-25,1995. The summanes bnefly desenbe ration; Volume ill presents the results of developmental assess-the program and results of nuclear safety research sponsored ment cases that demonstrate and venfy the models used in the by the Office of Nuclear Regulatory Research, U S. NRC. Sum-code: Volume IV discusses in detail RELAP5 models and corre.
1
6 Main Citations and Abstracts lations; Volume V presents guidehnes that have evolved over posibve test rate at 1.22%. Licensee employees and long-term the past several years through the use of the RELAPS code; contractors had lower combined positive test rates (.33% and Volume VI discusses the numencal scheme used in RELAP5;
.49% respectively). Of the substances tested, marijuana was re-and Volume Vil presents a collection of independent assess-sponsible for the highest percentage of positive test results ment calculations.
(52.79%), followed by cocaine (24.57%) and alcohol (17.93%).
NUREG/CR-5535 V02: RELAPS/ MOD 3 CODE MANUAL. User's NUREG/CR-5944 V02: A CHARACTERIZATION OF CHECK Guide And input Requirements.
- Idaho Natonal Engineenng VALVE DEGRADATION AND FAILURE EXPERIENCE IN THE Laboratory. August 1995. 323pp. 9509150290. INEL-95/0174.
NUCLEAR POWER INDUSTRY.1991 Failures.
8549&O49.
MCELHANEY,K.L Oak Ridge Nabonal Laboratory. July 1995.
See NUREG/CR-5535,V01 abstract.
87pp. 9508090036. ORNL-6734. 84963:003.
NUREG/CR-5535 V04: RELAPS/ MOD 3 CODE MANUAL.Models Review and characterization of check valve failures taken And Correlations.
- Idaho National Engineenng Laboratory.
from the Institute of Nuclear Power Operation's Nuclear Plant August 1995. 430pp. 9509150303. INEL 95/0174. 85498.001.
Reliability Data System was performed in accordance with part two of a three-phase project sponsored by the U.S. Nuclear See NUREG/CR-5535,V01 abstract.
""*"'m.The analysis was performed for check 9#
NUREG/CR-5535 V05 R1-RELAPS/ MOD 3 CODE a
s inmMM e uNam M va a
s c um MANUAL. User's Guideline. FLETCHER,C.D - SCHULTZ,R.R-previous analysis performed for the time period 1984-1930. To Idaho National Engineenng Laboratory. Aug'ust 1995. 293pp.
maintain consistency and for ease of trending, the 1991 analy-9509150307. INEL 95/0174. 85497.008.
sis presents the same parameters and cross-correlations in es.
See NUREG/CR 5535,V01 abstract, sentially the same format as the 1984 1990 study. Additonal NUREG/CR-5591 VOS N2: HEAVY SECTION STEEL IRRADIA-data was obtained for the 1991 analysis, including information TION PROGRAM. Progress Report For April 1994 Through Sep-related to specific check valve type. This information is present-tember 1994. CORWIN,W.R. Oak Ridge National Laboratory.
ed in a separate section of the report.
July 1995. 76pp. 9508160263. ORNL/TM 11568. 85042:092.
NUREG/CR-5973 R02: CODES AND STANDARDS AND OTHER The goal of the Heavy-Section Steel Irradiation Program is to GUIDANCE CITED IN REGULATORY DOCUMENTS.
provide a thorough, quantitative assessment of effects of neu.
NICKOLAUS,J.R.; BOHLANDER,K.L. Battelle Memorial Insttute, tron irradiaton on material behavor, and in particular the frac.
Pacific Northwest Laboratory. August 1995.
525pp.
ture toughness properties, of typical pressure vessel steels as 9509130146. PNL-8462. 85429 001.
they relate to hght water reactor pressure-vessel integnty. Ef.
As part of the U.S. Nuclear Regulatory Commission (NRC) fects of specimen size, material chemistry, product form and mi.
Standard Review Plan Update and Development Program, Pa-crostructure, irradiation fluence, flux, temperature and spectrum, cific Northwest Laboratory developed a hsting of industry con-and post-irradiaton annealing are being examined on a wide sensus codes and standards and other government and indus-range of fracture properties. The HSSI Program is arranged into try guidance referred to in regulatory documents. In addition to 14 tasks: (1) program management, (2) fiscture toughness updating previous information, Revision 2 adds more than 500 (K(IC)) curve shift in high-copper welds, (3) crack arrest tough-ness (K(la)) curve shift in high-copper welds, (4) irradiation ef.
citatens. This hsting identifies the version of the code or stand-ard cited in the regulatory document, the regulatory document, facts on cladding (5) K(lc) and K(la) curve shifts in low upper.
and the latest version of the code or standard. It also provides shelf welds, (6) annealing effects in low upper shelf welds, (7) a summary charactenzation of the nature of the citation. This irradiation effects in a commercial low upper-shelf weld, (8) mi.
crostructural analysis of irradiation effects (9) in-service aged hsting war developed from electronic searches of the Code of matenal evaluatons, (10) correlation monitor matenals. (11)
Federal Regulations and the NRC's Bulletins, Information No-tees Circulars Enforcement Manual, Generic Letters, inspec-special technical assistance, (12) JPDR steel examination, (13) technical assistance for JCCCNRS Working Groups 3 and 12, tion Manual, Pohey Statements Regulatory Guides, Standard Technical Specifications, and the Standard Review Plan and (14) additional requirements for matenals. This report pro.
vides an overview of the activities within each of these tasks (NUREG-0800).
from April 1994 Through September 1994.
NUREG/CR-6002:
RISK-BASED MAINTENANCE NUREG/CR-5758 V05: FITNESS FOR DUTY IN THE NUCLEAR MODELING.Prontization Of Maintenance importances And POWER INDUSTRY, Annual Summary Of Program Performance Ouantification Of Maintenance Effectiveness. VESELY,W.E.;
Reports CY 1994. WESTRA,C.; DURBIN,N.; FIELD,1.; et af. Bat-REZOS,J.T. Science Applicatens International Corp (formerly telle Seattle Researcn Center. August 1995.83pp.9508220332.
Science Apphcatens, Inc.).
- Brookhaven National Laboratory.
PNL 10038. 85118:134.
September 1995. 90pp. 9510030191. BNL-NUREG-52332.
This report summartzes data from semaannual reports on fit-85672:266_
ness-for-duty program performance submstted to the NRC by This report describes approaches for priontizing the nsk im-utikties for two reporting periods: Jan.1 through June 30,1994, portances of maintenances using a Probabilisac Risk Assess-and Jufy 1 through Dec. 31,1994. In 1994, hcensees reported ment (PRA). Approaches are then described for quantifying the that they had conducted 163,247 teste for the presence of ille-reliabahty and nsk effects of maintenance actions. Two different gal drugs and alcohol. Of these tests, 1,372 (.84 %) were con-PRA importance measures, minimal cutset importances and risk firmed posittve. Positive test results vaned by category of test reduction importances, are used to pnontize maintenances and and category of worker. The majority of positive test results the report shows that smilar results are obtained if appropriate (977) were obtained through pre-access tenting. Of tests con-cnteria are used. The justifications for the particular importance ducted on workers having access to the protected area, 233 measures are also developed. The approaches which are devel-were positive from random testing and 122 were positive from oped for quantifying the reliability and risk effects of mainte-for<ause testing. Followup testing of workers who had previ-nance actons are extensions of the usual reliabihty models now ously tested positive recutted in 50 positive tests. For cause used in PRAs. These extended models consider degraded testing resulted in the highest percentage of positive tests; states of the component and quantify the benefits of mainte-about 16% of for-cause tests were positive. In comparison, nance in correcting degradations and preventing failures. The 1.22% of pre-access tests and.28% of random tests were posi-negative effects of maintenance, including maintenance down-tive. Positive test rates also varied by category of worker. When times, are also included. These models are specifc types of all types of tests are combined (pre-access, random, for cause, Markov models. This report analyzes a range of postulated and followup), short-term contractor personnel had the highest values of inpu' data in order to explore the potential usefulness
)
i Main Citations and Abstracts 7
of these models. The effects of maintenance are quantified to tices and policies, respectively. Findings based on these analy.
b3 large in specifc cases.
ses provided factual and conceptual support for the final phase NUXEG/CR-6009: DETECTION OF PUMP DEGRADATION.
of this project, which identified factors leadeng to human error in GREENE,R.H.; CASADA.D.A. Oak Ridge National Laboratory.
RAB. The impact of mose factors on RAB performance was August 1995.108pp. 9509130143. ORNL-6765. 85430:182.
then evaluated and priontized in terms of safety significance, This study examines the methods of detecting pump degrada.
and alternatue approaches for resolving safety significant prots ton that are employed in domestic and overseas nuclear facili-lems were identified and evaluated.
ties. This report evaluates cnteria mandated by required pump treting at U.S. nuclear plants and compares them to state-of.
NUREG/CR4143 V01: EVALUATION OF POTENTIAL SEVERE ACCIDENTS DURING LOW POWER AND SHUTDOWN OPER.
5 the-art diagnostic programs and practices implemented by other 4
major industnes. Since the working condition of the pump driver ATIONS AT GRAND GULF, UNIT
- 1. Summary Of Results.
is entical to pump operability, a review of new apphcations of WHITEHEAD,0.W. Sandia Nabonal Laboratories. July 1995.
motor diagnostics is also provided that highhghts developments 56pp. 9508230248. SAND 93-2440. 85118:215.
j in this technology. Vibraton spectral analysis is a powerful diag, This document contains a summarization of the results and nostic tool for the pump analyst. The routine collection and insights from the Level 1 accident sequence analyses of inter-analysis of spectral data is supenor to other technologies in its nally initiated events, internally initiated fire and flood events, ability to accurately detect numerous types and causes of pump seismically initiated events, and the Level 2/3 risk analysis of i
degradation. Existing ASME testing criteria do not require the intemally initiated events (excluding fire and flood) for Grand
]
evaluatien of pump vibration spectra but instead overall vibra.
Gulf Unit 1 as it operates in the Low Power and Shutdown tion amphtude. The mechanical information discernible from vi-Plant Operational State 5 during a refueling outage. The report d
bration amplitude is limited, and several pump failures in the nu.
summarizes the Level 1 information contained in Volumes 2 - 5 s
clear power industry were not detected by vibration amplitude and the Level 2/3 information contained in Volume 6 of monitoring. Since spectral snalysis provides pertinent informa.
tion concerning the mechanical condition of rotating machinery, its incorporaton into ASME testing cnteria may merit a relax-NUREG/CR4150 V01: SCDAP/RELAPS/ MOD 3.1 CODE i
ation in the monthly-to-quarterfy testing schedules that seek t MANUAL. interface Theory. ALLISON,C.M.;
BERNA,G.A.;
venfy pump operability.
CORYELL,E.W.; et al. Idaho National Engineenng Laboratory.
June 1995. 70pp. 9507180412. EGG-2720. 84716:299.
l NUREG/CR4100: GATE VALVE AND MOTOR OPERATOR RE-The SCDAP/RELAP5 code has been developed for best esti.
SEARCH FINDINGS.
STEELE,R.;
DEWALL,K.G.;
mate transient simulation of light water reactor coolant systems WATKINS,J.C.; et al. Idaho National Engineering Laboratory.
during a severe accident. The code models the coupled behav.
September 1995.
130pp. 9510060250. tNEL-94/0156.
lot of the reactor coolant system, the core, fission products re-i 85745:001, leased during a severe accident transient as well as large and This report provides an update on the valve research being small break loss-of-coolant accidents, operational transients l
sponsored by the U.S. Nuclear Regulatory Commission (NRC) such as anticipated transient without SCRAM, loss of offsite i
and conducted at the Idaho National Engineenng Laborato'Y power, loss of feedwater, and loss of flow. A generic modeling (INEL). The research addresses the need to provide assurance approach is used that permits as much of a particular system to that motor operated valves can perform their intended safety function, usually to open or close against specified (design be modeled as necessary. Control system and secondary basis) flow and pressure loads. This report desenbes several system components are included to permit modeling of plant i
controls, turbines, condensers, and secondary feedwater condi.
important developments: (a) two methods for estimating or bounding the design basis stem factor (in naing-stem valves)*
tioning systems. This volume describes the organization and manner of the interface between severe accident models which j
using data from tests less severe than design basis tests; (b) a 1
new correlaton for evaluating the opening responses of gate are resident in the SCDAP portion of the code and hydrodynam-vtives and for predict:ng opening requirements; (c) an extrapo ic models whyn are resident in the RELAP portion of the code.
lation method that uses the results of a best effort flow test to A description of the organization and structure of SCDAP/
estimate the ri sign basis closing requirements of a gate valve RELAPS is presented Additional information is provided regard-4 e
i that exhibits atypical responses (peak force occurs before flow ing the manner in which models in one portion of the code
?
isolation); and (d) the extension of the original INEL closing cor-impact other parts of the code, and models which are depend-ent on and derive information from other subcodes.
J relation to include low-flow and low-pressure loads. The report s.lso includes a general approach, presented in step-by step 1
j format, for determining operaSng margins for rising stem valves NUREG/CR-6160 V02: SCDAP/RELAP/ MOD 3.1 CODE 1
(gate valves and globe valws) as well as quarter turn valves MANUAL. Damage Progression Model Theory. ALLISON,C.M.;
1 (ball valves and butterfly valves).
BERNA.G.A.; CHENG,T.C.; et at Idaho National Engineering Laboratory. June 1995, 190pp. 9507180418. EGG-2720.
NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF 84713:172.
REMOTE AFTERLOADING BRACHYTHERAPY. Supporting The SCDAP/RELAPS code has been developed for best esti.
Analyses Of Human-System Interfaces, Procedures And mate transient simulation of light water reactor coolant systems Practices. Training And Organizational Practices And Proce-dunng a severe accident. The code models the coupled behav-dures. CALLAN,J R.; KELLY,R.T.; OUINN.M.L.; et al. Pacific Sci.
ior of the reactor coolant system, the core, fission products re-ence & Engineenng Group, Inc. July 1995.226pp.9508090067.
leased during a severe accident transient as well as large and 84965:001.
small break loss-of-coolant accidents, operational transients A human factors project on the use of nuclear by-product ma-such as anticipated transient without SCRAM, loss of offsite terial to treat cancer using remotely operated afterloaders was power, loss of feedwater, and loss of flow A generic modeling undertakr'n by the Nuclear Regulatory Commission. The pur-approach is used that permits as much of a particular system to pose of the project was to identify factors that contribute to be modeled as necessary. Control system and secondary human error in the system for remote afterloading brachyther-system components are included to permit moddng of plant apy (RAB). This report documents the findings from the second, controls, turbines, condensers, and secondary feedwater condi-therd, fourth, and fifth phases of the project, which involved de-tioning systems. This volume contains detailed descriptions of tiiled analyses of four major aspects of the RAB system linked the severe accident models and correlatons. It provides the to human error: human-system interfaces; procedures and prac-user wrth the underlying assumptions and simplifications used to tres; trairung practices and policies; and organizational prac-generate and implement the basic equations into the code, so l
d 4
0
i 8
Main Citations and Abstracts an intelligent assessment of the applicability and accuracy of study, which accounted for both axial and radial nodalization of the resulting calculation can be made.
the core, are also reported.
NUREG/CR-6150 V03: SCDAP/RELAPS/ MOD 3.1 CODE NUREG/CR 6159: USING MICRO SAINT TO PREDICT PER.
MANUALUser's Guide And input Manual. ALLISON,C.M.;
FORMANCE IN A NUCLEAR POWER PLANT CONTROL BERNA,G.A.; CORYELL.E.W.; et al. Idaho National Engineenng ROOM.A Test Of Validity And Feasibility. LAWLESS,M.T.;
Laboratory. June 1995. 352pp. 9507180429. EGG-2720.
LAUGHERY,K.R.
Micro Analysis
- Design, Inc.
84715:311.
PERSENSKY,J.J. Control, Instrumentation & Human Factors The SCDAP/RELAPS code has been developed for best esti-Branch (Post 941217). September 1995. 30pp. 9510030209.
mate transient simulation of light-water-reactor coolant systems 85663.255.
during a severe accident. The code models the coupled behav*
1he United States Nuclear Regulatory Commission (NRC) re-sor of the reactor coolant system, core, fission products re-quires a technical basis for regulatory actions. In the area of leased dun.ng a severe accident transient as well as large and human factors, one possible technical basis is human perform-small break loss-of-coolant accidents, operational transients ance modeling technology including task network modeling.
such as anticipated transient without SCRAM, loss of offsite This study assessed the feasibility and validity of task network power, loss of feedwater, and loss of flow. A generic modeling modeling to predict the performance of control room crews.
approach is used that permits as much of a particular system to Task network models were built that matched the expenmental be modeled as necessary. Control system and secondary conditions of a study on computerized procedures that was con-system components are included to permit modeling of pla r ducted at North Carolina State University. The data from the controls, turbines, condensers, and secondary feedwater conds
" paper procedures" conditions were used to calibrate the task tioning systems. This volume, Volume 3, provides guidelines to network models. Then, the models were manipulated to reflect code users based upon lessons learned during the developmen-expected changes when computerized procedures were used.
tal assessment process. A desenption of problem control and These models' predictions were then compared to the experi-the enstallation process is included. Appendix A contains the de-mental data from the "computenzed conditions" of the North senption of the input requirements.
Carolina State Un!versity study. Analyses indicated that the NUREG/CR-6150 V04: SCDAP/RELAPS/ MOD 3.1 CODE models predicted some subsets of the data well, but not all. Im-MANUAL.MATPRO--A Library Of Matenals Properties For Light-plications for the use of task network modeling are discussed.
Water. Reactor Accident Analysis. ALLISON,C.M.; BERNA.G.A.;
NUREG/CR-6184: SEPARATE EFFECTS TESTING AND ANALY-CHAMBERS,R.; et al. Idaho National Engineenng Laboratory.
SES TO INVESTIGATE LINER TEARING OF THE 1:16-SCALE June 1995. 674pp. 9507180441. EGG 2720. 84714:001.
REINFORCED CONCRETE CONTAINMENT BUILDING.
The SCDAP/RELAP5 code has been developed for best esti.
SPLETZER,8 L.; LAMBERT L.D.; BERGMAN,V.L; et al. Sandia mate transient simulation of light. water-reactor coolant systems National Laboratones. May 1995. 250pp. 9507200213.
dunng a severe accident. The code models the coupled behav.
SAND 921720. 84749-001.
ior of the reactor coolant system, core, fission products re-leased during a severe accident transient as well as large and The overpressurizabon of a 1:6-scale reinforced concrete containment buildsng demonstrated that liner tearing is a plausi-small break loss-of-coolant accidents, operational transients ble failure mode in such structures under severe accident condi-such as anticipated transient without SCRAM, loss of offsite tions. A combined expenmental and analytical program was de-power, loss of feedwater, and loss of flow. A genenc modeling veloped to determine the important parameters that affect liner approach is used that permits as much of a particular system to teanng and to develop reasonably simple analytical methods for be modeled as necessary. Control system and secondary system components are included to permit modeling of plant predicting when teanng will occur. Three sets of test specimens controls, turbines, condensers, an(.i secondary feedwater condi-were designed to allow individual control over and investigation tK)ning systems. This volume, Volume 4, descnbes the matenal of the mechanisms believed to be important in causing failure of properties correlations and computer subroutines (MATPRO) the liner plate. The series of tests investigated the effect on used by SCDAP/RELAPS. Formulation of the materials proper-liner teanng produced by the anchorage system, the loading conditions, and the transition in thickness from the liner to the ties are generally semi-empiricalin nature. A wide vanety of ma.
tenal property subroutines are contained in this document. This insert plate. Before testira, the specimens were analyzed using two-and three-dimensional finite element models. Based on the document also contains desenptions of the reaction and solu-tion rate models needed to analyze a reactor accident.
analysis, the failure mode and corresponding load conditions were predicted for each specimen. Test data and post-test ex-NUREG/CR-6150 V05: SCDAP/RELAPS/ MOD 3.1 CODE amenation of test specimens show mixed agreement with the MANUAL. Developmental Assessment.
ALLISON,C.M.;
analytical predictions with regard to failure mode and specimen BERNA.G.A : BOURDON,S.M.; et al. Idaho National Engineering response for most tests. Many similanties were also observed Laboratory. June 1995. 349pp. 9507180448 EGG-2720.
between the response of the liner in the 1:6-scale reinforced 84717:001.
concrete containment model and the response of the test The SCDAP/RELAPS code has been developed for best estF specimens. This work illustrates the fact that the failure mecha-mate transient simulation of light water reactor coolant systems nism of a reinforced concrete containment building can be during a severe accident. The code models the coupled behav-greatly influenced by details of liner and anchorage system ior of the reactor coolant system, the core, fission product re-design. Further, it significantly increases the understanding of leased during a severe accident transient as well as large and containment building response under severe conditions.
small break loss of coolant accidents, operational ;ransients such as anticipated transient without SCRAM, loss of offsite NUREG/CR-6188 V02: MICROBIAL DEGRADATION OF LOW-power, loss of feedwater, and loss of flow. A generic modeling LEVEL RADIOACTIVE WASTE. Annual Report For FY 1994.
approach is used that permits as much of a particular system to ROGERS,R.D.; HAMILTON M.A.; VEEH,R.H.; et al. Idaho Na-be modeled as necessary. Control system and secondary tional Engineering Laboratory. August 1995.66pp.9509130162.
system components are included to permit modeling of plant INEL 95/0153. 85430:287.
controls, turbines, condensers, and secondary feedwater condi.
The Nuclear Regulatory Commission stipulates in 10 CFR 61 tioning systems. This volume contains detailed code-to data cal-that disposed low-level radioactive waste (LLW) be stabilized.
culations performed using SCDAP/RELAPS/ MOD 3.1, as well as To provide guidance to disposal vendors and nuclear station comparison calculations performed with earlier code versions.
waste generators for implementing those requirements, the The results of full plant calculations which include Surry, TMI-2, NRC developed Technical Position on Waste Form, Revision 1, and Browns Ferry are described. The results of a nodalization That document details a specified set of reco6.6,66ded testing l
_ ~ - _ - - - -
1 i
Main Citations and Abstracts 9
j procedures and enteria, including several tests for determining NUREG/CR-6265: MULTIDISCIPLINARY FRAMEWORK FOR the biodegradation properties of waste forms. Cement has been HUMAN RELIABILITY ANALYSIS WITH AN APPLICATION TO widely used to solidify LLW; however, the resulting waste forms ERRORS OF COMMIS? TON AND DEPENDENCIES.
are sometimes susceptible to failure due to the actions of waste BARRIERE,M.T, Brookhaven*
National Laboratory.
constituents, stress, and environment. The purpose of this re.
WREATHALL.J. John Wreathall & Co., Inc. COOPER,S.E.; et al.
search program is to develop modified microbial degradation Science Apphcations International Corp. (formerfy Science Ap-l test procedures that will be more appropriate than the existing plications, Inc.). August 1995. 289pp. 9509200039. BNL.
NUREG-52431,85539:094.
procedures for evaluating the effects of microbiologically influ-enced chemical attack on coment-solidified LLW. Groups of Sirce the early 1970s, human reliability analysis (HRA) has microorganisms indigenous to LLW disposal sites are being em-been considered to be an integral part of probabilistic risk as-sessments (PRAs). Nuclear power plant (NPP) events, from ployed that can metabolically convert organic and inorganic Three Mile Islard through the mid 196;s, showed the impor-substrates into organic and mineral acids. Such acids aggres-tance of human performance to NPP risk. Recent events dem-sively react with cement and can ultimately lead to structural ons a nan pe ance conUnues b b a MnaM 5
failure. Results over the past year on the application of mecha-source of risk, in light of these observations, the current limita-l a
naams inherent in microbially influenced degradation of cement-tions of existing HRA approaches become apparent when the 4
based material are the focus of this annual report. Data-validat-role of humans is examined explicrtly in the context of real NPP ed evidence of the potential for microbially influenced deteriora-events. The development of new or improved HRA methodolo-l 1
tion of cement-solidified LLW and subsequent release of radion-gies to more realistecally rcpresent human performance is rec-1
' uclides has been developed during this study.
ognized by the Nuclear Regulatory Commission (NRC) as a necessary means to increase the utility of PRAs. To accomplish j
NUREG/CR 6261: A
SUMMARY
OF ORNL FISSION PRODUCT this objective, an Improved HRA Project, sponsored by the i
RELEASE TESTS WITH RECOMMENDED RELEASE RATES NRC's Office of Nuclear Regulatory Research (RES), was initi-4 AND DIFFUSION COEFFICIENTS.
LORENZ,R.A/
ated in late February,1992, at Brookhaven National Laboratory OSBORNE,M.F, Oak Ridge National Laboratory July 1995.
(BNL) to develop an irnproved method for HRA that more realis-4 l
83pp.9509070074. ORNL/TM-12801. 85401:146.
tically assesses the human contnbution to plant risk and can be Fission product release data from the ORNL HI test series fully integrated with PRA. This report describes the research ef-4 and Vi test series are summanzed in this report and compared forts includsng the development of a multidisciplinary HRA l
with releaso results from similar testa performed in France (the framework, the characterization and representation of errors of HEVA test series). The ORNL test results are also compared commission, and an approach for addressing human dependen-4 with four in-reactor tests, the SNL ST 1 and ST 2 tests, and the cies. The implications of the research and necessary require-4 INEL SFD 13 and SFD 14 bundio tests. Test atmospheres monts for further development also are discussed.
l range from steam to hydrogen, and the temperature range is NUREG/CR-6277 V01: HUMAN FACTORS EVALUATION OF 1675 to 2700 K.
TELETHERAPY. Identification Of Problems And Alternative Ap-NUREQ/CR-6263 V01: HIGH INTEGRITY SOFTWARE FOR NU.
fra
, ir"c 9jpp9 8'O 66 099 09 CLEAR POWER PLANTS Candidate Guidehnes, Technical Basis A series of human factors evaluations were undertaken to And Research Needs Executive Summary. SETH,S.; BAIL,W.;
better understand the contnbuting factors to human error in the 3
1 CLEAVES,0.; et al. MITRE Corp. June 1995. 86pp.
teletherapy environment. Teletherapy is a multidisciplinary meth-l 9508020314. MTR 94W0000114. 84908.262.
odology for treating cancerous tissue through selective expo-l The work documented in this report was performed in support sure to an external beam of ionizing radiation. A team of human of the U.S. Nuclear Regulatory Commission to examine the factors specialists, assisted by a panel of radiation oncologists, 1
I technical basis for candidate guidelines that could be consid-medical physicists, and radiation therapists, conducted site visits i
ered in reviewing and evaluating high integnty computer soft-to radiation oncology departments at community hospitals, uni-j ware used in the safety systems of nuclear power plants. The versity centers, and free-standing clinics. A function and task framework for the work consisted of the following software de-analysis was initially performed to guide subsequent evaluations velopment and assurance actmties: requirements specification; in the areas of system-user interfaces, procedures, training and 4
j~
design; coding; verification and validation, including static analy.
qualifications, and organizational pohcies and practices. The sis and dynamic testing; safety analysis; operation and mainte-present work focuses solely on training and qualifications of j
nance; configuration management; quality assurance; and plan.
personnel (e g., training received before and during employ.
ning and management. Each activity (framework element) was ment), and the potential impact of organizational factors on the I
subdivided into technical areas (framework subelements). The performance of teletherapy. Organizational factors include such l
report desenbes the development of approximately 200 candi-topics as adequacy of staffing, performance evaluations, com.
date guidelines that span the entire range of software hfe-cycle monly occurring errors, implementation of quality assurance pro-actmties; the assessment of the technical basis for those candi-grams, and organizational climate.
j date guidelines; and the identification, categonzation and prionti-NUREG/CR 6277 V02: HUMAN FACTORS EVALUATION OF zation of research needs for improving the technical basis. The TELETHERAPY. Function And Task Analysis. KAYE,R.D.;
report has two volumes: Volume 1, Executive Summary, in-HENRIKSEN,K.; JONES,R.; et al. Hughes Training, Inc. July
)
cludes an overview of the framework and of each framework 1995. 250pp. 9508020293. 84910.067.
I element, the complete set of candidate guidelines, the results of See NUREG/CR.6277,V01 abstract.
the assessment of the technical basis for each candidate guide-NUREG/CR 6277 V03: HUMAN FACTORS EVALUATION OF hne, and a discussion of research needs that support the regu-latory function; Volume 2 ls the main report.
TELETHERAPY. Human-System Interfaces And Procedures.
a KAYE,R.D.; HENRIKSEN,K.; JONES,R.; et al. Hughes Training, i
NUREG/CR-6263 V02: HIGH INTEGRITY SOFTWARE FOR NU.
Inc. July 1995. 70pp. 9508020295. 84915:001.
I CLEAR POWER PLANTS Candidate Guidelines, Technical Basis See NUREG/CR-6277,V01 abstract.
And Research Needs. Main Report. SETH,S.; BAIL,W.;
NUREG/CR 6277 V04: HUMAN FACTORS EVALUATION OF CLEAVES,0.; et al. MITRE Corp. June 1995. 430pp.
TELETHERAPY. Training And Organizational Analysis.
9508020315. MTR 940000114. 84909.001.
HENRIKSEN,K.; KAYE.R.D.; JONES R.; et al. Hughes Training, 4
See NUREG/CR.6263,V01 abstract.
Inc. July 1995. 71pp. 9508020296. 64008:191.
4 w
i
E 10 Main Citations and Abstracts See NUREG/CR-6277,V01 abstract.
NUREG/CR-6313 V02: ROBUST, ACCURATE, AND NON-CON-TACTING VIBRATION MEASUREMENT NUREG/CR4277 V06: HUMAN FACTORS EVALUATION OF SYSTEMS Supplemental Appendices Presenting Companson TELETHERAPY. Literature Review. HENRIKSEN,K.; KAYE,R.D.;
Measurements Of The Robust Laser interferometer And Typical JONES,R.; et al Hughes Training, Inc. July 1995. 113pp.
Accelerometer Systems. GOODENOW,T.C.; SHIPMAN,R.L.;
I 9508020306. 84915.071, HOLLAND.H M. Epoch Engineering, Inc. June 1995, 200pp.
See NUREG/CR4277,V01 abstract.
9507200236. 84750:092.
See NUREG/CR-6313,V01 abstract.
NUREG/CR-6305: BLT-EC (BREACH, LEACH, TRANSPORT, AND EQUIL!BRIUM CHEMISTRY), A FINITE-ELEMENT MODEL NUREG/CR-6323: RELATIVE RISK ANALYSIS IN REGULATING THE USE OF RADIATION. EMITTING MEDICAL DEVICES.A FOR ASSESSING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE DISPOSAL UNITS. Background, Theory, Preliminary Applicaten.
JONES,E.D.;
BANKS,W.W.;
ALTENBACH,T.J.; et al. Lawrence Livermore National Laborato-And Model - Description. MACKINNON.R.J.; SULLIVAN,T.M p ember 1995.181pp. 9510060245. UCRL-ID-120051.
Brookhaven National Laboratory. SIMONSON,S.A.; et al. Mas-3 sachusetts Institute of Technology, Cambridge, MA. August This report describes a preliminary application of an analysis 1995.155pp.9509200030. BNL-NUREG-52446. 85540:001, approach for assessing relative risks in the use of radiation.
Periormance assessment models typically account for sorp-emitting medical devices. Results are presented on human-initi-ton and dissolution-precipitaten by using an empirical distribu-ated actions and failure modes that are most likely to occur in ton coefficient (K(d)) that combines the effects of all chemical the use of the Gamma Knife, a gamma irradiation therapy reactons between solid and aqueous phases. There is an in-device. This effort represents an initial step in a U.S. Nuclear creasing awareness that performance assessments based Regulatory Commission (NRC) plan to evaluate the potential solely on empirically based K(d) models may be incomplete, role of risk analysis in regulating the use of nuclear medical de-particularly for applications involving radionuclides having sorp-vices. For this preliminary application of risk assessment, the aion and solubility properties that are sensitive to variations in focus was to develop a basic process using existing techniques the in situ chemical environment. To accommodate such vari-for identifying the most likely risk contributors and their relative atons and to assess impact on radionuclide mobihty, one must importance. The approach taken developed relative risk rank-model radionuchde release, transport, and chemical processes ings and profiles that incorporated the type and quality of data in a coupled fashion. This modehng was incorporated into the available and could present results in an easily understood two-dimensional, finite-element, computer code BLT-EC which form. This work was performed by the Lawrence Livermore Na-can predict container degradation, waste-form leaching, and ad.
tional Laboratory for the NRC.
vective-dispersive, multispecies, solute transport. BLT-EC ac-NUREG/CR-6324: OUALITY ASSURANCE FOR GAMMA counts for retardation directly by modeling the chemical proc-KNIVES. JONES.E.D.; BANKS.W.W.; FISCHER,L.E. Lawrence esses of complexation, sorpton, dnsolution-precipitation, ion-Livermore National Laboratory. September 1995. 146pp.
exchange, and oxidaton-reduction reactions. Heroin we: (1) de-9510060248. UCAL-lD-120056. 85745:121.
scribe in detail physical and chemical processes that control the This report describes and summanzes the resuMs of a quakty release and migration of radionuclides from shallow land LLW assurance (OA) study of the Gamma Knife, a nuclear medical disposal facilities; (2) formulate the mathematical models that device used for the gamma irradiation of intracranial lesions.
represent these processes; (3) outline how these models are in-The study's focus was on the physical aspects of QA and did corporated and implemented in BLT-EC; and (4) demonstrate not address issues that are essentially medical, such as patient application of BLT-EC on sample problems.
selection or presenption of dose. A nsk. based OA assessment approach was used. In this report, sample programs for quality NUREG/CR-6313 V01: ROBUST, ACCURATE, AND NON. CON-control and assuance are included. The use of the Gamma TACTING VIBRATION MEASUREMENT SYSTEM. Summary of Knife was found to conform to existing standards and guidehnes Comparison Measurements Of The Robust Laser interferometer concerning radiation safety and quakty control of external beam And Typical Accelerometer Systems. GOODENOW,T.C.;
therapies (shielding, safety reviews, radiation surveys, interlock SHIPMAN,R.L; HOLLAND,H.M. Epoch Engineering, Inc. June systems, exposure monitoring, good medical physics practices, 1995. 74pp. 9507200222. 84749:285.
etc.) and to be compliant with NRC teletherapy regulations.
Epoch Engineering, incorporated (EEI) has completed a There are, however, current practices for the Gamma Knife not series of vibration measurements comparing their newty-devel-covered by existing, formalized regulations, standards, or guide-oped Robust Laser Interferometer (RLI) with accelerometer in-lines. These practices have been adopted by Gamma Knife strumentaten systems. eel has successfully demonstrated, on users and continue to be developed with further experance.
several pieces of commonplace machinery, that non-contact, Some of these have appeared in publications or preser.tations line-of-sight measurements are practical and yield results equal and are slowly finding their way into recommendations of pro-to or, in some cases, better than customary field implementa.
fessional organizations.
tions of accelerometers. The demonstration included analysis NUREG/CR-6325: AN IMPLICIT STEACY-STATE INITIAll2ATION and comparison of such phenomena as nonh.neanty, transverse PACKAGE FOR THE RELAPS COMPUTER CODE.
sensitivity, harmonics, and signal-to-noise rato. Fast Fourier PAULSEN,M.P.; PETERSON.C.E. Computer Simulaton & Analy-Transformatons were performed on the accelerometer and the sis, Inc. August 1995.142pp. 9509130168. 85433:001.
laser system outputs to provide a comparison basis. The RLl A direct steady-state initialization (DSSI) method has been was demonstrated, within the limits of the task, to be a viable, developed and implemented in the RELAPS hydrodynamic anal-line-of-sight, non-contract attematwe to accelerometer systems.
ysis program. It provides a means for users to specify a small Several different kinds' of machinery were instrumented and set of initial conditions which are then propagated through the compared, including a small pump, a gear-driven cement mixer.
remainder of the system. The DSSI scheme utilizes the steady-a rotor idt, and two small fans. Known machinery vibration state form of the RELAPS balance equations for nonequilibrium sources were verified and RLI system output file formats were two. phase flow, it also employs the RELAPS component models vonfied to be compatible with commercial computer programs and constitutue model packages for wall-to-phase and inter-used for vibration mm Aug and trend analysis. The RLI was phase momentum and heat exchange. A fully implicit solution of also observed to be less subject to clWJomagnetic interference the lineanzed hydrodynamic equations is implemented. An im-(EMI) and more capable at very low frequencies.
plicit coupling scheme is used to augment the standard steady-
Main Citations and Abstracts 11 state heat conduction solution for steam generator use. It sentative of the air inhaled by radiation workers. A new sensor solves the pnmary-side tube region eriergy equations, heat con-was developed in this project and successfully tested in the duction equations, wall heat flux boundary conditions, and over-AMS laboratory for measurement of low flow rates of air. The til energy balance equations as a coupled system of equations sensor uses a conventional thermocouple as its sensing ele-cnd improves convergence. The DSSI methods for initializing raent and is therefore referred to as a " thermocouple flow RELAP5 problems to steady-state conditions has been com-sensor", The dynamic response of the thermocouple is meas-pared with the transient solution scheme using a suite of test ured using an in-situ response time testing method. The re-problems including; adiabatic single-phase liquid and vapor flow sponse time information is then converted to a flow signal using through channels with and without heating and area changes; a predetermined response time-versus-flow correlation for the heated two-phase test bundle representative cf BWR core con-thermocouple. The thermocouple flow sensor has the potential ditions; and a single-loop PWR model.
to aid in determining in-door air flow pattems. This may be ac-NUREG/CR-6328: ADEOUACY OF THE 123-GROUP CROSS-complished by using multiple thermocouples to measure air flow SECTION LIBRARY FOR CRITICALITY ANALYSES OF velocities in several locations in the room and use the velocity WATER-MODERATED URANIUM SYSTEMS. PARKS.C.V.;
information with computational fluid dynamics or neural network 4
WRIGHT.R.O.; JORDAN,W.C. Oak Ridge National Laboratory.
models to establish air flow pattems.
August 1995.29pp.9508300310. ORNL/TM-12970. 85287:291.
In a recent criticality analysis for an array of water-moderated NUREG/CR-6335: FATIGUE STRAIN-LIFE BEHAVIOR OF packages containing high-ennched uranium, the 123-group CARBON AND LOW-ALLOY STEELS, AUSTENITIC STAIN-cross-sectinn library in the SCALE system was observed to LESS STEELS, AND ALLOY 600 IN LWR ENVIRONMENTS.
have a nonconservative discrepancy of approximately 3 to 3.5V.
KEISLER,J.; CHOPRA,0.K.; SHACK,W.J. Argonne National Lab-when compared to more recently developed libraries. A simple oratory. August 1995. 82pp. 9508300329. ANL-95/15.
representative system of UO(2)F(2)
- H(2)O was used to identi-85288:221.
fy that the problem results from a lack of resonance data for The existing fatigue strain vs. life (S-N) data, foreign and do-(235)U. Only a single set of self-shielded cross sections, most mestic, for carbon and low-alloy steels, austenitic stainless likely corresponding to a water-moderated infinite dilute system, steels, and Alloy 600 used in the construction of nuclear power 4
was provided with the onginal data. The UO(2)F(2).H(2)O plant components have been compiled and categorized accord-study indicates that this limitation may cause nonconservatrve ing to material, loading, and environmental conditions. Statistical discrepancies as high as 5.5% for some water-moderated high-models have been developed for estimating the effects of the onnched uranium systems. Charactenstics of the systems where gg the discrepancy is evident are identified and discussed.
The results of a rigorous statistical analysis have been used to NUREG/CR-6333: BREATH VERSION 1.1 - COUPLED FLOW estimate the probability of initiating a fatigue crack. Data in the AND ENERGY TRANSPORT IN POROUS MEDIA. Simulator De-literature were reviewed to evaluate the effects of size, geome-senpton And User Guide. STOTHOFF,S.A. Southwest Research try, and surface finish of a component on its fatigue life. The Institute. July 1995. 93pp. 9509200049. CNWRA94-020.
fatigue S-N curves for components have been determined by 85539.001.
adjusting the probability distribution curves for smooth test j
i This document desenbes the BREATH computer code, in-specimens for the effect of mean stress and applying design ciuding the mathematical and numerical formulation for the sim-margins to account for the uncertainties due to component g
ulator, usage desenption, and sample input files with corre-size / geometry and surface finish. The significance of the effect sponding output filos. The BREATH computer code is designed of environment on the current Code design curve and on the 4
to simulate one-dimensional flow of a liquid phase and disper-roposed interim design curves published in NUREG/CR-5999 sive transport of the corresponding vapor species, coupled with P'
9 energy transfer, in a heterogeneous porous medium. The BREATH code is organized into a flow equation simulator and sample components from BWRs and PWRs are presented.
an energy equation simulator, which can be coupled or used in-NUREG/CR-6347: MULTI-PHASE REACTIVE TRANSPORT dependently. Both simulators use linear finite element basis THEORY. LICHTNER,P.C-Southwest Research institute' i
functions. A modified Picard iteration scheme is used to solve the nonlinear sets of equations. Heunstic algonthms are avail.
LICHTNER,P.C. Center for Nuclear Waste Regulatory Analyses.
I able to control time stepping and the active solution domain.
July 1995.102pp. 9508090044. CNWRA94-018. 84963:087.
The BREATH simulator has been developed for use in auxiliary Physicochemical processes in the near-field region of a high-analyses which are a part of the Nuclear Regulatory Commis-level waste repository may involve a diverse set of phenomena sion Iterative Performance Assessment program. The simulator including flow of liquid and gas, gaseous diffusion, and chemical was developed in response to the observation from Total reaction of the host rock with aqueous solutions at elevated System Performance Assessments by both the Nuclear Regula-temperatures. This report develops some of the formalism for tory Commission and the U.S. Department of Energy that total-desenbing simultaneous multicomponent solute and heat trans-system performance at the Yucca Mountain site in Nevada is port in a two-phase system for partially saturated porous media.
highly sensitive to the infiltration rate. Accordingly, this first ver.
Diffusion of gaseous species is described using the Dusty Gas sion of the code is primarily intended to simulate processes im-Model which provides for simultaneous Knudsen and Fickian portant to infiltration and evaporation in climatic and hydrologic diffusion in addition to Darcy flow. A new form of the Dusty Gas near-surfa'e environments representative of the Yucca Moun-Model equations is denved for binary diffusion which separates tain site, the total diffusive flux into segregative and nonsegregative com-NUREG/CR-6334: NEW SENSOR FOR MEASUREMENT OF ponents. Migration of a wetting front is analyzed using the 1
LOW AIR FLOW VELOCITY. Phase l Final Report, quasi-stationary state approximation to the Richards' equation.
HASHEMIAN,H.M.; HASHEMIAN,M.; RIGGSBEE.E.T. Analysis &
Heat-pipe phenomena are investigated for both gravity-and Measurement Services Corp. August 1995.145pp.9508230253.
capillary-driven reflux of liquid water. An expression for the 85120:001.
burnout permeebility is denved for a gravity-driven heat-pipe. Fi-This is the report of a six-month feasibility study of a new nally an estimate is given for the change in porosity and perme-sensor to measure ambient air flow velocity and direction for ability due to mineral dissolution which could occur in the region j
health physses applications in nuclear facilities. The information of condensate formation in a heat-pipe.
j from this sensor is to be used to determina where to place air samplers to sample airborno radioactive material that is repre-
12 Main Citations and Abstracts NUREG/CR 6351: REVIEW OF SCENARIO SELECTION AP-not exceeded. Electronic personal dosimeters EPDs, are widely PROACHES FOR PERFORMANCE ASSESSMENT OF HIGH-used for this application. As their rehabihty has improved users LEVEL WASTE REPOSITORIES AND RELATED ISSUER have shown an interesi in their use for both incremental control BONANO,E.J. Southwest Research Institute. BACA.R.G. Beta and as the pnmary dosimeter to track the dose of record for the Corp, International. August 1995. 78pp. 9509070092. CNWRA worker. In this application they would replace the traditional film 94 002. 8540t:230.
or thermoluminescent dosameter whose performance is thor.
The selection of scenanos representing plausible reahzations oughly understood. The EPD bnngs with it some of the prob-of the future conditions-with associated probabilities of occur.
lems of instruments which are not seen with the traditional dosi-rence-that can affect the long-term performance of a high level meters. The report contains results of a survey of users and a radioactive waste (HLW) repository is the commonly used survey of vendor hterature that highhght some of the hmatations method for treating the uncertainty in the prediction of the future and problems of EPDs. The radiation protection community is states of the system. This method, conventionally referred to as concerned that the rehabikty and accuracy of the data from the the "scenano approach," while common is not the only method EPD be comparable to traditional methods if they assume this to deal with this uncertainty; other methods, such as the envi-additional role. The report lists type tests, test methods and ronmental simulation approach (ESA), have also been pro-cakbration methods intended to ensure the required reliabihty.
posed. Two of the difficulties with the scentino approach ar!
NUREG/CR-6356: HYDRAULIC CHARACTERIZATION OF HY-the lack of uniqueness in the definition of the term 'scenano GREEN.R.d T-DROTHERMALLY ALTERED NOPAL TUFF.
and the lack of uniqueness in the approach to formulate scenar-RICE MEYER-JAMES,K.A Southwest Research Institute.
ios, which rekes considerably on subjective judgments. Conse-George Rice & Associates. July 1995. 69pp. 9509150281.
quently, it is difficult to assure that a complete and unique set of CNWHA 94-027. 85521:001 scenanos can be defined for use in a performance assessment.
Understanding the mechanics of vanably saturated flow in Because scenarios are key to the determination of the long-e 6 mle term performance of the repository system, this lack of unique-e d N NW $bd &
9 ness can present a considerable challenge when attempting to active waste repository for the Yucca Mountain site. Developing reconcile the set of scenanos, and their level of detail, obtained that understanding must be founded on the analysis and inter-using different approaches, particularfy among pioponents and pretation of laboratory and field data. This report presents an regulators of a HLW repository.
analysis of the unsaturated hydraukc properties of tuff cores NUREG/CR-6354 DRF FC: PERFORMANCE TESTING OF ELEC-from the Pena Blanca natural analog site in Mexico. The basic TRONIC PERSONAL DOSIMETERS. Draft Report For Comment.
intent of the analysis was to examine possible trends and rela-SWINTH.K.L; MCDONALD.J.C.; SiSK,D R.; et al. Battelle Me-tionships between the hydrauhc properties and the degree of monal Institute, Pacific Northwest Laboratory August 1995.
hydrothermal alteration exhibited by the tuff samples. These 172pp. 9508230227. PNL 10560. 85127:119.
data were used in flow simulations to evaluate the significance in radiation protection, incremental control of worker radiation of a particular conceptual (composite) model and of distinct hy-exposures is important to ensure that penodic dose hmits are draulic properties on the rate and nature of water flow.
)
l
]
1 f
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-roferenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.
1 1
SECONDARY REPORT NUMBER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER l
ANL 95/15 NUREG/CR-6335 INEL-94/0111 NUREG/CP-0144 V02 ANL-95/25 NUREG/CA-4667 V19 yj Q V02 BIENNIAL NUREG-1363 V06 INEL 95/0174 NUREG/CR-5535 V01 BNL NUREG-51561 NUREG/CR-2907 V13 INEL 95/0174 NUREG/CR-5535 V02 BNL NUREG 52332 NUGEG/CR 6002 INEL 95/0174 NUREG/CR 5535 V04 i
BNL-NUREG-52431 NUREG/CR4265 INEL-95/0174 NUREG/CA-5535 V05 R1 BNL-NUREG-52446 NUREG/CR-6305 MIR 940000114 NUREG/CR-6263 V02 y[H4 (MQ'y $
BSAC 700/95/005 NUREG/CR-5758 V05 CNWRA 94402 NUREG/CR-6351 ORNL 6765 NUREG/CR-6089 CNWRA 94427 NUREG/CR-6356 ORNL/TM-11568 NUREG/CR 5591 V05 N2 CNWRA94418 NUREG/CR-6347 OANL/TM 12801 NUREG/CA-6261 CNWRA94 020 NUREG/CR-6333 OF.NL/TM 12970 NUREG/CR4328 EGG-2720 NUREG/CR 6150 V01 PNL 10560 NUREG/CR 6354 DRF FC EGG 2720 NUREG/CR4150 V02
$8 hhhM$
EGG 2720 NUREG/CR-6150 V03 SAND 92-1720 NUREG/CR-6184 EGG-2720 NUREG/CR-6150 V04 SAW '93-2440 NUREG/CR4143 V01 EGG-2720 NUREG/CR4150 VOS UCAL ID 120051 NUREG/CR-6323 INEL 94/0111 NUREG/CP 0144 V01 UCRL-lO-120056 NUREG/CR-6324 4
i i
j i
i I
~
l i
i 13
4 4
e.
_,,.m,,
,_y,,
)
I J
k 1
4 t
1 l
i I
l i
l I
i i
I f
I 1
l l
l i
l l
I Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by the author. If further information is needed, refer to the main cita-tion by the NUREG number.
+
1 t
ABELOUIST,E.W.
NUREG/CA-6150 V05:
SCDAP/RELAP5/ MOD 3.1 CODE NUREG-1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS MANUALDevelopmental Assessment.
WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS CONTAMINANTS AND FIELD CONDITIONS Draft Report For Com-BLEY,D.C.
ment.
NUREG/CR-6265. MULTIDISCIPLINARY FRAMEWORK FOR HUMAN RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF I
CR 6150 VOI:
SCDAP/RELAP5/ MOD 3i CODE MANUAL Interface Theory.
BLOCK,R C
^
NUREG/CP-0142 V01: PROCEEDINGS OF THE 7TH INTERNATIONAL am ge Pr73: saion odelT MANUAL V
SCDAP/R 5/ MOD 31 CODE MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS NUREG/CR4150 MANUAL User's Guido And input Manual.
(NURETH-7). Sessions 15.
NUREG/CR-6150 V04:
SCDAP/RELAP5/ MOD 31 CODE NUREG/CP-0142 V02: PROCEEDINGS OF THE 7TH INTERNATIONAL
- MANUAL.MATPRO-A Library Of Matenals Properties For Light-Water.
MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS Reactor Accident Analysis.
(NURETH-7). Sessions 611.
i NUREG/CR4150 VOS SCDAP/RELAP5/ MOD 3.1 CODE NUREG/CP 0142 V03 PROCEEDINGS OF THE 7TH INTERNATIONAL i
MANUALDevelopmental Assessment MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS i
(NURETH-7). Sessions 1216.
NUREG/CF
- 23. RELATIVE RISK ANALYSIS IN REGULATING THE MEETING ON NUCLEAR REACTOR THERMAL. HYDRAULICS USE OF RADIATION EMITTING MEDICAL DEVICES.A Preliminary Ap-Em4 Sessions m2(
plicatiort BOHLANDER,K.L.
ASHAR,H.
1 NUREG-1522: ASSESSMENT OF INSERVICE CONDITIONS OF NUREG/CR 5973 R02 CODES AND STANDARDS AND OTHER GUID-SAFETY RELATED NUCLE AR PLANT STRUCTURES ANCE CITED IN REGULATORY DOCUMENTS BACA.R.G.
BONANO;E.J.
j NUREG/CR 6351: REVIEW OF SCENARIO SELECTION APPROACHES NUREG/CR-6351 REVIEW OF SCENARIO SELECTION APPROACHES FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL WASTE RE-FOR PERFORMANCE ASSESSMENT OF HIGH LEVEL WASTE RE-i POSITORIES AND RELATED ISSUES.
POSITORIES AND RELATED ISSUES.
N RE 1522. ASSESSMENT OF INSERVICE CONDITIONS OF NUREG/CR-6150 VOS:
SCDAP/RELAPS/ MOD 3.1 CODE SAFETY.RELATED NUCLEAR PLANT STRUCTURES.
MANUAL Developmental Assessment i
EAIL,W.
4 NUREG/CR 6263 V01; HIGH INTEGRITY SOFTWARE FOR NUCLEAR BRAMWELL,D.
POWER PLANTS Candidate Guidehnes. Technical Basis And Re earch NUREG/CR-6100: GATE VALVE AND MOTOR-OPERATOR RESEARCH Needs Executive Summary FINDINGS NUREG/CR-6263 V02 HIGH INTEGRITY SOFTWARE FOR NUCLEAR POWER PLANTS Candidate Guidelines. Technical Basis And Research BROWN,E.J.
Needs. Main Report.
NUREG/CP 0146 PROCEEDINGS OF THE WORKSHOP ON GATE i
EANKS,W.W.
NUREG/CR-6323: RELATIVE RISK ANALYSIS IN REGULATING THE BROWN,W.S.
4 USE OF RADIATION-EMITTING MEDICAL DEVICES A Prehminary Ap.
NUREG-1507 DRFT N: MINIMUM DETECTABLE CONCENTRATIONS WITH TYPICAL R ADIATION SURVEY INSTRUMENTS FOR VARIOUS NUR CR-6324 OUAUTY ASSURANCE FOR GAMMA KNIVES CONTAMINANTS AND FIELD CONDITIONS Draft Report For Com.
EARRIERE,M.T.
ment.
NUREG/CR-6265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF CALLAN.J.R.
COMMISSION AND DEPENDENCIES.
NUREG/CR-6125 V03 HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-R4184: SEPARATE EFFECTS TESTING AND ANALYSES TO a a t e At d F d a INVESTIGATE LINER TEAR:NG OF THE 1:16-SCALE REINFORCED CONCRETE CONTAINMENT BUILDING CASADA.D.A.
NUREG/CR 6089: DETECTION OF PUMP DEGRADATION.
DERNA,G.A.
NUREG/CR-6150 V01:
SCDAP/RELAP5/ MOD 3.1 CODE CHAMBERS.R NURE /
150 V
SCDAP/RELAP/ MOD 31 CODE NUREG/CR 6150 V04.
SCDAP/RELAP5/ MOD 3.1 CODE MANUALDamage Progression Model Theory MANUALMATPRO-A Ubrary Of Matenals Properties For Ught-Water-NUREG/CR4150 Vua SCDAP/RELAP5/ MOD 31 CODE Reactor Acodent Anatysis.
MANUAL. User's Guide And input Manual NUREG/CR4150 V04:
SCDAP/RELAP5/ MOD 3.1 CODE CHENG,T.C.
MANUALMATPR(bA Ubrary Of Malenals Properties For Light Water.
NUREG/CP 6150 V02.
SCDAP/RELAP/ MOD 3.1 CODE j
Reactor Acesdent Analysis.
MANUAL Damage Progression Model Theory.
15 i
16 Personal Author index CHIN.E.
EASTERLY,J.C.
NUREG/CR4125 V03. HUMAN FACTORS EVALUATION OF REMOTE NOREG/CR 6125 V03: HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Humary System interfaces. Procedures And Practces.Tranng And Organaation-System Interfaces. Procedures And Practces,Tranng And Organaatiore al Practces And Procedures al Practces And Procedures.
CHOPRA,0.K.
FADDEN.M.
NUREG/CR-4667 Vl9-ENVIRONMENTALLY ASSISTED CRACKING IN NUREG.0525 V02 R03. SAFEGUARDS
SUMMARY
EVENT LIST LIGHT WATER REACTORS. Semiannual Report. April-September 1994.
(SSEL). January 1,1990 Through December 31,1994.
NUREG/CR4335: FATIGUE STRAIN-LIFE BEHAVIOR OF CARDON AND LOW-ALLOY STEELS. AUSTENITIC STAINLESS STEELS, AND FEINER,F.
ALLOY 600 IN LWR ENVIRONMENTS.
NUREG/CP 0142 V01: PROCEEDINGS OF THE 7TH INTERNATIONAL MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS CHUNG,H.M.
(NURETH-7). Sessions 1-5.
NUREG/CR.4667 V19: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CP-0142 V02: PROCEEDINGS OF THE 7TH INTERNATIONAL LIGHT WATER REACTORS. Semiannual Report.Apnl September 1994.
MEETING ON NUCLEAR REACTOR THERMAL. HYDRAULICS (NURETH 7). Sessions 611.
CLEAVES,D NUREG/CP-0142 V03. PROCEEDINGS OF THE 7TM INTERNATIONAL NUREG/CR.6263 VOI: HIGH INTEGRITY SOFTWARE FOR NUCLEAR MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS POWER PLANTS Candidate Guidelines. Technmal Basis And Research (NURETH-7). Sessions 12-16.
NUREG/CP-0142 V04 PROCEEDINGS OF THE 7TH INTERNATIONAL NU
/
V li INTEGRITY SOFTWARE FOR NUCLEAR MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS POWER PLANTS. Candidate Guidelines. Techncal Basis And Research (NURETH.7).Sessanns 17 24.
Needs Main Report.
FIELD L COHEN H'CR4263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR NUREG/CR-5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/
INDUSTNY. Annual Summary Of Program Performance Reports CY POWER PLANTS Candidate Guidelines, Technical Basis And Research 1994 Needs Executive Summary, NUREG/CR4263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR FISCHER,LE R LANT andidate Guidelines, Technical Basis And Research USE OF RADIATION EMITTING MEDICAL DEVICES.A Preliminary Ap-COOPER,S.E.
plication.
NUREG/CR 6265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN NUREG/CR4324 QUALITY ASSURANCE FOR GAMMA KNIVES.
RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF FLETCHE R.C.D.
COMMISSION AND DEPENDENCIES.
NUREG/CR-5535 V05 R1: RELAPS/ MOD 3 CODE MANUALUser's CORWIN,W.R.
Guideline.
NUREG/CR 5591 V05 N2: HEAVY.SECTION STEEL 1RRADIATION PROGRAM Progress Report For April 1994 Through September 1994.
GAVENDA,D.J.
N1"1EG/CR-4667 V19: ENVIRONMENTALLY ASSISTED CRACKING IN CONYELL E.W.
tlGHT WATER REACTORS. Semiannual Regvart. April. September 1994.
NUREG/CR4150 V01:
SCDAP/RELAPS/ MOD 3.1 CODE MANUALinterface Theory.
GOGOLAK,C.V.
NUREG/CR.6150 V02.
SCDAP/RELAP/ MOD 3.1 CODE NUREG 1505 DRFT FC: A NONPARAMETRIC STATISTICAL METHOD-MANUAL Damage Progression Model Theory.
OLOGY FOR THE DESICN AND ANALYSIS OF FINAL STATUS DE-NUREG/CR4150 V03 SCDAP/RELAP5/ MOD 3.1 CODE COMMISSIONING SURVEYS. Draft Report For Comment.
MANUAL. User's Guide And input Manual.
NUREG/CR4150 V0+
SCDAP/RELAP5/ MOD 31 CODE GOODENOW,T.C.
MANUALMATPRO-A Library Of Matenals Properties For Light-Water.
NUREGICR-6313 V01: ROBUST. ACCURATE, AND NON-CONTACTING urements Of The Robust Laser Interferometer And Typical Acceit ome.'
NUR C 6150 5-SCDAP/RELAP5/ MOD 31 CODE MANUALDevelopmental Assessment.
ter Systems.
NUREG/CR 6313 V02: ROBUST, ACCURATE. AND NON-CONTACTING CUNNINGHAM M NUREG/CR5N8 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER VIBRATION MEASUREMENT SYSTEMS. Supplemental Appendees Presenting Companson Measurements Of The Robust Laser Interter.
INDUSTRY. Annual Summary Of Program Performance Reports CY ometer And Typical Accelerometer Systems.
g994 GRE EN,R.T.
DAVIS.K.L.
NUREG/CR-6356. HYDRAULIC CHARACTERIZATION OF HYDROTH-NUREG/CR.6150 VOI:
SCDAP/RELAP5/ MOD 3.1 CODE ERMALLY ALTERED NOPAL TUFF.
)
MANUAL Interface Theory NUREG/CR.6150 V02.
SCDAP/RELAP/ MOD 3.1 CODE f
GRE E NE,R.H.
MANUALDamage Progresson Model Theory NUREG/CR.6150 V03.
SCDAP/RELAPS/ MOD 3.1 CODE NUREG/CR6089 DETECTION OF PUMP DEGRADATION.
MANUALUser's Guide And input Manual.
NUREG/CR 6150 V04' SCDAP/RELAPS/ MOD 3.1 CODE GROSSMAN,N.
MANUALMA1 PRO-A Library Of Matenals Properties For Light-Water.
NUREG 1519 SURFACE INTERACTIONS OF CESIUM AND BORIC j
ACID WITH STAINLESS STEEL.
j Reactor Accident Analysis.
NUREG/CR.6150 V05.
SCDAP/RELAP5/ MOD 31 CODE j
GR E MANUALDevelopmental Assessment DEWALL,K.G, LIGHT WATER REACTORS. Semiannual Report.Apni-September 1994.
NUREG/CR4100: GATE VALVE AND MOTOR. OPERATOR RESEARCH FINDINGS.
HAGRMAN D.L NUREG/CR-6150 V02:
SCDAP/RELAP/ MOD 3.1 CODE DOTY,K.
MANUAL. Damage Progression Model Theory.
NUREG/CR-2907 V13 RADIOACTIVE MATERIALS RELEASED FROM NUREG/CR-6150 V04 SCDAP/RELAPS/ MOD 31 CODE NUCLEAR POWER PLANTS. Annual Report 11#92.
MANUALMATPRO-A Library Of Matenais Properties For Light Water.
Reactor Accident Analysis DURSIN,N.
NUREG/CR 5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER HAGRMAN,D.T.
INDUSTRY. Annual Summary Of Program Performance Reports CY NUREG/CR.6150 VOI:
SCDAP/RELAPS/ MOD 3.1 CODE 1994 MANUALinterface Theory.
Personal Author Index 17 NUREG/CR-6150 V02:
SCDAP/RELAP/ MOD 3.1 CODE HYBERTSON.D.
MANUAL. Damage Prog. ression Model Theory NUREG/CR 6263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR NUREG/CR 6150 V03-SCDAP/RELAP5/ MOD 3.1 CODE POWER PLANTS Candidate Guidehnes, Technical Basis And Research MANUAL. Users Guide And input Manual-Needs Executive Summary.
NUREG/CR 6150 V04-SCDAP/RELAP5/ MOD 3.1 CODE NUREG/CR-6263 V02: H!GH INTEGRITY SOFTWARE FOR NUCLEAR MANUALMATPRO-A Library Of Matenals Properties For Light-Water
- POWER PLANTS Canddate Guidehnes. Technical Basis And Research Heactor Accident Analyses Needs. Main Report.
NUREGICR-6150 V05:
SCDAP/RELAPS/ MOD 3.1 CODE MANUALDevelopmental Assessment.
JOHNSEN.E.C.
NUREG/CR-6150 V03:
SCDAP/RELAPS/ MOD 31 CODE I
CR 6188 V02: MICROBIAL DEGRADATION OF LOW-LEVEL NUR NUREG/ R 610 05 SD LAP 5/ MOO 3.1 CODE RADIOACTIVE WASTE. Annual Report For FY 1994 MANUALDevelopmental Assessment.
HAMPTON,N.L JONES,E.D.
NUREG/CR-6150 V04.
SCDAP/RELAP5/ MOD 3.1 CODE NUREG/CR-6323. RELATIVE RISK ANALYSIS IN REGULATING THE MANUAL.MATPRO--A L brary Of Matenals Properties For Light-Water.
USE OF RADIATION-EMITTING MEDICAL DEVICES.A Prelmnar) Ap.
Reactor Accident Analysis.
pucation.
HASHEMIAN,H.M.
NUREG/CR 6324: OUAllTY ASSURANCE FOR GAMMA KNIVES.
NUREG/CR-6334: NEW SENSOR FOR MEASUREMENT OF LOW AIR J ES R FLOW VELOCITY. Phase 1 Final Report.
HASHEMIAN,M.
THERAPY. Identification Of Problems And Alternative Approaches.
NUREG/CR-6334. NEW SENSOR FOR MEASUREMENT OF LOW AIR NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF FLOW VELOCITY. Phase 1 Final Report.
TELETHERAPY. Function And Task Analysis.
NUREG/CR-6277 V03.
HUMAN FACTORS EVALUATION OF HATTRUP,M.
TELETHERAPY Human-System Interfaces And Procedures.
i NUREG/CR 5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR-6277 V04.
HUMAN FACTORS EVALUATION OF INDUSTRY. Annual Summary Of Program Performance Reports CY TELETHERAPY. Training And Organizational Analysis.
1994.
NUREG/CR-6277 V05: HUMAN FACTORS EVALUATION OF TELETHERAPY. Literature Review HENRIKSEN.K.
NUREG/CR 6277 V01: HUMAN FACTORS EVALUATION OF TELE.
JORDAN,W.C.
i THERAPY. Identification Of Problems And Alternative Approaches.
NUREG/CR-6328: ADEOUACY OF THE 123-GROUP CROSS-SECTION NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF LIBRARY FOR CRITICALITY ANALYSES OF WATER. MODERATED TELETHERAPY Function And Task Analysis.
~
URANIUM SYSTEMS.
NUREG/CR-6277 V03 HUMAN FACTORS EVALUATION OF I
TELETHERAPY Human System Interfaces And Piocedures.
K ASSNE R,T.F.
NUREG/CR 6277 V04 - HUMAN FACTORS EVALUATION OF NUREG/CR-4667 V19: ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS Semiannual Report,Apni-September 1994.
NU 62 5
U f FA RS E\\ALUATION OF TELETHERAPY. Literature Review KASUMOVIC J.
NUREG/CR-6125 V03 HUMAN FACTORS EVALUATION OF REMOTE HINS,A G AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-NUREG/CR-4667 Vl9 ENVIRONMENTALLY ASSISTED CRACKING IN System Interfaces, Procedures And Prachces, Training And Organization-LIGHT WATER REACTORS. Semiannual Report,Apni-September 1994 al Practices And Procedures.
j HOHORST,J.K.
NU EG CR-6277 V01: HUMAN FACTORS EVALUATION OF TELE.
MA UAL Interface Th l
NUREGICR 6150 V02.
SCDAP/RELAP/ MOD 31 CODE THERAPY. Identification Of Problems And Alternative Approaches.
NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF l
MANUALDamage Progression Model Theory.
NUREG/CR-6150 V03-SCDAP/RELAPS/ MOD 3.1 CODE TELETHERAPY Function And Task Analysis.
NUREG/CR-6277 V03.
HUMAN FACTORS EVALUATION OF MANUAL User's Guide And in t Manual NUREG/CR 6150 V04.
DAP/RELAPS/ MOD 31 CODE TELETHERAPY. Human-System Interfaces And Procedures.
MANUALMATPRO-A Library Of Matenals Properties For Light Water.
NUREG/CR-6277 V04: HUMAN FACTORS EVALUATION OF i
l Reactor Accident Analysis.
TELETHERAPY. Training And Organizational Analysis.
l NUREG/CR-6150 V05-SCDAP/RELAPS/ MOD 3.1 CODE NUREG/CR-6277 V05: HUMAN FACTORS EVALUATION OF MANUALDevelopmental Assessment.
TELETHERAPY. Literature Review.
HOLLAND,H.M.
KEISLER.J.
NUREG/CR-6313 V01: RODUST, ACCURATE AND NON. CONTACTING NUREG/CR-6335. FATIGUE STRAIN-LIFE BEHAVIOR OF CAR 8ON VIBRATION MEASUREMENT SYSTEM Summary of Companson Meas.
AND LOW-ALLOY STEELS. AUSTENITIC STAINLESS STEELS, AND urements Of Th6 Robust Laser interferometer And Typical Accelerome-ALLOY 600 IN LWR ENVIRONMENTS.
ter Systems.
NUREG/CR-6313 V02: ROBUST, ACCURATE, AND NON. CONTACTING KELLY,R.T.
VlBRATION MEASUREMENT SYSTEMS Supplemental Appendices NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF REMOTE Presenting Companson Measurements Of The Robust Laser interfer.
AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-ometer And Typical Accelerometer Systems System intedaces. Procedures And Practices, Training And Organizabon-at Practsces And Procedures.
C4UFFERT,A.M.
NUREG 1505 DAFT FC: A NONPARAMETRIC STATISTICAL METHOD.
LAM 8ERT,LD.
OLOGY FOR THE DESIGN AND ANALYSIS Or FINAL STATUS DE-NUREG/CR 6184. SEPARATE EFFECTS TESTlNG AND ANALYSES TO COMMISSIONING SURVEYS Draft Report For Comment.
INVESTIGATE LINER TEARING OF THE 1:16-SCALE REINFORCED blVREG-1506 DAFT FC: MEASUREMENT METHODS FOR RADIOLOGI-CONCRETE CONTAINMENT BUILDING.
CAL SURVEYS IN SUPPORT OF NEW DECOMMISSIONING CRITERIA Draft Report For Comment LAUGHERY,K.R.
NUREG-1507 DAFT FC: MINIMUM DETECTABLE CONCENTRATIONS NUREG/CR-6159: USING MICRO SAINT TO PREDICT PERFORMANCE WITH TYPICAL RADIATION SURVEY INSTRU'MENTS FOR VARIOUS IN A NUCLEAR POWER PLANT CONTROL ROOM.A Test Of Yahdity CONTAMINANTS AND FIELD CONDITIONS Draft Report For Com-And Feasibihty.
ment.
LAWLESS,M.T.
l HUGHES,T.H.
NUREG/CR 6159: USING MICRO SAIN1 TO PREDICT PERFORMANCE l
WUREG/CR-4667 V19 ENVIRONMENTALLY ASSISTED CRACKING IN IN A NUCLEAR POWER PLANT CONTROL ROOM.A Tsst Of Vahdity LIGHT WATER REACTORS. Semiannual Report.Apnt-September 1994.
And Feasibihty.
18 Personal Author index LEPAGUl.P.
NUREG/CR 6277 V03: HUMAN FACTORS EVALUATION OF NUREG/CR4125 V03: HUMAN FACTORS EVALUATION 08 REMOTE TELETHERAPY. Human System interfaces And Procedures.
AFTERLOADING BRACHYTHERAPY. Supporting Anatyses Of Human.
NUREG/CR4277 V04' HUMAN FACTORS EVALUATION OF System Interfaces, Procedures And Practices,Tranng And Orgarnahon-TELETHERAPY.Tranng And Organizational Analysis.
af Practices And Procedures.
NUREG/CR4277 VOS: HUMAN FACTORS EVALUATION OF TELETHErMPY. Literature Review.
LICHTNER,P.C.
NUREG/CR4347: MULTI. PHASE REACTIVE TRANSPORT THEORY, MUCKLER,F.A.
NUREG/CR4125 V03. HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-R G C 4261: A
SUMMARY
OF ORNL FISSION PRODUCT RE-System lnterfaces. Procedures And Practices,Tranng And Organization-LEASE TESTS WITH RECOMMENDED RELEASE RATES AND DIF.
al Practices And Rocedures.
FUSION COEFFICIENTS.
NICKOLAUS,J.R.
LUCADAMO,X.
NUREG/CR-5973 R02: CODES AND STANDARDS AND OTHER GUID-NUREG/CR-2907 V13: RADIOACTIVE MATERIALS RELEASED FROM ANCE CITED IN REGULATORY DOCUMENTS.
NUCLEAR POWER PLANTS. Annual Report 1992 LUCKAS.WJ.
OLSEN C.S.
NUREG/CR4265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN NUREG/CR-6150 VO4; SCDAP/RELAP5/ MOD 3.1 CODE REllABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF MANUALMATPRO-A Library Of Matenals Properties For Light-Water-COMMISSION AND DEPENDENCIES.
Reactor Acesdent Analysis.
MACKINNON.R.J.
OSBORNE M.F.
NUREG/CR4305; BLT EC (BREACH. LEACH, TRANSPORT, AND EQUI-NUREG/CR4261: A
SUMMARY
OF ORNL FISSION PRODUCT RE-LIBRtVM CHEMISTRY). A FINITE ELEMENT MODEL FOR ASSESS-LEASE TESTS WITH RECOMMENDED RELEASE RATES AND DIF-ING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE FUSION COEFFICIENTS.
DISPOSAL UNITS. Background, Theory, And Model Descript ort PAIK,S.
MASON,R.E.
NUREG/CR4150 V02.
SCDAP/RELAP/ MOD 3.1 CODE NUREG/CR-6150 V04.
SCDAP/RELAPS/ MOD 3.1 CODE MANUALDamage Progression Model Theory.
MANUALMATPRO-A Library Of Materials Properties For Light-Water.
Reactor Accident Analysis-PARKS,C.V.
NUREG/CR4328. ADEOUACY OF THE 123-GROUP CROSS-SECTION LIBRARY FOR CRITICAUTY ANALYSES OF WATER MODERATED NU CR 150 V04:
SCDAP/RELAP5/ MOD 31 CODE URANIUM SYSTEMS.
MANUALMATPRO-A Library Of Matenals Properties For Light-Water.
Reactor Accident Ana!yssa PAULSEN,M.P.
NUREG/CR4325: AN IMPLICIT STEADY STATE INITIALIZATION PACK-MCCONNELL,J.W.
NUREG/CR4188 V02: MICROBIAL DEGRADATION OF LOW LEVEL AGE FOR THE RELAP5 COMPUTER CODE.
RADIOACTIVE WASTE. Annual Report For FY 1994.
MCOONALD,J.C.
NUREG/CR4159 USING MICRO SAINT TO PREDICT PERFORMANCE NUREG/CR6354 DAF FC. PERFORMANCE TESTING OF ELECTRON-IN A NUCLEAR POWER PLANT CONTROL ROOM.A Test Of Validity IC PERSONAL DOSIMETERS. Draft Report For Comment.
And Feasability.
MCELHANEY,K.L.
PETERSON C.E.
NUREG/CR-5944 V02: A CHARACTERIZATION OF CHECK VALVE NUREG/CR4325: AN IMPLICIT STEADY STATE INITIALIZATION PACK-DEGRADATION AND FAILURE EXPERIENCE IN THE NUCLEAR AGE FOR THE RELAP5 COMPUTER CODE.
POWER INDUSTRY.1991 Failures.
PIPER,R.K.
MCNEIL,K.A.
NUREG/CR4354 DRF FC: PERFORMANCE TESTING OF ELECTRON-NUREG/CR4150 V04.
SCDAP/RELAP5/ MOD 31 CODE IC PERSONAL DOSIMET ERS.OrMt Report For Comment.
MANUAL.MATPRO-A Library Of Matenals Properties For Light-Water.
Reactor Accident Analysis.
POWERS,G.E.
NUREG-1505 DRFT FC: A NONPARAMETRIC STATISTICAL METHOD-I MEYER JAMES,K.A NUREG/CR4356: HYDRAULIC CHARACTER 12ATION OF HYDROTH-OLOGY FOR THE DESIGN AND ANALYSIS OF FINAL STATUS DE-ERMALLY ALTERED NOPAL TUFF.
COMMISSIONING SURVEYS Draft Report For Comment.
MILLER,K.M.
QUINN,M.L.
NUREG-1506 DAFT FC: MEASUREMENT METHODS FOR RADIOLOGI-NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF REMOTE CAL SURVEYS IN SUPPORT OF NEW DECOMMISSIONING AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human.
CRITERIA. Draft Report For Comment.
System interfaces. Procedures And Practices.Tranng And Organization-al Prachces And Procedures.
NUREG/CR4150 V04:
SCOAP/RELAPS/ MOD 3.1 CODE RAMEY-SMITH,A.
MANUALMATPRO--A Library Of Malenals Propertes For Light. Water-NUREG/CR6265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN Reactor Accident Analysrs RELIABILITY ANALYSIS Wi1H AN APPLICATION TO ERRORS OF MONTELEONE,S.
NUREG/CP-0148. TRANSACTIONS OF THE TWENTY THIRD WATER REYMANN,G.A.
REACTOR SAFETY INFORMATION MEETING NUREG/CR 6150 V04:
SCDAP/RELAP5/ MOD 3.1 CODE MOORE.R.A.
MANUAL.MATPRO--A Lsbrary Of Matenals Properties For Light-Water-NUREG/CR4125 V03: HUMAN FACTORS EVALUATION OF REMOTE Reactor Accident Analysis.
AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-Sys e ntert s Procedures And Practices,Tranng And Organization-g gg MODELING.Pnontizahon Of Masntenance importances And Quantifica-MORISSEAU,0.S.
bon Of Maintenance Effectiveness.
NUREG/CR6277 VOI: HUMAN FACTORS EVALUATION OF TELE-THERAPY. Identification Of Problems And Altemative Approaches.
RICE,G.
NUREG/CR4277 V02: HUMAN FACTORS EVALUATION OF NUREG/CR.6356: HYDRAULIC CHARACTERt2ATION OF HYDROTH-TELETHERAPY. Function And Task Analysis.
ERMALLY ALTERED NOPAL TUFF.
Personal Author index 19 RIGOSSEE.E.T.
SIEFKEN,L.J.
NUREG/CR4334. NEW SENSOR FOR MEASUREMENT OF LOW AIR NUREG/CR4150 V01:
SCDAP/RELAPS/ MOD 3.1 CODE i
FLOW VELOCITY Phase I Final Report MANUALinterface Theory l
NUREG/CR4150 V02:
SCDAP/RELAP/ MOD 3.1 CODE l
ROGERS.RA MANUALDamage Progression Model Theory.
NUREG/CR4188 V02: MICROBIAL DEGRADATION OF LOW-LEVEL NUREG/CR4150 V03:
SCDAP/RELAP5/ MOD 3.1 CODE RADIOACTIVE WASTE. Annual Report For FY 1994.
MANUALUser's Guide And input Manual.
NUREG/CR4150 V04:
SCDAP/RELAP5/ MOD 3.1 CODE
^
- "*'8 E
'4100; GATE VALVE AND MOTOR-OPERATOR RESEARCH Reactor Accident Analyss.
t FINDINGS.
i NUREG/CR4150 V05:
SCDAP/RELAP5/ MOD 31 CODE MUTHER,W.E.
MANUALDevelopmental Assessment.
NUREG/CR4667 V19 ENVIRONMENTALLY ASSISTED CRACKING IN 0
LIGHT WATER REACTORS. Sermannual Report.Apr& September 1994.
E 6305. BLT-EC (BREACH, LEACH, TRANSPORT, AND EQUI-SAUNDERS,W.M.
LIBRIUM CHEMISTRY). A FINITE-ELEMENT MODEL FOR ASSESS-NUREG/CR4125 V03: HUMAN FACTORS EVALUATION OF REMOTE ING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE AFTERLOADtNG BRACHYTHERAPY.Supporung Analyses Of Human.
DioPOSAL UNITS. Background, Theory, And Model Descnption.
Systeen interfaces, Procedures And Practces,Tranng And Organizahon-al Practces And Procedures.
SISK.D.R.
i NUREG/CR4354 DRF FC: PERFORMANCE TESTING OF ELECTRON-l SCHAEFER C.
IC PERSONAL DOSIMETERS. Draft Report For Comment.
I NUREG/CR4263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR l
POWER PLANTS.Candedate Guidehnes Technmal Bases And Research SOPPET,W.K.
i Needs Execuhve Summary.
NUREG/CR.4667 V19: ENVIRONMENTALLY ASSISTED CRACKING IN l
NUREG/CR 6263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR LIGHT WATER REACTORS Semiannual Report.Apni September 1994.
POWER PLANTS Candidate Guideknes, Techncal Baset And Research Needs. Main Report.
SPLETZER,5.L NUREG/CR 6184: SEPARATE EFFECTS TESTING AND ANALYSES TO l
-SCHOENFELD L INVESTIGATE LINER TEARING OF THE 1:16-SCALE REINFORCED i
l l
NUREG/CR4125 VU1 HUMAN FACTORS EVALUATION OJ REMOTE CONCRETE CONTAINMENT BUILDING.
i l
AFTERLOADING BRACHYTHERAPY.Supporhng Analyses ")f Human-l System interfaces, Procedures And Practices,Tranng And Organizahon-STEELE,R.
al Practces And Procedures.
NUREG/CR 6100: GATE VALVE AND MOTOR-OPERATOR RESEARCH SCHULTZ,R.R.
i NUREG/CRf535 V05 R1: RELAPS/ MOD 3 CODE MANUALUser's STOTHOFF,S.A.
Guidehne' NUREG/CR4333. BREATH VERSION 1.1 COUPLED FLOW AND ENERGY TRANSPORT IN POROUS MEDIA Simulator Desenphon And I
SERIG.D1 User Guide.
NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY.Supporhng Analyses Of Human-STRUCKMEYER,R Sys e nterfaces Pr es And Practces,Tranng And Organizam NUREG.0837 V15 NO2: NRC TLD DIRECT RADIATION MONITORING NUREG/CR4277 V01: HUMAN FACTORS EVALUATION OF TELE-NETWORK. Progress Report.Apnt-June 1995.
THERAPY, identifcahon Of Problems And Alternative Approaches.
NUREG/CR4277 V02: HUMAN FACTORS EVALUATION OF STUART,G.
NUREG/CR 6263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR TELETHERAPY. Function And Task Analysis.
i NUREG/CR4277 V03: HUMAN FACTORS EVALUATION OF POWER PLANTS Candedate Guidehnes. Techncal Basis And Research TELETHERAPY. Human-System Interfaces And Procedures.
Needs. Main Report.
NUREG/CR-6277 V04: HUMAN FACTORS EVALUATION OF TELETHERAPY.Tranng And Organizahonal Analysis SUEN,C.J.
NUREG/CR4277 V05.
HUMAN FACTORS EVALUATION OF NUREG/CR.6305. BLT-EC (BREACH, LEACH, TRANSPORT, AND EQUI-TELETHERAPY. Literature Review.
LIBRIUM CHEMISTRY), A FINITE-ELEMENT MODEL FOR ASSESS-ING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE G/CR4263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR POWER PLANTS. Candidate Guidehnes, Techncal Bases And Research SULLIVAN,T.M.
Neede Executrve Summary-NUREG/CR-6305: BLT EC (BREACH. LEACH, TRANSPORT, AND EQUI-NUREG/CR4263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR LIBRIUM CHEMISTRY), A FINITE ELEMENT MODEL FOR ASSESS-POWER PLANTS Candidate Guedehnes, Technical Bams And Research ING THE RELEASE OF RADIONUCLIDES FROM LOW. LEVEL WASTE Needs. Main RepM DISPOSAL UNITS Background. Theory, And Model Desenption.
INAO"'G/CR-4867 V19: ENVIRONMENTALLY ASSISTED CRACKING IN SWINTH,K.L NURE NUREG/CR4354 DRF FC: PERFORMANCE TESTING OF ELECTRON-LIGHT WATER REACTORS. Semiannual Report,Apnt-September 1994.
IC PERSONAL DOSIMETERS. Draft Report For Cornment.
NUREG/CR4335: FATIGUE STRAIN-LIFE BEHAVIOR OF CARBON AND LOW-ALLOY STEELS, AUSTENITIC STAINLESS STEELS, AND ALLOY 600 IN LWR ENVIRONMENTS.
REG /CR-6263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR SHIEH,A.S.
POWER PLANTS Candidate Guidelines. Technical Basis And Research NUREG/CR4 tSO V02-SCDAP/RELAP/ MOD 3.1 CODE Needs Executrve Summary.
MANUALDemage Progresson Model Theory.
NUREG/CR4263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR POWER PLANTS Candidate Guidehnes Techncal Basis And Research SHIPMAN,R.L Needs. Main Report.
NUREG/CR4313 V01: ROBUST, ACCURATE, AND NON CONTACTING VIBRATION MEASUREMENT SYSTEM. Summary of Compenson Meas.
THOMPSON,M.G.
urements Of The Robust Laser interferometer And Typcal Accelerome-NUREG/CR4354 DRF FC: PERFORMANCE TESTING OF ELECTRON-ter Systems.
IC PERSONAL DOSIMETERS Draft Report For Comment.
NUREG/CR4313 V02-ROBUST, ACCURATE, AND NONCONTACTING VIBRATION MEASUREMENT SYSTEMS. Supplemental Appendices TICHLER,J.
Preeereng Companoon Measurements Of The Robust Laser interfer.
NUREG/CR-2907 V13. RADIOACTIVE MATERIALS RELEASED FROM omster And Typcal Accelerometer Systers NUCLEAR POWER PLANTS. Annual Report 1992.
20 Personal Author IndOx WESTRA,C.
TORTORELLl,J.P.
NUREG/CP-0144 V01: A WORKSHOP ON DEVELOPING RISK ASSESS-NUREG/CR-5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER MENT METHODS FOR MEDICAL USE OF RADIOACTIVE INDUSTRY. Annual Summary Of Program Performance Reports CY MATERIALSummary 1994' NUREG/CP4144 V02: A WORKSHOP ON DEVELOPING RISK ASSESS-MENT METHODS FOR MEDICAL USE OF RADIOACTIVE WHITEHEAD,D.W.
MATERIALSupporting Documents.
NUREG/CR-6143 V01: EVALUATION OF POTENTIAL SEVERE ACCl-NUR G'/CR4263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR R D U UNT Su ary Re s POWER PLANTS Candidate Guxletines, Techrwcal Basis And Research Needs Erscutuo Summa.
WILSON,R.
NUREG/CR4263 V02. HlhH INTEGRITY SOFTWARE FOR NUCLEAR NUREG/CR 5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER l
l POWER PLANTS Candidate Guidelines. Technical Basis And Research INDUSTRY. Annual Su mary Of Program Performance Reports CY m
l Needs Main Report VEEH.R.H.
NUREG/CR 6188 V02: MICRO 0lAL DEGRADATION OF LOW. LEVEL WREATHALL J.
RADIOACTIVE WASTE. Annual Report For FY 1994.
NUREG/CR4265: MULTlDISCIPLINARY FRAMEWORK FOR HUMAN REllABILITY ANALYSIS wtTH AN APPLICATION TO ERRORS OF VESELY,W.E.
RISK-BASED MAINTENANCE COMMISSION AND OEPENDENCIES.
MODELING Pnontuata Of Maintenance importances And Quantifica-ton Of Maintenance Effectueness.
WRIGHT R.O.
NUREG/CR4328: ADEOUACY OF THE 123-GROUP CROSS-SECTION CATKINS,J.C.
LIBRARY FOR CRITICALITY ANALYSES OF WATER. MODERATED NUREG/CR4100: GATE VALVE AND MOTOROPERATOR RESEARCH URANIUM SYSTEMS.
FINDINGS.
WEATHERBY,J.R.
YARDUMIAN,J.
4 NUREG/CR4184. SEPARATE EFFECTS TESTING AND ANALYSES TO NUREG4525 V02 R03: SAFEGUARDS
SUMMARY
EVENT LIST INVESTIGATE LINER TEARING OF THE 1:16-SCALE REINFORCED (SSEL). January 1,1990 Through December 31,1994.
CONCRETE CONTAINMENT BUILDING l
4 1
Subject Index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be some redundancy, which will be removed later when a rea-sonable thesaurus has been developed through experience. Suggestions for improvements are welcome.
AEOD Candidate Guldeline NUREG-1272 V06 NO2 OFFICE FOR ANALYSIS AND EVALUATION OF NUREG/CR 6263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR OPERATIONAL DATA,1993 Annual Report - Nuclear Matenals.
POWER PLANTS Candidate Guidehnes, Technical Basis And Research Needs Executive Summary.
Abnormal Occurrence NUREG/CR 6263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR NUREG-0090 V17 N04. REPORT TO CONGRESS ON ABNORMAL POWER PLANTS candidate Guidehnes, Technical Basis And Research OCCURRENCES October-December 1994.
Needs Main Report.
NUREG-0000 V10 N01: REPORT TO CONGRESS ON ABNORMAL OCCURF.ENCES. January-March 1995.
Cesium Hydroxide NUREG-1519. SURFACE INTERACTIONS OF CESIUM AND BORIC Accelerometer System ACID WITH STAINLESS STEEL NUREG/CR-6313 V01: ROBUST. ACCURATE. AND NON-CONTACTING VIBRATION MEASUREMENT SYSTEM Sumrnary of Companson Meas.
Check Valve wer nts Of The Robust Laser interferometer And Typical Accelerome-DEGRADATION AND FAILURE EXPERIENCE IN THE NUCLEAR NUREG/CR-6313 V02. ROBUST. ACCURATE. AND NON CONTACTING POWER INDUSTRY.1991 Failures.
VIBRATION MEASUREMENT SYSTEMS Supplemental Appendices Codes And Standards Presenting Companson Measurements Of The Robust Laser Interior-NUREG/CR-5973 R02: CODES AND STANDARDS AND OTHER GUID-ometer And Typical Accelerometer Systems-ANCE ClTED IN REGULATORY DOCUMENTS.
Advisory Committee On Nuclear Waste Concrete NUREG 1423 V05: A COMPILATION OF REPORTS OF THE ADVISORY NUREG/CR-6188 V02: MICROBlAL DEGRADATION OF LOW-LEVEL COMMITTEE ON NUCLEAR WASTE. July 1993 - June 1995.
RADIOACTIVE WASTE. Annual Repor1 For FY 1994.
Aging Containment NUREG/CR 5944 V02: A CHARACTERIZAYlON OF CHECK VALVE NUREG 1522: ASSESSMENT OF INSERVICE CONDITIONS OF DEGRADATION AND FAILURE EXPERIENCE IN THE NUCLEAR SAFETY-RELATED NUCLEAR PLANT STRUCTURES.
POWER INDUSTRY.1991 Failures.
NUREG/CR-6089 DETECTION OF PUMP DEGRADATION Containment Building NUREG/CR-6184. SEPARATE EFFECTS TESTING AND ANALYSES TO Air Flow Velocity INVESTIGATE LINER TEARING OF THE 1:16-SCALE REINFORCED NUREG/CR 6334. NEW SENSOR FOR MEASUREMENT OF LOW AIR CONCRETE CONTAINMENT BUILDING.
FLOW VELOCITY Phase 1 Final Report Control Room Olrt>orne Effluent NUREG/CR-6159 USING MICRO SAINT TO PREDICT PERFORMANCE NUREG/CR-2907 V13: RADIOACTIVE MATERIALS RELEASED FROM IN A NUCLEAR POWER PLANT CONTROL ROOM.A Test Of Vahdity NUCLEAR POWER PLANTS Annual Report 1992 And Feasibility Annual Report Corrosion Fatigue NUREG 1145 V11: U S. NUCLEAR REGULATORY COMMISSION 1994 NUREG/CR-4667 V19: ENVIRONMENTALLY ASSISTED CRACKING IN ANNUAL REPORT, LIGHT WATER REACTORS. Semiannual Report.Apnt-September 1994.
A O A L Y S EE S. A S E T SA L SS ES B EN R
T IYe a199 19 4 ALLOY 600 IN LWR ENVIRONMENTS.
QuotenitJc Stainless Steel NUREG/CR 6335. FATIGUE STRAIN-LIFE BEHAVIOR OF CARBON U
/C 28: ADEOUACY OF THE 123-GROUP CROSS SECTION AND LOW ALLOY STEELS, AUSTENITIC STAINLESS STEELS, AND ALLOY 600 IN LWR ENVIRONMENTS ~
LIBRARY FOR CRITICALITY ANALYSES OF WATER-MODERATED URANIUM SYSTEMS.
BREATH Version 1 Cross-Section Library NUREG/CR 6333 BREATH VERSION 1.1 COUPLED FLOW AND NUREG/CR-6328: ADEQUACY OF THE 123-GROUP CROSS-SECTION ENERGY TRANSPORT IN POROUS MEDIA Simulator Desenption And LIBRARY FOR CRITICALITY ANALYSES OF WATER-MODERATED User Guide-URANIUM SYSTEMS.
BWR Damage Progression NUREG 1123 ROI: KNOWLEDGE AND ABILITIES CATALOG FOR NU-NUREG/CR-6150 V02:
SCDAP/RELAP/ MOD 3.1 CODE CLEAR POWER PLANT OPERATORS. BOLLING WATER REACTORS.
MANUALDamage Progression Model Theory.
Boating Water Reactor Decommissioning NUREG-1123 RO1: KNOWLEDGE AND ABILITIES CATALOG FOR NU-NUREG 1307 ROS: REPORT ON WASTE BURIAL CHARGES. Escalation CLEAR POWER PLANT OPERATORS BOILING WATER REACTORS.
Of Decommissioning Waste Disposal Costs At Low-Level Waste Bunal Facshties.
Boric Acid NUREG 1505 DRFT FC: A NONPARAMETRIC STATISTICAL METHOD-NUREG-1519. SURFACE INTERACTIONS OF CESIUM AND BORIC OLOGY FOR THE DESIGN AND ANALYSIS OF FINAL STATUS DE-ACID WITH STAINLESS STEEL COMMISSIONING SURVEYS Draft Report For Comment 21
22 Subject index NUREG 1506 DAFT FC: MEASUREMENT METHODS FOR RADIOLOGI-Fissiori Product CAL SURVEYS IN SUPPORT OF NEW DECOMMISSONING NUREG/CR4261: A
SUMMARY
OF ORNL FISSION PRODUCT RE-LEASE TESTS WITH RECOMMENDED RELEASE RATES AND DIF-CRITERIA. Draft Report For Comment.
NUREG 1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS FUSION COEFFICIENTS.
WITH TYPICAL RADIATON SURVEY INSTRUMENTS FOR VARIOUS CONTAMINANTS AND FIELD CONDITIONSDraft Report For Com.
Fitness Sr Duty NUREG/CR-5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER INDUSTRY. Annual Summary Of Program Performance Reports CY ment.
1994.
Degredat6cn NUREG 1522: ASSESSMENT OF INSERVICE CONDITIONS OF Fracture Mechanics SAFETY-RELATED NUCLEAR PLANT STRUCTURES.
N!! REG /CR 5944 V02: A CHARACTERIZATION OF CHECK VALVE NUREG/CR-5591 V05 N2: HEAVY SECTON STEEL IRRADIATION DEGRADATION AND FAILURE EXPERIENCE IN THE NUCLEAR PROGRAM Progress Report For Aprd 1994 Through September 1994.
POWER INDUSTRY.1991 Fastures.
NUREG/CR-6089: DETECTION OF PUMP DEGRADATION Gamma Knife NUREG/CR-6324: OUALITY ASSURANCE FOR GAMMA KNIVES.
Diffusion Coeffic6ent NUREG/CR4261: A
SUMMARY
OF ORNL FISSION PRODUCT RE-Gate Valve LEASE TESTS WITH RECOMMENDED RELEASE RATES AND DtF.
NUREG/CP-Of 46. PROCEEDINGS OF THE WORKSHOP ON GATE VALVE PRESSURE LOCKING AND THERMAL BINDING.
FUSION COEFFICIENTS-Health Physic Doelmeter NUREG/CR4354 DRF FC: PERFORMANCE TESTING OF ELECTRON-NUREG/CR4334: NEW SENSOR FOR MEASUREMENT OF LOW AIR IC PERSONAL DOSIMETERS. Draft Report For Comment-FLOW VELOCITY. Phase i Final Report.
Heat Pipe Phenomena Dusty Gas Model NUREG/CR-6347: MULTI-PHASE REACTIVE TRANSPORT THEORY.
NUREG/CR4347. MULTl-PHASE REACTIVE TRANSPORT THEORY.
Heavy Sect 6on Steel trrad6ation Program Embrittlement NUREG/CR-5591 V05 N2: HEAVY SECTION STEEL 1RRADIATION NUREG/CR-5591 VOS N2: HEAVY SECTION STEEL IRRADIATON PROGRAM. Progress Report For Apnl 1994 Through September 1994.
PROGRAM. Progress Report For Aprd 1994 Through September 1994.
Energy Tronoport High Integrity Software NUREG/CR4333: BREATH VERSION 1.1 COUPLED FLOW AND NUREG/CR4263 VO1: HIGH INTEGRITY SOFTWARE FOR NUCLEAR ENERGY TRANSPORT IN POROUS MEDIA Simulator Desenption And POWER PLANTS Candidate Guidehnes, Technical Basis And Research Needs Executwe Summa y User Guide-NUREG/CR4263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR NTS. Candidate Guidehnes, Technical Basis And Research R
N2 P1: ENFORCEMENT ACTIONS SIGNIFICANT AC.
Needs Mam Report.
TIONS RESOLVED,1NDIVIDUAL ACTIONS Ouarterly Progress O
R LE EA L NSE a
s ER Y
E TF Report.Apni-June 1995 NUREG 0940 V14 N2 P3: ENFORCEMENT ACTIONS. SIGNIFICANT AC.
High-Level Waste Repository TONS RESOLVED MATERIAL LICENSEES Ouarterly Progress NUREG/CR4351: REVIEW OF SCENARIO SELECTION APPROACHES FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL WASTE RE-NU 600 AL STATEMENT OF POLICY AND PROCEDURE POSITORIES AND RELATED ISSUES.
FOR NRC ENFORCEMENT ACTIONS. Enforcement Policy.
Human Fector Enforcement Pol 6ey NUREG/CP-0144 V01: A WORKSHOP ON DEVELOPING RISK ASSESS-NUREG-1600. GENERAL STATEMENT OF POLICY AND PROCEDURE MENT METHODS FOR MEDICAL USE OF RADIOACTIVE FOR NRC ENFORCEMENT ACTONS Enforcement Pohey.
MATERIAL. Summary.
NUREG/CP-0144 V02: A WORKSHOP ON DEVELOPING RISK ASSESS-EnytronmentalSimulation Approach MENT METHODS FOR MEDICAL USE OF RADIOACTIVE NUREG/CR-6351: REVIEW OF SCENARIO SELECTION APPROACHES MATERJALSupportog Documents.
FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL WASTE RE.
NUREG/CR4159 USING MICRO SAINT TO PREDICT PERFORMANCE POSITORIES AND RELATED ISSUES.
IN A NUCLEAR POWER PLANT CONTROL ROOM.A Test Of Vahdity And Feasibihty.
Environmental Traneport NUREG/CR4265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN NUREG/CR-6305: BLT EC (BREACH. LEACH, TRANSPORT, AND EOut.
RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF LIBRQin JHEhSTRG A FINITE-ELEMENT MODEL FOR ASSESS.
COMMISSION AND DEPENDENCIES.
ING "HE RELEASE OF GADIONUCLIDES FROM LOW-LEVEL WASTE DISPOSAL UNITS. Background, Theory, And Model Desenpt>on.
NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF REMOTE Equ66lbrNm Chemistry AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-NUREG/CR4305: BLT-EC (BREACH. LEACH, TRANSPORT, AND EQUI.
System lnteriaces, Procedures And Practices Training And Organization-LIBRIUM CHEMISTRY), A FINITE-ELEMENT MODEL FOR ASSESS.
al Prachces And Procedures.
ING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE NUREG/CR-6277 V01: HUMAN FACTORS EVALUATION OF TELE-DISPOSAL UNITS Background, Theory, And Model Desenption.
THERAPY, identification Of Problems And Alternatue Approaches.
NUREG/CR-6277 V02.
HUMAN FACTORS EVALUATION OF Examination TELETHERAPY.Functon And Task Analysis.
NUREG-1123 RO1: KNOWLEDGE AND ABILITIES CATALOG FOR NU-NUREG/CR 6277 V03.
HUMAN FACTORS EVALUATION OF CLEAR POWER PLANT OPERATORS: BOILING WATER REACTORS.
TELETHERAPY. Human-System Interfaces And Procedures.
NUREG/CR4277 V04: HUMAN FACTORS EVALUATION OF Failure Mode Analysis NUREG/CR4002:
RISK BASED MAINTENANCE TELETHERAPY. Training And Organizahonal Analysis.
NUREG/CR4277 VOS: HUMAN FACTORS EVALUATION OF MODELING Pnontirahon Of Maintenance importances And Ovantifica.
TELETHERAPY. Literature Rewsw.
bon Of Maintenance Effectueness Human Rollability NUREG/CR 6335: FATIGUE STRAIN LIFE BEHAVIOR OF CARBON NUREG/CR-6265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN Fettgue Design Curve RELtABILITY ANALYSIS WITH AN APPLICATON TO ERRORS OF AND LOW-ALLOY STEELS. AUSTENiTIC STAINLESS STEELS, AND COMMISSION AND DEPENDENCIES.
ALLOY 600 IN LWR ENVIRONMENTS.
Subject index 23 Hydraulle Characterization ING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE NUREG/CR-6356. HYDRAULIC CHARACTERIZATION OF HYDROTH-DISPOSAL UNITS Background. Theory, Ano Model Descnption.
ERMALLY ALTERED NOPAL TUFF.
Maintenance lofittrat6on Analysts NUREG/CR4002.
RISK-BASED MAINTENANCE NUREG/CR-6333: BREATH VERSION 1.1 COUPLFD FLOW AND MODELING Pnontization Of Maintenance importances And Quantifica.
ENERGY TRANSPORT IN POROUS MEDIA. Simulator Desenption And tion Of Maintenance Effectrveness.
User Guide.
Medical Device NUREG/CR 6323: RELATIVE RISK ANALYSIS IN REGULATING THE U G CR 6 1 V01, ROBUST ACCURATE, AND NON-CONTACTING VIBRATION MEASUREMENT SYSTEM Summary of Companson Meas-USE OF RADIATION-EMITTING MEDICAL DEVICES A Preliminary Ap-urements Of The Robust Laser interferometer And Typical Accelerome-placation.
N E R 313 V02: ROBUST, ACCURATE AND NON-CONTACTING e@ cal sadWntstra%n NUREG/CR-6277 V01: HUMAN FACTORS EVALUATION OF TELE.
VIBRATION MEASUREMENT SYSTEMS Supplemental Appendeces
" 2
^
And y Acce ero ter Syste s TELETHERAPY. Function And Task Analysis Instrumentation NUREG/CR 6277 V03 HUMAN FACTORS EVALUATION OF NUREG-1505 DAFT FC: A NONPARAMETRIC STATISTICAL METHOD.
TELETHERAPY. Human-System lnterfaces And Procedures.
OLOGY FOR THE DESIGN AND ANALYSIS OF FINAL STATUS DE.
NUREG/CR 6277 V04: HUMAN FACTORS EVALUATION OF COMMISSIONING SURVEYS Draft Report For Comment TELETHERAPY. Training And Organizational Analysis.
NUREG 1506 DAFT FC: MEASUREMENT METHODS FOR RADIOLOGl.
NUREG/CR 6277 VOS.
HUMAN FACTORS EVALUATION OF CAL SURVEYS IN SUPPORT OF NEW DECOMMISSIONING TELETHERAPY. Literature Review.
CRITERIA Draft Report For Comment.
NUREG-1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS Medical Ouality Management WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS NUREG/CR-6277 V01: HUMAN FACTORS EVALUATION OF TELE-CONTAMINANTS AND FIELD CONDITIONS Draft Report For Com.
THERAPY, identification Of Problems And Altematwe Approaches.
ment.
NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF TELETHERAPY. Function And Task Analysis.
Interface Theory 3.1 CODE TELETHERAPY Human-System Interfaces And Procedures.
NUREG/CR-6277 V03.
HUMAN FACTORS EVALUATION OF NUREG/CR-6150 V01:
SCDAP/RELAP5/ MOD MANUALinterface Theory NUREG/CR-6277 V04: HUMAN FACTORS EVALUATION OF Internal Event TELETHERAPY. Training And Organizational Analysis.
NUREG/CR 6277 V05: HUMAN FACTORS EVALUATION OF NUREG/CR-6143 V01: EVALUATION OF POTENTIAL SEVERE ACCl-TELETHERAPY Literature Review.
DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT GRAND GULF, UNIT 1. Summary Of Results.
Med cal Use NUREL/CP-0144 V01: A WORKSHOP ON DEVELOPING R!SK ASSESS-NUREG/CR-4667 V19 ENVIRONMENTALLY ASSISTED CRACKING IN MENT METHODS FOR MEDICAL USE OF RADIOACTIVE LIGHT WATER REACTORS. Semiannual Report.Aptd-September 1994.
02IA WORKSHOP ON DEVELOPING RISK ASSESS-NURE /
4 Legst issuances MENT METHODS FOR MEDICAL USE OF RADIOACTIVE NUREG-0750 V40.
NUCLEAR REGULATORY COMMISSION MATERIALSupporting Documents.
ISSUANCES. Opinions And Decissons Of The Nuclear Regulatory Com-m#ssion With Selected Orders Juty-December 1994 Microbial Degradation NUREG4750 V41 102 INDEXES TO NUCLEAR REGULATORY COM-NUREG/CR-6188 V02: MICROBIAL DEGRADATION OF LOW-LEVEL MISSION ISSUANCES January June 1995 RADIOACTIVE WASTE. Annual Report For FY 1994 NUREG4750 V41 N05: NUCLEAR REGULATORY COMMISSION IS-SUANCES FOR MAY 1995 Pages 321380.
NPROS NUREG 0750 V41 N06: NUCLEAR REGULATORY COMMISSION IS-NUREG/CR-5944 V02: A CHARACTER 12ATION OF CHECK VALVE SUANCES FOR JUNE 1995 Pages 381496.
DEGRADATION AND FAILURE EXPERIENCE IN THE NUCLEAR NUREG-0750 V42 N01: NUCLEAR REGULATORY COMMISSION IS-POWER INDUSTRY.1991 Fadures SUANCES FOR JULY 1995 Pages 145.
Light Water Reactor
~
NUREG/CR-4667 V19. ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CP-0142 V01: PROCEEDINGS OF THE 7TH INTERNATIONAL LIGHT WATER REACTORS. Semiannual Report.Apni-September 1994.
MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS (NURETH 7) Sessions 15.
Laner Tearing NUREG/CP-0142 V02: PROCEEDINGS OF THE 7TH INTERNATIONAL NUREG/CR4184: SEPARATE EFFECTS TESTING AND ANALYSES TO MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS INVESTIGATE LINER TEARING OF THE 1:16-SCALE REINFORCED (NURETH-7). Sessions 6-11.
CONCRETE CONTAINMENT BUILDING.
NUREG/CP0142 V03: PROCEEDINGS OF THE 7TH INTERNATIONAL MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS Liquid Effluent (NURETH-7). Sessions 1216 NUREG/CR-2907 V13. RADIOACTIVE MATERIALS RELEASED FROM NUREG/CP 0142 V04 PROCEEDINGS OF THE 7TH INTERNATIONAL NUCLEAR POWER PLANTS. Annual Report 1992.
MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS (NURETH-7). Sessions 17 24.
NUREG/CR4143 VOI: EVALUATION OF POTENTIAL SEVERE ACCI-New Sensor DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR-6334. NEW SENSOR FOR MEASUREMENT OF LOW AIR GRAND GULF, UNIT 1. Summary Of Results.
FLOW VELOCITY. Phase i Final Report.
Low-Anoy Steet NUREG/CR-6335: FATIGUE STRAIN-LIFE BEHAVIOR OF CARBON Nuclear Plant Safety System NUREG/CR-6263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR D OW LLO S S AU E TIC STAINLESS STEELS, AND POWER PLANTS. Candidate Guadelines Technical Basis And Research Needs Executwe Summary.
Lew4.evel Radioacthre Weste NUREG/CR-6263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR NOREG/CR-6188 V02: MICROBIAL DEGRADATION OF LOW-LEVEL POWER PLANTS Cand<date Guedehnes, Technscal Bases And Research RADIOACTIVE WASTE. Annual Report For FY 1994.
Needs Main Report.
Low-Level Weste D6aposal Nuclear Plant Structure NUREG/CR4305. BLT-EC (BREACH, LEACH, TRANSPORT, AND EQUI-NUREG 1522. ASSESSMENT OF INSERVICE CONDITIONS OF LIBRIUM CHEMISTRY), A FINITE-ELEMENT MODEL FOR ASSESS-SAFETY RELATED NUCLEAR PLANT STRUCTURES.
T 24 Subject index NUREG/CP W O V02:
SCDAP/RELAP/ MOD 3.1 CODE Nuclear Power Plant NUREG/CR4159: USING MICRO SAINT TO PREDICT PERFORMANCE MANUALDamage Progression Model Theorb IN A NUCLEAR POWER PLANT CONTROL ROOM.A Test Of Vahdity NUREG/CR4150 V03:
SCDAP/RELAP5/MOC 1
CODE MANUALUser's Guede And input Manual.
And Feasstwitty.
NUREG/CR 6150 V04:
SCDAP/RELAP5/ MOD 3.1 CODE
^ ^
G 0 42 V01: PROCEEDINGS OF THE 7TH INTERNATIONAL g,
MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS NUREG/CR4150 VOS:
SCDAP/RELAPS/ MOD 3.1 CODE MANUAL. Developmental Assessment VOYP OCEEDINGS OF THE 7TH INTERNATIONAL NUREG/CR4325: AN IMPLICIT STEADY STATE INITIAllZATION PACK.
N 4
MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS AGE FOR THE RELAP5 COMPUTER CODE.
(NURETH-7tSessions 6-11.
NUREG/CP 0142 V03: PROCEEDINGS OF THE 7TH INTERNATIONAL RELAP5/ MOD 3 Computer Code MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS NUREG/CR 5535 VOI: RELAP6/ MOD 3 CODE MANUAL. Code Structure.
(NURETH-7) Sessaons 1216.
NUREG/CP 0142 V04. PROCEEDINGS OF THE 7TH INTERP'ATIONAL System Models, And Solution Methods.
MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS NUREG/CR-5535 V02: RELAPS/ MOO 3 CODE MANUALUser4 Guide And input Requerements.
(NURETH-7). Sessions 17 24.
NUREG/CR4535 V04: RELAP5.
1 CODE MANUAL.Models And Nuclear Reguietory Research Correlations.
NUREGa266 V09, NRC SAFET* a SEARCH IN SUPPORT OF REGU*
NUREG/CR 5535 V05 R1: RELAP5/ MOD 3 CODE InANUALUser's LATION. FY 1994.
G m ne.
Nuclear Safety Research Rad 6ation Survey NUREG/CP-0148: TRANSACTIONS OF THE TWENTY THIRD WATER NUREG 1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS REACTOR SAFETY INFORMATION MEETING.
WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS CONTAMINANTS AND FIELD CONDITIONS Draft Report For Com-Operating Expertence NUiMG 1272 VOS NO2: OFF6CE FOR ANALYSIS AND EVALUATION OF ment.
OPERATIONAL DATA.1993 Annual Report. Nuclear Matenals.
NUREG/CR4089 DETECTION OF PUMP DEGRADATION.
Rad 6ation Therapy NUREG/CR 6323: RELATIVE RISK ANALYSIS IN REGULATING THE Orgeniash Chwt USE OF RADIATION EMITTING MEDICAL DEVICES A Prehminary Ap-NUREG4325 R18: U.S. NUCLEAR REGULATORY COMMISSION OR, GAN12ATION CHARTS AND FUNCTIONAL STATEMENTSJuly 23.
NU E H 6324: QUALITY ASSURANCE FOR GAMMA KNIVES.
Radioactive M"ortal Performance NLt EG/CR 6159. USING MICRO SAINT TO PREDICT PERFORMANCE NUREG/CP 0144 V01: A WORKSHOP ON DEVELOPING RISK ASSESS-IN A NUCLEAR POWER PLANT CONTROL ROOM A Test Of Validity MENT METHODS FOR MEDICAL USE OF RADIOACTIVE MATERIALSummary.
And Feasibihty.
NUREG/CP 0144 V02: A WORKSHOP ON DEVELOPING RISK ASSESS-NU R
EW OF SCENARIC SELECTION APPRCACHES M ERIA.
ng me ts FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL WASTE RE-NUREG/CR-2907 V13: RADIOACTIVE MATERIALS RELEASED FROM POSITORIES AND RELATED ISSUES.
NUCLEAR POWER PLANTS. Annual Report 1992.
Performance Testing Radiological Survey NUREG/CR-6354 DRF FC: PERFORMANCE TESTING OF ELECTRON.
NUREG 1506 DRFT FC: MEASUREMENT METHODS Fa RADIOLOGi-IC PERSONAL DOSIMETERS Drafi Report For Comment.
CAL SURVEYS IN SUPPORT OF NEW DECOMMISSIONING Petit 6one For Ru6emaking CRITERIA. Draft Report For Comment.
NUREG-0936 V14 N01: NRC TEGULATC AGENDA. Semiannual ReportJanuary June 1995.
Radionucl6de Migration NUREG/CR4305: BLT-EC (BREACH. LEACH. TRANSPORT, AND EQUI-LIBRIUM CHEMISTRY), A FINITE-ELEMENT MODEL FOR ASSESS.
N RE C 6333. BREATH VERSION 11 - COUPLED FLOW AND ING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE ENERGY TRANSPORT IN POROUS MEDIA Simulator Desenption And DISPOSAL UNITS Background, Theory, And Model Description.
User Ge Reactive transport Pressure Locking NUREG/CR-6347: MULTI-PHASE REACTIVE TRANSPORT THEORY.
NUREG/CP 0146 PROCFEDINGS OF THE WORKSHOP ON GATE VALVE PRESSURE LOEKING AND THERMAL BINDING.
Reactor Accident Pressure vessel NUREG/CR-6265: MUT.iDISCIPLINARY FRAMEWORK FOR HUM AN NUREG/CR-5591 VOS N2: HEAVY-SECTION STEEL IRRADIATION RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF PROGRAM Progress Report For Apnl 1994 Through September 1994 COMMISSION AND DEPENDENCIES.
Probabillet6c R6ek Assessment Reactor Compownt NUREG/CR4143 V01: EVALUATION OF POTENTIAL SEVERE ACCI-NUREG/CR-6002:
RISK BASED MAINTENANCE DENTS CUHING LOW POWER AND SHUTDOWN OPERATIONS AT MODELING.Pnontaation Of Maintenance importances And Quantifica-GRAND GULF, UNIT 1. Summary Of Results.
tion Of Maintenance Effectiveness.
Program Performance NUREG/CR 5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER Reactor Operator INDUSTRY. Annual Summary Of Program Performance Reports CY NUREG-1123 R01. KNOWLEDGE AND ABILITIES CATALOG FOR NU.
1 CLEAR POWER PLANT OPERATORS: BOILING WATER REACTORS.
1994.
Pump Reactor Safety NUREG/CR-6089. DETECTION OF PUMP DEGRADATON-NUREG/CR4265: MUL'lDISCIPLINARY FRAMEWORK FOR HUMAN RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF Ouellty Assurance COMMISSION AND DEPENDENCIES.
NUREG/CR4324:OUALITY ASSURANCE FOR GAMMA KNIVES.
Reactor Safety Research RELAP5 Computer Code NUREG/CR 6150 VOI:
SCDAP/R2 LAPS / MOD 31 CODE NUREG/CP-0148: TRANSACTIONS OF THE TWENTY THIRD *. VATER MANUAL. Interface Theory.
REACTOR SAFETY INFORMATION MEETING.
i Subject Index 25 Reguletlon Severe Accident NUREG/CR4323. RELATIVE RISK ANALYSIS IN REGULATING THE NUREG 1519 SURFACE INTERACTIONS OF CESIUM AND BORIC USE OF RADIA'ilON EMITTING MEDICAL DEVICES A Prehrranary Ap-ACID WITH STAINLESS STEEL.
plcation.
NUREG/CR-6143 V01: EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT Reguletory Agenda GRAND GULF, UNIT 1. Summary Of Results.
NUREG4936 V14 N01: NRC REGULATORY AGENDA. Semiannual Report, January-June 1995 Shutdown Operation NUREG/CR4143 V01: EVALUATION OF POTENTIAL SEVERE ACCl-DENTS DURING LOW NR AW SHMWN @NAS M U
304 V20 1: RE ULATORY AND TECHNICAL REPORTS GRAND W,N tSumman G Resuns, IABSTRACT INDEX JOURNAL). Compilation For First Guarter 1995. January-March.
Sond Waste D6sposal NUREG/CR-2907 V13' RADIOACTIVE MATERIALS RELEASED FROM papistory Document NUCLEAR POWER PLANTS. Annual Report 1992.
NUREG/CR-5973 A02: CODES AND STANDARDS AND OTHER GUID.
ANCE CITED IN REGULATORY DOCUMENTS Stein 6ees Steel NUREG-1519. SURFACE INTERACTIONS OF CESIUM AND BORIC Reinforced Concrete NUREG/CR4184' SEPARATE EFFECTS TESTING AND ANALYSES TO ACID WITH STAINLESS STEEL.
INVESTIGATE LINER TEARING OF THE 1:16-SCALE REINFORCED Standard Rev6ew Plan CONCRETE CONTAINMENT BU!LDING' NUREG/CR-5973 R02: CODES AND STANDARDS AND OTHER GUID-Release Rate ANCE CITED IN REGULATORY DOCUMENTS.
NUREWCR-6261: A
SUMMARY
OF ORNL FISSION PRODUCT RE-LEASE TESTS WITH RECOMMENDED RELEASE RATES AND DIF.
Steady-State initialltation FUSIOrd COEFFICIENTS.
NUREG/CR4325: AN IMPLICIT STEADY STATE INITIALIZATION PACK-AGE FOR THE RELAPS COMPUTER CODE.
Comote Aftertoading Brachytherapy NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF REMOTE Stress Corrosion Cracking AFTERLOADING BRACHYTHERAPY. Supporting Analyses ~* Human.
NUREG/CR-4667 V19: ENVIRONMENTALL) ASSISTED CRACKING IN l
System Interfaces, Procedures And Practices. Training And Organization-LIGHT WATER REACTORS. Semiannual Report. April-September 1994.
al Practres And Procedures.
Surface interaction Qeport To Congrose NUREG 1519: SURFACE INTERACTIONS OF CESIUM AND BORIC NUREG 0090 V17 N04: REPORT TO CONGRESS ON ASNORMAL ACID WITH STAINLESS STEEL OCCURRENCES October-December 1994.
NUREG 0090 V18 NOI: REPORT TO CONGRESS ON ABNORMAL Survey Design 7
OCCURRENCES. January-March 1995.
NUREG 1505 DAFT FC: A NONPARAMETRIC STATISTICAL METHOD-OLOGY FOR THE DESIGN AND ANALYSIS OF FINAL STATUS DE-NI'" A"'#
'I' COMMISSIONING SURVEYS Draft Report For Comment.
Y NUREG/CR4323: RELATIVE RISK ANALYSIS IN REGULATING THE NUREG 1506 DRFT FC: MEASUREMENT METHODS FOR RADIOLOGI-4 USE OF 9ADIATION-EMITTING MEDICAL DEVICES.A Prehminary Ap CAL SURVEYS IN SUPPORT OF NEW DECOMMISSIONING plication.
CRITERIA. Draft Report For Comment.
)
NUREG 1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS 1
R6ek Asseeement WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS NUREG/CP-0144 VOI: A WORKSHOP ON DEVELOPING RISK ASSESS.
CONTAMINANTS AND FIELD CONDITIONS. Draft Report For Com MENT METHODS FOR MEDICAL USE OF RADIOACTIVE MATERiAi *umma.
ment.
NUREG/CP 0144 Vo A WORKSHOP ON DEVELOPING RISK ASSESS-MENT METHODS FOR MEDICAL USE OF RADIOACTIVE TLD NUREG-0837 V15 NO2: NRC TLD DIRECT RADIATION MONITORING MATERIALSupporting Documents.
NETWORK Progress ReportApril-June 1995.
Robust Laser interferomver I
NUREGrCR4313 V0' MUST, ACCURATE, AND NON. CONTACTING Task Procedure VIBRATION MEAWy NT SYSTEM Summary of Companson Meas.
NUREG/CR4125 V03: HUMAN FACTORS EVALUATION OF REMOTE urements Of The Reu user Interferometer And Typcal Accelerome-AFTERLOAC"NG BRACHYTHERAPY. Supporting Analyses Of Human-ter Systems.
System interfaces. Procedures And Practices.Trairung And Orgaruzation-NUREG/CR4313 V02: ROBUST, ACCURATE. AND NON CONTACTING al Practces And Procedures.
VIBRATION MEASUREMENT SYSTEMS Supplemental Appendees Presenting Companson Measurements Of The Robust Laser interfer-Teletherapy ometer And Typcal Accelerometer Systems.
NUREG/CR-6277 V01: HUMAN FACTORS EVALUATION OF TELE-THERAPY. Identifcation Of Problems And Alternatnre Approaches.
Rules NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF NUREG 0936 V14 N01: NRC REGULATORY AGENDA. Semiannual TELETHERAPY. Function And Task Analysas.
Report. January-June 1995, NUREG/CR-6277 V03: HUMAN FACTORS EVALUATION OF TELETHERAPY. Human System interfaces And Procedures.
SCOAP NUREG/CR4277 V04: HUMAN FACTORS EVALUATION OF t
NUREG/CR-6150 V01:
SCDAP/RELAP5/ MOD 31 CODE TELETHERAPY. Training And Organizational Analysis.
II
' SCDAP/RELAP/ MOD 3.1 CODE NUREG/
TEL RAPY.Ut a e e j
MANUAL. Damage e ression Model T NUREG/CR-6150 V 3:
SCDAP/ RELA 5/ MOO 3.1 CODE Thermal Bind 6pg NUREG/CP 0146: PROCEEDINGS OF THE WORKSHOP ON GATE
)
NURE /
5 4
D ELAPS / MOD 3.1 CODE VALVE PetESSURE LOCKING AND THERMAL BINDING.
MANUALMATPRO-A Library Of Matenals Properties For Ught-Water.
Y NU CR4150 SCDAP/RELAP5/ MOD 3.1 CODE j
jC 0 2 V01: PROCEEDINGS Of THE 7TH INTERNATIONAL MANUALDevelopmental Assessment.
MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS Safeguards Summary Event List (NURETH-7). Sessions 15.
NUREG-0525 V02 R03: SAFEGUARDS
SUMMARY
EVENT LIST NUREG/CP4142 V02: PROCEEDINGS OF THE 7TH INTERNATIONAL (SSEL). January 1,1990 Through December 31,1994.
MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS (NURETH-7). Sessions 6-11.
Safety Messerch NUREG/CP 0142 V03: PROCEEDINGS OF THE 7TH INTERNATIONAL j
NUREG 1266 V09: NRC SAFETY RESEARCH IN SUPPORT OF REGO-MEETING ON NUCLE M REACTOR THERMAL HYDRAULICS LAT4ON - FY 1994.
(NURETH-7). Sessions 1216.
26 Subject index NUREG/CP4142 V04 PROCEEDINGS OF THE 71H INTERNATIONAL NUREG/CR-5535 V05 R1: RELAP5/ MOD 3 CODE MANUAL. User's MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS Gudehne (NURETH-7) Sesssons 17-24 NUREG/CR-5535 V01: RELAP5/ MOD 3 CODE MANUALCode Structure.
Unsaturated Rock System Models. And Solutxm Methods NUREG/CR-63b6 HYDRAULIC, CHARACTERIZATION OF HYDROTH-NUREG/CR.5535 V02: RELAP5/ MOD 3 CODE MANUALUser's Gude ERMALLY ALTERED NOPAL TUFF.
Ard input Requirements NUREG/GR 5535 V04. RELAP5/ MOD 3 CODE MANUAL Models And Uranium NUMG/CM328 AMOUAG & WE 1234RO@ @OSWCNN NU E /
535 VOS RI. RELAP5/ MOD 3 CODE MANUAL User's LIBRARY FOR CRITICALITY ANALYSES OF WATER MODERATED Gudehne' URANIUM SYSTEMS Thermocouple NUREG/CR 6334. NEW SENSOR FOR MEASUREMENT OF LOW AIR Vendor inspecten NUREG-0040 Vt9 NO2: LICENSEE CONTRACTOR AND VENDOR IN-FLOW VELOCfTY Pflase l F#nal Report SPECTION STATUS REPORT. Quarterly Report, Aprd-June 1995 (White Thermoluminescent Dos 6 meter Book)
NUREG-0837 V15 NO2. NRC TLD DIRECT RADIATION MONITORING NETWORK Progress Report Apr#-June 1995 Vibration Measurement System NUREG/CR-6313 V01. ROBUST, ACCURATE. AND NON-CONTACTING URE 4540 V17 N06 TtTLE LIST OF DOCUMENTS MADE PUBLICLY AV AILABLE. June 1-30.1995 7 N07 TiTtE LIST OF DOCUMENTS MADE PUBLICLY N E /R 313 V02 ROBUST, ACCURATE, AND NON-CONTACTING V
B E' y
'31' 99b VIBRATION MEASUREMENT SYSTEMS Suppl mental Appendices Presenting Companson Measurements Of The Robust Laser interfer-Transient Analysis NUREG/CR 5535 V01. RELAP5/ MOD 3 CODE MANUAL Code Structure, ometer And Typical Accelerometer Systems.
Systern Models, And Solution Methods NUREG/CR 5535 V02: RELAPS/ MOD 3 CODE MANUALUser's Gude Waste Burial NUREG-1307 R05. REPORT ON WASTE BURIAL CHARGES Escalation And input Requirements NUREG/CR-5535 V04 RELAP5/ MOD 3 CODE MANUAL Models And Of Decommissioning Waste Disposal Costs At Lo. Level Waste Burial Correlations Facihtees 1
. = _ =.
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.
ADVISORY COMMITTEE (S)
DIVISION OF SAFETY PROGRAMS (POST 870413)
ADVISORY COMMITTEE ON NUCLEAR WASTE NUREG/CP-0146 PROCEEDINGS OF THE WORKSHOP DN GATE NUREG 1423 V05. A COMPILATION OF REPORTS OF THE ADVISO*
VALVE PRESSURE LOCKING AND THERMAL BINDING.
RY COMMITTEE ON NUC EAR WASTE. July 1993 - June 1995 EDO. OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS S & PANEL (S{
ATOMIC SAFETY BOAR OPERATIONS BRANCH NU G 3 V06 AT SAFETY UCENSING BOARD SSEL January,19 Thro embe 94 PANEL BIENNIAL REPORT. Fiscal Years 1993 1994 NUREG/CR-6125 V03 HUMAN FACTOP.S. EVALUATION OF REMOTE AFTERLOADING BRACHYTHERAPY Supporting Analyses OFFICE OF EXECUTIVE DIREC10R FOR OPERATIONS (EDO)
Of Human-System Interfaces. Procedures And Practices, Training And REGION 1 (POST 820201)
NUREG-0837 V15 NO2' NRC TLD DIRECT RADIATION MONITORING Organizational Practces And Procedures NETWORK Progress
.Apnl-June 1995.
NUREG/CR-6277 VOI: HUMAN FACTORS EVALUATION OF TELE-OFC OF ENFORCEMENT ST 870413)
THERAPY. Identihcaton Of Problems And Alternative Approaches NUREG 0940 Vid N2 1; ENFORCEMENT ACTIONS SIGNIFICANT NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF ACTIONS RESOLVEDJNDIVIDUAL ACTIONS Quarterly Progress TELETHERAPY. Function And Task Analysis.
Report.Apnadune 1995 NUREG/CR 6277 V03. HUMAN FACTORS EVALUATION OF TELE-NUREG-0940 V14 N2 P2. ENFORCEMENT ACTIONS SIGNIFICANT THERAPY Human-System interfaces And Procedures ACTIONS RESOLVED, REACTOR LICENSEES.Quarterty Progress NUREG/CR-6277 V04 HUMAN FACTORS EVALUATION OF Report,Apnt-June 1995 TELETHERAPY.Tranng And Organizatonal Analysis.
NUREG-0940 Vid N2 P3. ENFORCEMENT ACTIONS. SIGNIFICANT NUREG/CR-6277 V05: HUMAN FACTORS EVALUATION OF ACTIONS RESOLVED MATERIAL tlCENSEES Ouarterly Progress TELETHERAPY Literature Review.
Report.Apnadune 1995.
NUREG-1600: GENERAL STATEMENT OF POLICY AND PROCE-EDO. OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)
DURE FOR NRC ENFORCEMENT ACTIONS Enforcement Policy-OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 941217)
OFC OF PERSONNEL (POST 870413)
NUREG 1266 V09 NRC SAFETY RESEARCH IN SUPPORT OF REG-NUREG-0325 R18. U S NUCLEAR REGULATORY COMMISSION OR-ULATION. FY 1994 GANIZATION CHARTS AND FUNCTIONAL STATEMENTSJuly 23.
DIVISION OF REGULATORY APPLICATIONS (POST 941217) 1995.
NUREG 1307 ROS REPORT ON WASTE BURIAL 8 '*"
"O EDO-OFFICE OF ADMINISTRATION PRE 870413 & POST 890205)
NU 15 5 T
ARAMETRIC STATISTICAL METH-N E 114 1
U LEAR REG T RY OMMISSION ODOLOGY FOR THE DESIGN AND ANALYSIS OF FINAL STATUS 1994 ANNUAL REPORT.
DIVISION OF FREEDOM OF INFORMATION & PUBLICATIONS SERV.
DECOMMISSIONING SURVEYS Draft Report For Comment.
NUREG-1506 DRFT FC: MEASUREMENT METHODS FOR RADIO-ICES (POST 940714 NUREG 0304 V20 N01: REGULATORY AND TECHNICAL REPORTS LOGICAL SURVEYS IN SUPPORT OF NEW DECOMMISSIONING (ABSTRACT INDEX JOURNAL). Compilaton For First Quarter CRITERIA. Draft Report For Comment.
NUREG 1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS 1995. January. March.
NUREG 0540 V17 N05 TITLE LIST OF DOCUMENTS MADE PUBLIC-WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR VARI.
LY AVAILABLE May 1 31,1995 OUS CONTAMINANTS AND FIELD CONDITIONS. Draft Report For NUREG-0540 V17 N06-TITLE LIST OF DOCUMENTS MADE PUBLIC-Comment.
LY AVAILABLE. June 1 30,1995.
DIVISION OF SYSTEMS TECHNOLOGY (POST 941217)
NUREG 0540 V17 N07. TITLE LIST OF DOCUMENTS MADE PUBLIC-NUREG-1519. SURFACE INTERACTIONS OF CESIUM AND BORIC LY AVAILABLE. July 1 31,1995.
ACID WITH STAINLESS STEEL.
NUREG-0750 V40 NUCLEAR REGULATORY COMMISSION CONTROL, INSTRUMENTATION & HUMAN FACTORS BRANCH (POST lSSUANCES Opinons And Decisions Of The Nuclear Regulatory 941217)
Commisson With Selected Orders July-December 1994.
NUREG/CA-6125 V03: HUMAN FACTORS EVALUATION OF NUREG-0750 V41102: INDEXES TO NUCLEAR REGULATORY COM-REMOTE AFTERLOADING BRACHYTHERAPY. Supporting Analyses hA E LATORY COMMISSION IS-NU 4 N05 N Org ni at Pr etc s And Proc ures NUREG O 41 N06 C
REGU TORY COMMISSION IS-
^
SUANCES FOR JUNE 1995 Pa s 381-496 NU CR 277 V01 HUMAN FACTORS EVALUATION OF TELE-SUAN F
JUL 19 Pa a 4 THERAPY. Identificaton Of Problems And Alternative Approaches.
NUREG 0936 V14 N01: NRC EGULATORY AGENDA. Semiannual NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF Report January-June 1995.
TELETHERAPY Functon And Task Analysis.
EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR-6277 V03: HUMAN FACTORS EVALUATION OF TELE-THERAPY. Human-System interfaces And Procedures.
DATA OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA, DI.
NUREG/CR-6277 V04 HUMAN FACTORS EVALUATION OF RFCTOR TELETHERAPY.Tranng And Organizatonal Analysis.
NUREG4090 V17 N04 REPORT TO CONGRESS ON ABNORMAL NUREG/CR-6277 V05-HUMAN FACTORS EVALUATION OF OCCURRENCES October-December 1994 TELETHERAPY. Literature Review.
NUREG4090 V18 N01: REPORT TO CONGRESS ON ABNORMAL PROBABILISTIC RISK ANALYSIS BRANCH (POST 941217)
OCCURRENCES. January March 1995.
NUREG/CR-6265. MULTIDISCIPLINARY FRAMEWORK FOR HUMAN NUREG-1272 V08 NO2: OFFICE FOR ANALYSTS AND EVALUATION RELIABILITY ANALYSIS WITH AN APPLICAllON TO ERRORS OF OF OPERATIONAL DATA.1993 Annual Report - Nuclear Matenais.
^OMM!SSION AND DEPENDENCIES.
1 i
27
1 28 NRC Originating Organization Index (Staff Reports)
EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST $00428)
NUREG-1123 ROI: KNOWLEDGE AND ABILITIES CATALOG FOR OFFICE Or NUCLEAR REACTOR REGULATION (POST 941001)
NUCLEAR POWER PLANT OPERATORS. BOILING WATER REAC-NUREG@40 V19 NO2: LICENSEE CONTRACTOR AND VENDOR IN-TORS.
SPECTION STATJS F1 PORT. Quartetty Report. April June NUREG-1522; ASSESSMENT OF INSERVICE CONOfTIONS OF 1995 (WNto Book)
SAFETY-RELATED NUCLEAR PLANT STRUCTURES.
N
NRC Originating Organization Index (International Agreements) f This index lists those NRC organizations that have published international agreement re-i i
ports. The index is arranged alphabetically by major NRC organizations fices) and then by subsections of these (e.g., divisions, branches) where (e.g., program of-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.
)
i Thai were no NUREG/lA reports publHhed during this quarter 29
^
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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) end 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) prepared by that organi-zation. If further information is needed, refer to the main citation by the NUREG/CR number.
u EDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG/CR-5535 V02: REL/PS/ MOD 3 CODE MANUAL User's Guide OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS And inpu1 Requirements NUREG/CR-6328 ADEQUACY OF THE 123-GROUP CROSS-SEC.
NUREG/CS5535 V04: RELAP5/ MOD 3 CODE MANUAL.Models And TlON LIBRARY FOR CRITICALITY ANALYSES OF WATER-MODER-Correlations.
ATED URANIUM SYSTEMS.
NUREG/CR 5535 V05 R1: RELAP5/ MOD 3 CODE MANUAL. User's DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST Guidehne.
870729)
NUREG/CR-6002:
RISK-BASED MAINTENANCE NUREG/CR4323: RELATIVE RISK ANALYSIS IN REGULATING THE MODEUNG.Pnontization Of Maintenance importances And Quantifi-USE OF RADIATION-EMITTING MEDICAL DEVICES A Prehminary cation Of Maintenance Effectveness Apphcation.
NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF NUREG/CR4324: QUALITY ASSURANCE FOR GAMMA KNIVES.
REMOTE AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-System interfaces.Procedares And Practices, Training And EDO. OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)
Organizational Practices And Procedures.
OlVISION OF ENGINEERING TECHNOLOGY (POST 941217)
NUREG/CR-6143 V01: EVALUATION OF POTENTIAL SEVERE ACCl-NUREG/CR-4667 V10 ENVIRONMENTALLY ASSISTED CRACKING DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT IN LIGHT WATER REACTORS. Semiannual Report. April-September GRAND GULF. UNIT 1 Summary Of Results.
N G/CR 5591 V05 N2: HEAVY SECTION STEEL IRRADIATION MANUALi t ace Th PROGRAM Progress Report For April 1994 Through September NUREG/CR-6150 V02:. SCDAP/RELAP/ MOD 3.1 CODE Vb YCA RE 5/ MOD 3.1 CODE N
G/CR-5944 V02: A CHARACTERl2ATION OF CHECK VALVE NUREG/ 61 DEGRADATION AND FAILURE EXPERIENCE IN THE NUCLEAR M ANUAL User's Guide And input Manual.
POWER INDUSTRY.1991 Failures.
NUREG/CR-6150 V04:
SCDAP/RELAP5/ MOD 3.1 CODE NUREG/CR-6089 DETECTION OF PUMP DEGRADATION MANUAL.MATPRO.-A Library Of Matenals Properties For Light-NUREG/CR 6100: GATE VALVE AND MOTOR. OPERATOR R E' Water-Reactor Accident Analysis.
SEARCH FINDINGS NUREG/CR-6150 V05:
SCDAP/RELAP5/ MOD 3.1 CODE NUREG/CR6184 SEPARATE EFFEC 1S TESTING AND ANALYSES MANUALDevelopmental Assessment.
TO INVESTIGATE LINER TEARING OF THE 116-SCALE REIN-NUREG/CR-6159-USING MICRO SAINT TO PREDICT PERFOAM-FORCED CONCRETE CONTAINMENT BUILDING-ANCE IN A NUCLEAR POWER PLANT CONTROL ROOM.A Test Of NUREG/CR-6313 V01. ROBUST, ACCURATE, AND NON-CONTACT-Vahdity And Feasibehty.
ING VIBRATION MEASUREMENT SYSTEM Summary of Companson NUREG/CR-6261: A
SUMMARY
OF ORNL FISSION PRODUCT RE-Measurements Of The Robust Laser Interferometer And Typical Ac-LEASE TESTS WITH RECOMMENDED RELEASE RATES AND DIF.
celerometer Systems-FUSION COEFFICIENTS.
NUREG/CR4313 V02. ROBUST, ACCURATE, AND NON-CONTACT
- NUREG/CR-6263 V01: MIGH INTEGRITY SOFTWARE FOR NUCLEAR ING VIBRATION MEASUREMENT SYSTEMS Supplemental Append 8-POWER PLANTSCandidate Guidehnes, Technical Basis And Re-ces Presenting Companson Measurements Of The Robust Laser in-search Needs Executive Summary terferometer And Typer al Accelerometer Systems.
NUREG/CR4263 V02: HIGH INTEGRITY SOFTWARE FOR NUCLEAR NUREG/CR4335: FATlGUE STRAIN-UFE BEHAVIOR OF CARBON POWER PLANTS Candidate Guidehnes, Technical Basis And Re-AND LOW-ALLOY STEELS, AUSTENITIC STAINLESS STEELS, search Needs Main Report.
AND ALLOY 600 IN LWR ENVIRONMENTS NUREG/CR-6265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN DIVISION OF REGULATORY APPUCATIONS (POST 941217)
REUABILITY ANALYSIS WITH AN APPUCATION TO ERRORS OF NUREG/CR6168 V02: MICROBIAL DEGRADATION OF LOW-LEVEL COMMISSION AND DEPENDENCIES.
RADIOACTIVE WASTE. Annual Repor1 For FY 1994 NtAEG/CR-6277 VOI: HUMAN FACTORS EVALUATION OF TELE-NUREG/CR 6305. BLT EC (BREACH. LEACH, TRANSPORT, AND THERAPY. Idontification Of Problems And Alternative Approaches.
EOUluBRIUM CHEMISTRY), A FINITE ELEMENT MODEL FOR AS-NUREG/CR-6277 V02: HUMAN FACTORS EVALUATION OF SESSING THE RELEASE OF RADIONUCUDES FROM LOW LEVEL TELETHERAPY. Function And Task Analysis.
WASTE DISPOSAL UNITS. Background. Theory And Model Descnp-NUREG/CR4277 V03: HUMAN FACTORS EVALUATION OF TELE-tion THERAPY. Human-System Interfaces And Procedures.
NUREG/CR4333. BREATH VERSION 1.1 COUPLED FLOW AND NUREG/CR 6277 V04. HUMAN FACTORS EVALUATION OF ENERGY TRANSPCRT IN POROUS MEDIA. Simulator Descnption TELETHERAPY. Training And Organizational Analysis.
And User Guide.
NUREG/CR-6277 V05: HUMAN FACTORS EVALUATION OF NUREG/CR4334: NEW SENSOR FOR MEASUREMENT OF LOW AIR TELETHERAPY. Literature Review.
FLOW VELOCITY. Phase i Final Report.
NUREG/CR4325: AN iMPUCIT STEADY STATE INITIAUZATION NUREG/CR-6347: MULTI-PHASE REACTIVE TRANSPORT THEORY.
PACKAGE FOR THE PELAP5 COMPUTER CODE.
NUREG/CR 6351: REVIEW OF SCENARIO SELECTION APPROACH-ES FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL WASTE EDO - OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)
REPOSITORIES AND RELATED ISSUES.
OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)
NUREG/CR-6354 DRF FC: PERFORMANCE TESTING OF ELEC.
NUREG/CR-2907 V13. RADIOACTIVE MATERIALS RELEASED FROM TRONIC PERSONAL DOSIMETERS Draft Report For Comment.
NUCLEAR POWER PLANTS. Annual Report 1992.
NUREG/CH4356. HYDRAUUC CHARACTERIZATION OF HYDROTH.
NUREG/CR-5756 V05: FITNESS FOR DUTY IN THE NUCLEAR ERMALLY ALTERED NOPAL TUFF.
POWER INDUSTRY. Annual Summarv Of Program Performance Re-OlvlSION OF SYSTEMS TECHNOLOGY (POST 941217) ports CY 1994.
NUREG/CR-5535 V01: RELAP5/ MOD 3 CODE MANUAL. Code Strue.
NUREG/CR-5973 R02: CODES AND STANDARDS AND OTHER ture, System Models, And Solution Methods.
GUIDANCE CITED IN REGULATORY DOCUMENTS.
31
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8 E
Contractor Index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation, Listed below each contractor are the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the main citation by the NUREG/CR number.
d AMERICAN NUCLEAR SOCIETY CALIFORNIA, UNIV. OF SAN DIEGO, CA NUREG/CP 0142 V01: PROCEEDINGS OF THE 7TH INTERNATIONAL NUREG/CR-6125 V03: HUMAN FACTORS EVALUATION OF REMOTE MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS AFTERLOADING BRACHYTHERAPY. Supporting Analyses Of Human-(NURETH-7) Sessions 15.
System Interfaces. Procedures And Practices, Training And Organization-NUREG/CP 0142 V02; PROCEEDINGS OF THE 7TH INTERNATIONAL al Practices And Procedures.
MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS (NURETH-7) Sessions 6-11.
CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES NUREG/CP-0142 V03: PROCFEDINGS OF THE 7TH INTERNATIONAL NUREG/CR 6347: MULTI-PHASE REACTIVE TRANSPORT THEORY.
MEETING ON NUCLEAR REACTOR THERMAL-HYDRAULICS (NURETH-7) Sessions 12-16.
COMPUTER SIMULATION & ANALYSIS,INC.
NUREG/CP-0142 V04. PROCEEDINGS OF THE 7TH INTERNATIONAL NUREG/CR4325. AN IMPLICIT STEADY STATE INITIAll2ATION PACK.
MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS AGE FOR THE RELAP5 COMPUTER CODE.
(NURET47) %ssions 17 24-EARTHLINGS COTTAGE ANALYSIS & MEASUREMENT SERVICES CORP.
REG /CR-6354 DRF FC: PERFORMANCE TESTING OF ELECTRON-NUREG/CR-6334. NEW SENSOR FOR MEASUREMENT OF LOW AIR NU,C PERSONAL DOSIMETERS Draft Report For Comment.
FLOW VELOCITY. Phase 1 Final Report.
ENERGY, DEPT.0F, ENVIRONMENTAL MEASUREMENTS LABORATORY NUREG 1505 DRF1 FC: A NONPARAMETRIC STATISTICAL METHOD-CR 4t;67 V 9 L V R ENTALLY ASSISTED CRACKING IN OLOGY FOR THE DESIGN AND ANALYSIS OF FINAL STATUS DE-LIGHT WATER REACTORS. Semiannual Report.Apni-September 1994 NUREG/CR-6335 FATIGUE STRAIN-LIFE BEHAVIOR OF CARBON COMMISSIONING SURVEYS. Draft Report For Comment.
NUREG-1506 DRFT FC: MEASUREMENT METHODS FOR RADIOLOGi-AND LOW ALLOY STEELS. AUSTENITIC STAINLESS STEELS, AND CAL SURVEYS IN SUPPORT OF NEW DECOMM!SSIONING ALLOY 600 IN LWR ENVIRONMENTS.
CRITERIA Draft Report For Comment.
CATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST LABORATORY EPOCH ENGINEERING. INC.
NUREG/CR-5758 V05 FITNESS FOR DUTY IN THE NUCLEAR POWER NUREG/CR4313 V01: ROBUST, ACCURATE, AND NON-CONTACTING INDUSTRY. Annual Summary Of Program Performance Reports CY VlBRATION MEASUREMENT SYSTEM Summary of Compenson Maas-1994 urements Of The Robust Laser Interferometer And Typical Accelerome.
NUREG/CR-5973 R02. CODES AND STANDARDS AND OTHER GUID-ter Systems.
ANCE CITED IN REGULATORY DOCUMENTS NUREG/CR-6313 V02: ROBUST, ACCURATE, AND NON-CONTACTING NURE1/CR4354 DAF FC: PERFORMANCE TESTING OF ELECTRON-VlBRATION MEASUREMENT SYSTEMS Supplemental Appendices IC PERSONAL DOSIMETERS. Draft Report For Comment-Presentmg Companson Measurements Of The Robust Laser interfer-
' Y BATTELLE SEATTLE RESEARCH CENTER a
NUREG/CR-5758 V05: FITNESS FOR DUTY IN THE NUCLEAR POWER GEORGE RICE & ASSOCIATES INDUSTRY. Annual Summary Of Program Performance Reports CY NUREG/CR4356 HYDRAULIC CHARACTERIZATION OF HYDROTH-188#
ERMALLY ALTERED NOPAL TUFF.
j' BETA CORP, INTERNATIONAL HUuHES TRAINING,INC[ HUMAN FACTORS EVALUATION OF TELE-NUREG/CR4351: REVIEW OF SCENARIO SELECTION APPROACHES NUREG/CR4277 V01 FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL WASTE RE-THERAPY. ldentification Of Problems And Alternative Approaches.
POSITORIES AND RELATED ISSUES.
NUREG/CR4277 V02: HUMAN FACTORS EVALUATION OF TELETHERAPY Fwiction And Task Analysis.
BROOKHAVEN NATIONAL LABORATORY NUREG 1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS NUREG/CR-6277 V03.
HUMAN FACTORS EVALUATION OF WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS TELETHERAPY. Human-System interfaces And Procedures.
NUREG/CR 6277 V04.
HUMAN FACTORS EVALUATION OF CONTAMINANTS AND FIELD CONDITIONS Draft Report For Com-TELETHERAPY. Training And Organizational Arulysis.
ment NUREG/CP 0148 TRANSACTIONS OF THE TWENTY THIRD WATER NUREG/CR4277 V05: HUMAN FACTORS EVALUATION OF REACTOR SAFETY INFORMATION MEETING TELETHERAPY. Literature Review.
NUREG/CR-2907 V13: RADIOACTIVE MATERIALS RELEASED FROM IDAHO NATIONAL ENGINEERING LABORATORY NUCLEAR POWER PLANTS Annual Report 1992.
NUREG/CR 6002:
RISK BASED MAINTENANCE NUREG/CP-0144 V01: A WORKSHOP ON DEVELOPING RISK ASSESS-
)
MODELING.Pnontizabon Of Maintenance importances And Quantifica-MENT METHODS FOR MEDICAL USE OF RADIOACTIVE j
toon Of Maintenance Effectiveness.
MATERIAL. Summary NUREG/CR4265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN NUREG/CP 0144 V02: A WORKSHOP DN DEVELOPING RISK ASSESS-RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF MENT METHODS FOR HEDICAL USE OF RADIOACTIVE i
I COMMISSION AND DEPENDENCIES.
MATERIALSupporting Documents.
NUREG/CR-6305: BLT-EC (BREACH, LEACH, TRANSPORT, AND EQUl-NUREG/CR 5535 V01. RELAP5/ MOD 3 CODE MANUAL. Code Structure, LIBRIUM CHEMISTRY), A FINITE ELEMENT MODEL FOR ASSESS-System Models. And Solution Methods.
ING THE RELEASE OF RADIONUCLIDES FROM LOW LEVEL WASTE NUREG/CR-5535 V02: RELAP5/ MOD 3 CODE MANUAL. User's Guide DISPOSAL UNITS Background, Theory, And M xlel Desenption.
And input Requirements.
NUREG/CR-5535 V04. RELAPS/ MOD 3 CODE MANUAL.Models And CAUFORNIA STATE UNfVERSITY AT FRESNO Correlations.
NUf1EG/CR4305: BLT EC (BREACH, LEACH, TRANSPORT, AND EOul-NUREG/CR-5535 VOS R1: RELAPS/ MOD 3 CODE MANUALUser's LIBRIUM CHEMISTRY), A FINITE-ELEMENT MODEL FOR ASSESS-Guidehne.
ING THE RELEASE OF RADIONUCLIDES FROM LOW-LEVEL WASTE NUREG/CR-6100: GATE VALVE AND MOTOR-OPERATOR RESEARCH DISPOSAL UNITS. Background. Theory, And Model Desenptort FINDINGS.
l 1
33
34 Contractor Index NUREG/CR4150 VOI:
SCDAP/RELAPS/ MOD 3.1 CODE OAK RIDGE NATIONAL LABORATORY MANUALinterf ace Theory.
NUREG/CR-5591 V05 N2: HEAVY-SECTION STEEL IRRADIATON NUREG/CR-6150 V02:
SCDAP/RELAP/ MOD 3.1 CODE PROGRAM Progress Report For Agn'i 1994 Through September 1994.
NUREG/CR-5944 V02: A CHARAwERIZATION OF CHECK VALVE MANUAL. Damage Progression Model Theory.
NUREG/CR4150 V03:
SCDAP/RELAPS/ MOD 3.1 CODE DEGRADATION AND FAILURE EXPERIENCE IN THE NUCLEAR POWER INDUSTRY.1991 Failures.
MANUALUser's Guide And input Manual.
F PUM GR A y@f[hTR NUREG/CR 6150 V04:
SCDAP/RELAP5/ MOD 3.1 CODE MANUAL.MATPRO--A Library Of Matenals Properties For Light-Water-LEASE TESTS WITH RECOMMENDED RELEASE RATES AND DIF.
Reactor Accident Analysas~
FUSION COEFFICIENTS NUREG/CR-6150 V05.
SCDAP/RELAP5/ MOD 3.1 CODE NUREG/CR-6328. ADEOUACY OF THE 123-GROUP CROSS-SECTION MANUAL.Dovelopmental Assessment.
LIBRARY FOR CRITICALITY ANALYSES OF WATER-MODERATED NUREG/CR4188 V02: MICROBIAL DEGRADATION OF LOW-LEVEL URANIUM SYSTEMS.
RADIOACTIVE WASTE. Annual Report For FY 1994.
PACIFIC SCIENCE & ENGINEERING GROUP,INC.
JOHN WREATHALL & CO.,INC-NUREG/CR4125 V03: HUMAN FACTORS EVALUATON OF REMOTE NUREG/CR 6265. MULTIDISCIPLINARY FRAMEWORK FOR HUMAN AFTERLOADING BRACHYTHERAPY. Supporting t,nalysee Of Human.
RELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF System Interfaces. Procedures And Practices. Training And Organization.
COMMISSION AND DEPENDENCIES.
al Practices And Procedures.
LAWRENCE LIVERMORE NATIONAL LABORATORY PLC,INC. (FORMERLY PICKARD, LOWE & GARRICK,INC.)
NUREG/CR-6265 MULTIDISCIPLINARY FRAMEWORK FOR HUMAN NUREG/CR4323: RELATIVE RISK ANALYSIS IN REGULATING THE
' ELIABILITY ANALYSIS WITH AN APPLICATION TO ERRORS OF H
USE OF RADIATION-EMITTING MEDICAL DEVICES.A Preliminary Ap.
COMMISSION AND DEPENDENCIES.
plication.
NUREG/CR4324: OVALITY ASSURANCE FOR GAMMA KNIVES.
SANDIA NATIONAL LABORATORIES NUREG/CR4143 Vot: EVALUATION OF POTENTIAL SEVERE ACCI-MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE, MA DENTS DURING LOW POWER AND SHUTDOWN OPERATIONS AT NUREG/CR.6305: BLT-EC (BREACH, LEACH. TRANSPORT. AND EQUI-GRAND GULF, UNIT 1. Summary Of Results.
LIBRIUM CHEMISTRY) A FINITE ELEMENT MODEL FOR ASSESS-NUREG/CR4184: SEPARATE EFFECTS TESTING AND ANALYSES TO ING THE RELEASE OF RADIONUCLIDES FROM LOW LEVEL WASTE INVESTIGATE LINER TEARING OF THE 1:16-SCALE REINFORCED DISPOSAL UNITS.Bacitground. Theory. And Model Desenption.
CONCRETE CONTAINMENT BUILDING.
MICRO ANALYSIS & DESIGN,INC.
SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY NUREG/CR4159: USING MICRO SAINT TO PREDICT PERFORMANCE SCIENCE APPLICATIONS, IN A NUCLEAR POWER PLANT CONTROL ROOM.A Test Of Validity NUREG/CR-6002:
RISK-BASED MAINTENANCE And Feasibility.
MODELING Pnontization Of Maintenance importances And Quantifica-tion Of Maintenance Effectiveness.
MITRE CORP.
NUREG/CR.6265: MULTIDISCIPLINARY FRAMEWORK FOR HUMAN NUREG/CR 6263 V01: HIGH INTEGRITY SOFTWARE FOR NUCLEAR RELIABILITY ANALYSIS WifH AN APPLICATION TO ERRORS OF POWER PLANTS. Candidate Guidelines. Technical Basis And Research COMMISSION AND DEPENDENCIES.
Needs. Executive Summary' INTEGRITY SOFTWARE FOR NUCLEARSOUTHWEST RESEARCH INSTITUrE NUREG/CR-6263 V02: HIGH NUREG/CR4333 BREATH VERS!ON 1.1 - COUPLED FLOW AND POWER PLANTS Candidate Guidelines, Technical Basis And Research ENERGY TRANSPORT IN POROUS MEDIA.S4mulator Description And Needs Main Report.
User Guide NUREG/CR4347. MULTI-PHASE REACTIVE TRANSPORT THEORY.
OAK RIDGE ASSOCIATED UNIVERSITIES NUREG/CR4351: REVIEW OF SCENARIO SELECTION APPROACHES NUREG-1507 DRFT FC: MINIMUM DETECTABLE CONCENTRATIONS FOR PERFORMANCE ASSESSMENT OF HIGH-LEVEL WASTE RE-WITH TYPICAL RADIATION SURVEY INSTRUMENTS FOR VARIOUS POSITORIES AND RELATED ISSUES.
CONTAMINANTS AND FIELD CONDITIONS. Draft Report For Com-NUREG/CR-6356. HYDRAIJLIC CHARACTERIZATION OF HYDROTH-rr mt.
ERMALLY ALTERED NOPAL TUFF.
International Organization Index This index lists, in alphabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation. Listed below each country and per-forming organization are the NUREG/lA numbers and titles of their reports, if further infor-mation is needed, refer to the main citation by the NUREG/lA number.
There were no NUREG/lA reports published during this quarter.
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Licensed Facility Index This index lista the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number cnd followed by the report number. If further information is needed, refer to the main citation by the NUREG number.
2 416 Grand gun Nudow Stahon,[ht 1. M smsw NUREG/CR4143 V01 Power & Lght Co.
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NRC FORM 336 U.3. NUCLEAR REGULATORY COMMISSION
- 1. REPORT NUMBEl4 (2-49) gAxigned ty NRC, /W Vol.,
NRCM 1102, upp., Rev., and Mdendum Nurn-32ci, 3202 BIBLIOGRAPHIC DATA SHEET t*'* - " ""v l (See instructims on the rev.rs.)
NUREG-0304 Vol. 20, No. 3
- 2. mLE AND SUBmLE
- 3. DATE REPORT PUBUSHED Regulatory and 'Ibchnical Reports (Abstract Index Journal)
MONTH YEAR Compilation for Third Quarter 1995 January 1996 July-September
- 4. nu OR oRANT NuusER
- b. AUTHOH(b)
- 6. TYPE OF REPORT Reference
- r. PERIOD COVERED (inclusive Dates)
July-September
- 8. PERFORMING OHGAN!ZATION - NAME AND ADDRESS (if NRC, provide D#viskan Office or Region, U.S. Nuclear Regu;atory Commission, and mtiling 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
- 9. GPONSCRING OHGANIZATlON - NAME AND ADDRESS (if NRC, type "Same as above*; it contractor, prov6de NRC DMsion. Oft:ce or Region, U.S. Nuclear Regulatory Commission, and malling address.)
Same as 8, above.
- 10. GUPPLEMENTARY NOTES
- 11. ABSTRACT (200 we s or less)
This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceed-ings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.
I
- 12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.)
- 13. AVAILABILITY STATEMENT Unlimited
- 14. SECURITY CLASSIFICATION i
compilation abstract index (Thas Page)
Unclassified (This Report)
Unclassified
- 15. NUMBER OF PAGES
- 16. PRICE NRC FORM 335 (2-89)
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