ML20117J243
| ML20117J243 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1996 |
| From: | NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V21-N02, NUREG-304, NUREG-304-V21-N2, NUDOCS 9609100247 | |
| Download: ML20117J243 (42) | |
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Vol. 21, No. 2 i
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Regulatory and Technical Reports l (Abstract Index Journal)
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Compilation for i
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AVAILABILITY NOTICE i
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 i
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,
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circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu-ments and correspondence.
The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-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, forerunner 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 Administret.on, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washingwn 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 Broadway, New York, NY 10018-3308.
r NUREG-0304 Vol. 21, No. 2 Regulatory and Technical Reports (Abstract Index Journal)
Compilation for Second Quarter 1996 April-June Date Published: August 1996 M. A. Sheehan, Project' Manager Publications Branch Division of Freedom ofInformation and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 s ~ s.
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CONTENTS Preface..................................
....................................... v Index Tab it Main Citations and Abstracts......................................................... 1
?
e Staff Reports Conference Proceedings e
Contractor Reports e
e Grant Reports e international Agreement Reports Secondary Report Number index...........................
2 Personal Author index............................................
3 Subject index...................................................................... 4 NRC Originating Organization index (Staff Reports)..................................... 5 NRC Originating Organization index (International Agreements)......
6 NRC Contract Sponsor index (Contractor Reports)....................................... 7 Contractor index.......................
8 Intemational Organization index..................................
9 Licensed Facility index..................................................
...... 10 l
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PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to pubilsh this compilation quarterly and to 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 ir 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 (Intemational Agreements) l NRC Contract Sponsor Index (Contractor Reports)
Contractor index Intemational Organization index Licensed Facility index A detailed explanation of the entries precedes each index.
The bibliographic elements of the main citations are the following:
Staff Report NUREG-0808: MARK ll 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 l
report was published, (6) number of pages in the report, (7) the NRC Document Control System accession l
number, (8) the microfiche address (for internal NRC use).
l 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, (6) the report number of the originating organization, (9) the microfiche address (for NRC intemal use).
e v
Contractor Report NUREG/CR-1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR iIGHT WATER REAC-TORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R. Sandia Laboratories.
May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.
Where the entries are (1) report number, (2) report title (3) report authors, (4) organizational unit of authors or I
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).
Grant Report NUREG/GR4)013: APPUCATIONS OF A NEW MAGNETIC MONITORING TECHNIQUE TO IN SITU EVALUA-TION OF FATIQUE DAMAGE IN FERROUS COMPONENTS. JILES, D.C.; BINER, S.B.; GOVINDARAJU, M.; et al. Iowa State Univ., Ames, 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 intemal 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 Govemment Printing Office (GPO) orfrom the National Technicallnformation Service, Springfield, Virginia 22161. To purchase documents from the GPO, send a check or money order, payable to the Superintendent of Documents, to the following address:
Superintendent of Documents U.S. Govemment Printing Office Post Office Box 37082 i
Washington, DC 20013-7082 You may charge any purchase to your GPO !% posit Account, MasterCard charge card, or VISA charge card by calling the GPO on (202) 512-2249 or (20;:) 512-2171. Non-U.S. customers must make payment in advance cither by intemational Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bank, payable to the Superintendent of Documents.
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NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated report.
Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX This type of identification replaces contractor-established codes such as ORNljNUREG/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 DMslon of Freedom of Information and Publications Services.
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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-0020 V20: LICENSED OPERATING REACTORS STATUS and Licensing Appeal Board, and Atomic Safety and Licensing
SUMMARY
REPORT. Data As Of December 31, 1995.(Gray Board decisions issued dunng the period of July 1,1972 to Book 1) HARTFIELD,R.A. Office of information Resources Man-June 30,1995, interpreting the NRC's Rules.
agement (Post 890205). June 1996. 342pp. 9606250180.
88702:001.
NUREG-0430 V15: LICENSED FUEL FACILITY STATUS The Nuclear Regulatory Commission's annual summary of li-REPORT. inventory Difference Data. July 1,1994 - June 30, censed nuclear power reactor data is based primarily on the 1995.(Gray Book 11). JOY,0.R. Office of Nuclear Material Safety report of operating data submitted by licensees for each unit for
& Safeguards. May 1996.18pp. 9607090152. 88956:319.
the month of December because that report contains data for NRC is committed to the periodic publication of licensed fuel the month of December, the year to date (in this case calendar facility inventory difference data, following agency review of the year 1995) and cumulatwe data, usually from the date of com-information and completion of any related NRC investigations.
mercial operation. The data is not independently venfied, but information in this report includes inventory difference data for various computer checks are made. The report is divided into actwe fuel fabncation facdsties possessing more than one effec-two sectons. The first contains summary highlights and the twe kilogram of special nuclear material.
second contains data on each indwidual unit in commercial op.
NUREG-0540 V18 N01: TITLE LIST OF DOCUMENTS MADE erston. Section 1 capacity and availability factors are simple PUBLICLY AVAILABLE. January 1-31, 1996.
- Division of Free-anthmetic averages. Section 2 items in the cumulatwe column dom of Information & Publicatons Services (Post 940714).
are generally as reported by the licensee and notes as to the March 1996. 276pp. 9604230386. 87093:001.
use of weighted averages and starting dates other than com-This document is a monthly publication containing descrip-mercial operation are provided.
tions of information received and generated by the U.S. Nuclear NUREG-0040 V20 N01: LICENSEE CONTRACTOR AND Regulatory Commission (NRC). This information includes (1)
VENDOR INSPECTION STATUS REPORT. Quarterly docketed material associated with civilian nuclear power plants Report. January-March 1996.(White Book)
- Office of Nuclear and other uses of radioactive materials, and (2) nondocketed Reactor Regulaton (Post 941001). May 1996. 91pp.
material received and generated by NRC pertinent to its role as 9606250166. 88701:237.
a regulatory agency. The following indexes are included: Per.
This periodical covers the results of inspectons performed by sonal Author Corporate Source, Report Number, and Cross j
the NRC's Special Inspection Branch, Vendor inspection Sec Reference of Enclosures to Principal Documents.
tion, that have been distnbuted to the inspected organizations NUREG-0540 V18 N02: TITLE LIST OF DOCUMENTS MADE dunng the period from January through March 1996.
PUBLICLY AVAILABLE. February 1 29, 1996.
- Division of Free-NUREG-0304 V20 N04: REGULATORY AND TECHNICAL RE-dom of information & Publications Services (Post 940714). Aprii PORTS (ABSTRACT INDEX JOURNAL). Annual Compilation 1996. 264pp. 9605220337. 88310:001.
For 1995.
- Dwision of Freedom of information & Publications See NUREG-0540,V18,N01 abstract.
(
Services (Post 940714). April 1996. 120pp. 9605220248.
I 88319:273.
NUREG-0540 V18 NO3: TITLE LIST OF DOCUMENTS MADE This journal includes all formal reports in the NUREG series PUBLICLY AVAILABLE. March 1 31, 1996.
- Dwision of Free-prepared by the NRC staff and contractors, proceedings of con-dom of information & Publications Services (Post 940714). May ferences and workshops, grants, and international agreement 1996. 319pp 9606070098. 88487:001.
reports. The entries in this compilation are indexed for access See NUREG-0540,V18,N01 abstract.
by title and abstract, secondary report number, personal author' NUREG-0540 V18 N04: TITLE LIST OF DOCUMENTS MADE subject, NRC organization for staff and intemational agree-PUBLICLY AVAILABLE. April 1-30, 1996.
- Dwision of Freedom ments, contractor, intemational organization, and licensed facili-of Information & Publications Services (Post 940714) June ty.
1996. 425pp. 9606250175, 88700:001.
i NUREG-0304 V21 N01: REGULATORY AND TECHNICAL RE.
See NUREG 0540,V18,N01 abstract.
PORTS (ABSTRACT INDEX JOURNAL). Compilation For First NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND i
Quarter 1996. January-March. Dwision of Freedom of informa-EVALUATION OF RADIOLOGICAL EMERGENCY RESPONSE i
tion & Publications Services (Post 940714). June 1996. 43pp.
PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR l
EG 304'V N04 abstract' POWER PLANTS. Criteria For Emergency Planning in An Early l
Site Permit Application. Draft Report For Comment. KANTOR.F.;
NUREG-0386 D07: UNITED STATES NUCLEAR REGULATORY FOX,E.F. Office of Nuclear Reactor %egulation (Post 941001).
l COMMISSION STAFF PRACTICE AND PROCEDURE WINGERT,V.L; et al. Federal Emergency Management Agency.
DIGEST.Commisson, Appeal Board And Licensing Board April 1996. 32pp 9605220244. FEMA-REP-1. 88314:302.
Decisons. July 1972 - June 1995.
- Office of the General Coun.
The Nuclear Regulatory Commission (NRC) and the Federal set (Post 860701) April 1996,1056pp. 9605220382. 88311:001.
Emergency Management Agency (FEMA) have added Supple-This 7th edition of the NRC Practice and Procedure Digest ment 2 NUREG-0654/ FEMA-REP 1, Revision 1, to provide guid-contains a digest of a number of Commission, Atomic Safety ance for the development, review, and approval of radiological 1
2 Main Citations and Abstracts emergency information and plans sutenitted with an earfy site two groups: Part 1: ACRS Reports on Project Rev;ews, and Part permit apphcation under Subpart A of 10 CFR Part 52 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS NUREG-0750 V43101: INDEXES TO NUCLEAR REGULATORY reports by project name and by chronological order within COMMISSION ISSUANCES. January-March 1996.
- Dvision of Project name. Part 2 categonzes the reports by the most appro-Freedom d imormaton & Pubhcations Services (Post 940714).
pnate genene subject area and by chronological order within June 1996. 25pp. 9607090246. 88956:337.
subject area.
Digests and indexes for issuances of the Commission, the NUREG-1415 V08 N02: OFFICE OF THE INSPECTOR Atomc Safety and Licensing Board Panel, the Administrative Law Judges, the Drectors' Decisions, and the Decisions on Pe-GENERAL. Semiannual Report To Congress, October 1,1995 -
March 31,1996. BARCHl.T.; WATKINS.B.: GRODIN,M.; et al.
trhons for Rutemaking are presented.
Office of the inspector General (Post 890417). June 1996.
NUREG-0750 V43 N02: NUCLEAR REGULATORY COMMISSION 43pp. 9606180278. 88634:231.
ISSUANCES FOR FEBRUARY 1996. Pages 13-49.
- Division of The inspector General Act of 1978, as amended, requires Freedom of informaton & Pubhcatons Services (Post 940714).
that inspectors General submit a " Semiannual Report to Con.
April 1996. 44pp. 9604230336. 87976:198.
gress" summarizing program actrvities. The Inspector General's Legal issuances of the Commission, the Atomc Safety and Li-report is submitted to the Chairman of the NRC not later than censing Board Panel, the Administrative Law Judges, and NRC April 30, and October 31 for each reporting period. The Chair.
Program Offices are presented.
man comments on the report and prepares the NRC's Semian-nual W ongress as reqM by the Ad he Oakman j
NUREG-0750 V43 NO3: NUCLEAR REGULATORY COMMISSION su s
og a mW aM N Ns mpM no lats ISSUANCES FOR MARCH 1996. Pages51-121.
- Dvision of n
n a
ay M, mpcW Freedom of Information & Publications Services (Post 940714).
May 1996. 79pp. 9605220426. 88310:269.
NUREG-1437 V01: GENERIC ENVIRONMENTAL IMPACT See NUREG-0750,V43.N02 abstract.
STATEMENT FOR LICENSE RENEWAL OF NUCLEAR NUREG-0750 V43 N04: NUCLEAR REGULATORY COMMISSION PLANTS. Main Report.
- Dvision of Regulatory Applications ISSUANCES FOR APRIL 1996.Page 123-210.
- Dvision of (Post 941217). May 1996. 638pp. 9606180460. 88629:001.
Freedom of information & Pubhcations Services (Post 940714).
The generic environmental impact statement (geis) examines June 1996. 93pp. 9607120203. 89008:158.
the possible environmental impacts that could occur as a result See NUREG-0750,V43,N02 abstract.
of renewing licenses of individual nuclear power plants under 10 cfr part $4. The gets, to the extent possible, establishes the NUREG-0800 DRFT FC: STANDARD REVIEW PLAN FOR THE bounds and significance of these potential impacts. The analy-REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR ses in the geis encompass all operating hght-water power reac-POWER PLANTS. LWR Edition. Draft Report For Comment.
- tors. For each type of environmental impact the geis attempts Office of Nuclear Reactor Regulaton (Post 941001). June 1996.
to establish genene findings covenng as many plants as possi-7,046pp. 9606260017. 88730:001.
ble. This geis has three pnncipal objectives: (1) to provide an The Standard Review Plan (SRP) provides guidance to staff understanding of the types and seventy of environmental im-reviewers in the Office of Nuclear Reactor Regulabon in per*
pacts that may occur as a result of license renewal of nuclear forming safety reviews of applications to construct or operate power plants under 10 cfr part 54, (2) to identify and assess nuclear power plants. The pnncipal purpose of the SRP is to those impacts that are expected to be generic to license renew-assure the quality and uniformity of staff safety reviews. In al, and (3) to support a rulemaking (10 cfr part 51) to define the 1991, the Standard Review Pian Update and Development Pro-number and scope of issues that need to be addressed by the gram (SRP-UDP) was established to update NUREG-0800 for applicants in plant-by-plant license renewal proceedings. To ac-use in reviewing future reactor design applications. An "Imple-complish these objectives, the geis makes maximum use of en.
menting Procedures Document (IPD)", NUREG-1447, was vironmental and safety documentation from onginal licensing issued May 1992 to desenbe the SRP-UDP and establish the oroceedings and informabon from state and federal regulatory procedures for updating the SRP. The pnncipal objectives of the agencies, the nuclear utility industry, the open hterature, and SRP-UDP were to update the SRP to reflect the substantial professonal contacts.
changes in regulabon and regulatory guidance that occurred since the 1981 revision of the SRP and to reflect the experi-NUREG 1437 V02: GENERIC ENVIRONMENTAL IMPACT ence of the safety reviews conducted of design certificaten ap-STATEMENT FOR LICENSE RENEWAL OF NUCLEAR plications for evolutonary nuclear plants. This document pro-PLANTS. Appendices.
- Division of Regulatory Appleations vides the results of the update program.
(Post 941217). May 1996. 553pp. 9606180469. 88633:001.
NUREG-0837 V16 N01: NRC TLD DIRECT RADIATION MONI-See NUREG-1437,V01 abstract.
TORING NETWORK. Progress Report. January-March 1996.
NUREG-1440: REGULATORY ANALYSIS FOR AMENDMENTS STRUCKMEYER,R. Region 1 (Post 820201). May 1996. 227pp.
TO REGULATIONS FOR THE ENVIRONMENTAL REVIEW 96060N 88486:02&
FOR RENEWAL OF NUCLEAR POWER PLANT OPERAilNG This report provides the status and results of the NRC Ther-moluminescent Dosimeter (TLD) Direct Radiatson Monitonng LICENSES. Final Report.
- Division of Regulatory Applicatons Network. It presents the rad 4ation levels measured in the vicinity (Post 941217). May 1996. 35pp. 9606180288. 88630:327.
of NRC heensed facihties throughout the country for the first This regulatory analysis provides the supporting infor'naten for a rule that amends the nuclear regulatory commissian's re-quarter of 199&
quirements for environmental review of applications for renewal NUREG-1125 V17: A COMPILATION OF REPORTS OF THE AD.
of nuclear power plant operating hcenses. After considenng var.
VISORY COMMITTEE ON REACTOR SAFEGUARDS.1995 cus optons, the t'aff identified and analyzed two major attema-Annual.
- ACRS - Advisory Committee on Reactor Safeguards, tives. Alternative a is to not amend the regulations and to per-April 1996 118pp. 9605130141. 88226:142.
form environmental reviews under the existing regulabons. Alter-This compilaton contains 44 ACRS reports submitted to the native b is to assess, on a genenc basis, the environmental im-Commission, or to the Executive Director for Operations, dunng pacts of renewing the operating hcense of individual nuclear calendar year 1995. It also includes a report to the Congress on power plants, and define the issues that will need to be further the NRC Safety Research Program. All reports have been made analyzed on a case-by case basis. The findings of this assess-avadable to the public through the NRC Pubhc Document Room ment are codifed in 10 cfr part 51. The staff has selected alter-and the U S. Library of Congress. The reports are divided 'nto native b as the preferred alternative.
1 l
l Main Citations and Abstracts 3
NUREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE the torus at the Nine Mile Point 1 Plant. The report desenbes VESSEL SUPPORTS. JOHNSON,R.E. Division of Engineenng the causes of corrosion, requirements for rnonitoring corrosion, Technology (Post 941217). LIPINSKI,R.E. Idaho National Engi-and measures to mitigate the corrosive environment for the two neering Laboratory. May 1996. 200pp. 9605220250. 88321:001.
plants. The report describes the issuances of generic letters The NRC Generic Safety issue No.15, (GSI-15), " Radiation and information notices either to collect information to deter.
Effects on Reactor Pressure Vessel Supports," was established mine whether the problem is genene or to alert the licensees of to evaluate the concem that low-temperature, low-flux-level similar plants about the existence of such a problem. Implemen-neutron irradiation might embnttle reactor pressure vessel sup-tation of measures to enhance the containment performance ports to a rignificant degree and compromise plant safety. Eval-under severe accident conditions is discussed. A study by l
uation e' Pie surveillance samples from the High Flux isotope Brookhaven National Laboratory (BNL) of the performance of a l
Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) degraded containment under severe accident conditions is sum-I led to the conclusion that the embnttlement rates of some ma-marized. The details of the BNL study are in the appendix to the i
tenals used for pressurized water reactor pressure vessel (RPV) report.
I supports could be higher than expected. This disclosure raised a concern that a bottle fracture of the RPV supports could NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CON-occur during tho anticipated life-span of the plant. A later study SOLIDATING AND UPDATING MATERIALS LICENSING by the ORNL demonstrated that gamma radiation contributed a GUIDANCE. Draft Report For Comment. WHITTEN,J.E.;
significant amount of the embrittlement in the HFIR surveillance VACCA,P.C.; BROWN,K.D.; et al. Drvision of industrial & Medi-specimens. However, the shieldsng provided by the thick steel cal Nuclear Safety (Post 870729). April 1996. 39pp.
shell of the RPV ensures that degradation of RPV supports from 9605130135. 88220:239.
gamma irradiation is improbable or minimal. This report (1) de-This report describes the concept and approach for develop-scribes the technical findings resulting from the work done in ing the Materials Electronic Library (MEL). The Business Proc-accord with the GSI-15 Task Action Plan and (2) was used, in ess Redesign team for the licensing of matenals concerved, as part, as the basis for technical resolution of the issue.
an integra: part of its vision for the redesign of this licensing NUREG-1529 V01: PUBLIC COMMENTS ON THE PROPOSED 10 process, the idea for MEL. To establish MEL, the NRC will con-CFR PART 51 RULE FOR RENEWAL OF NUCLEAR POWER solidate and update numerous regulations and policy and guid-PLANT OPERATING LICENSES AND SUPPORTING DOCU-ance documents supporting the materials licensing process into MENTS: REVIEW OF CONCERNS AND NRC STAFF a single, comprehensive electronic repository for use by the RESPONSE. Executive Summary.
- Division of Regulatory Appli-NRC, Agreement and non-Agreement States, licensees, apph-cations (Post 941217). May 1996. 40pp. 9606180325.
cants, and the public.
88634:190.
This report documents the nuclear regulatory commission NUREG 1542 V01: ACCOUNTABILITY REPORT FISCAL YEAR (nrc) staff review of public comments provided in response to 1995. CONNELLY,S.R. Office of the Controller (Post 890205).
the nrc's proposed amendments to 10 code of federal regula-April 1996. 85pp. 9607120159. 88982:220.
tions (cfr) part 51, which establish new requirements for the en-The U.S. Nuclear Regulatory Commission (NRC) is one of six vironmental review of applications for the renewal of operating Federal agencies participating in a pilot project to streamline fi-
' licenses of nuclear power plants. The public comments include nancial management reporting. The goal of this pilot is to con-those submitted in wnting, as well as those provided at public sohdate performance-related reporting into a single accountabil-meetings that were, held with other federal agencies, state ity report in accordance with the Government Management cgencies, nuclear industry representatives, public interest Reform Act (GMRA) of 1994. The NRC's first accountability groups, and the general public. This report also contains the nrc report consolidates the information previously reported in the statt response to the vanous concerns raised, and highlights the NRC's annual financial statement required by the Chief Finan-cial Officers Act of 1990, as amended; the Chairman's annual changes made to the final rule and the supporting documents in response to these concerns.
report to the President and the Congress, required by the Fed-1 eral Managers' Financial Integrity Act of 1982; and the Chair.
NUREG-1529 V02: PUBLIC COMMENTS ON THE PROPOSED 10 man's semiannual report to the Congress on management deci-CFR PART 51 RULE FOR RENEWAL OF NUCLEAR POWER sions and final actions on Office of inspector General (OlG)
PLANT OPERATING LICENSES AND SUPPORTING DOCU.
audit recommendations, required by the inspector General Act MENTS: REVIEW OF CONCERNS AND NRC STAFF of 1978, as amended. This report also includes performance RESPONSE. Appendices.
- Drvision of Regulatery Applications measures, as required by the Chief Financial Officers Act of (Post 941217). May 1996. 671pp. 9606180333. 88627:001.
1990.
See NUREG 1529,V01 abstract.
NUREG/CP-0150: WORKSHOP ON ROCK MECHANICS ISSUES NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S IN REPOSITORY DESIGN AND PERFORMANCE MATERIALS LICENSLNG PROCESS REDESIGN.
ASSESSMENT. Held At Holiday Inn Crowne Plaza, l
RATHBUN,P.A.; BROWN K.D.; MADERA.J.R.; et al. Division of Rockville, Maryland. September 19-20, 1994.
- Center for Nucle-l Industrial & Medical Nuclear Safety (Post 870729). April 1996.
ar Waste Regulatory Analyses. April 1996.266pp.9606030259.
82pp. 9604160379. 87884:179-88422:001.
l This report describes the work and vision of the team char-The Center for Nuclear Waste Regulatory Analyses organized tered to redesign the process for licensing users of nuclear ma-and hosted a workshop on " Rock Mecharacs issues in Reposi-l terials. The Business Process Redesign team was chartered to tory Design and Performance Assessment" on behalf its spon-i improve the speed of the existing licensing process while main-sor the U.S. Nuclear Regulatory Commission (NRC). This work-l taining or improving public safety and to achieve required re-shop was held on September 19-20, 1994 et the Holiday Inn source levels. The report describes the team's methods for ac-Crowne Plaza, Rockville, Maryland. The objectives of the work-quinng and analyzing information about the existing matenals 16-shop were to stimulate exchange of technical information censing process and the steps necessary to radically change among parties actrvely investigating rock mechanics issues rele-this process to the envisioned future process.
vant to the proposed high-level waste repository at Yucca NUREG-1540: BWR STEEL CONTAINMENT CORROSION.
Mountain and identify / confirm rock mechanics issues important TAN,C.P.; BAGCHI,G. Office of Nuclear Reactor Regulation to repository design and performance assessment. The work-(Post 941001). April 1996 217pp. 9004230397. 87994:001, shop contained three technical sessions and two panel discus-The report describes regulatory actions taken after corrosion sions. The participants included technical and research staffs was discovered in the drywell at the Oyster Creek Plant and in representing the NRC and the Deputment of Energy and their
4 M:in Cititirns cnd Abstrccts I
contractors, as well as researchers from the academic, com-stainless steel. Depth sizing performance showed little correla-mercial, and internatonal technical communities. These pro-tion with the true crack depths.
ceedings include most of the technical papers presented in the technical sessons and the transcripts for the two panel discus.
NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS:
LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM
)
sions.
FOR FISCAL YEAR 1995. Annual Report. MCCONNELL.J.W.;
NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADIO-ROGERS.R.D.
Idaho Natonal Engineenng Laboretory.
ACTIVE RELEASES FROM NUCLEAR POWER PLANT JASTROW,J.D.; et al. Argonne National Laboratory. June 1996.
SITES. Methodology And Data Base. BAKER,D.A. Battelle Me-82pp. %07090111. INEL-94/0278. 88958:118.
monal institute, Pacific Northwest Laboratory. June 1996.
The Field Lysimeter Investigatons: Low-Level Waste Data 250pp. 9607090240. 88957:001.
Base Development Program, funded by the U.S. Nuclear Regu-This manual desenbd a dose assessment system used to latory Commission, is (a) studying the degradation effects in or-estimate the population or collective dose commitments re-ganic ion-exchange resins caused by radiahon, (b) examining ceived via both airborne and waterborne pathways by person the adequacy of test procedures recommended in the Branch 1
living within a 2-to 80-kilometer region of a commercial operat-Technical Positen on Waste Form to meet the requirements of ing power reactor for a specific year of effluent releases. Com-10 CFR 61 using solidified ion-exchange resins, (c) obtaining puter programs, data files, and utility routines are included performance information on solidified ion-exchange resins in a which can be used in conj. unction with an IBM or compatible disposal environment, and (d) determining the condition of liners personal computer to produce the required dose cornmitments used to dispose the ion-exchange resins. Compressive test re-and their statistical distributions. In addition, maximum individual suits of 12-year-old cement and vynyt ester-styrene solidifod airborne and waterborne dose commitments are estimated and waste forms are presented, which show effects of aging and compared to 10 CFR Part 50, Aprendix 1. design objectives.
self-irradiation. Results of the tenth year of data acquisition from NUREG/CR-4219 VII N2: HEAVY-SECTION STEEL TECHNOL.
the field testing are presented and discussed. Dunng the con-OGY PROGRAM Semiannual Progress Report For April-Sep-tinuing field testing, both portland type 1-11 cement and Dow vinyl i
tember 1994. PENNELL,W.E. Oak Ridge National Laboratory.
ester-styrene waste forms are being tested in fysimeter arrays 1
April 1996.117pp. 9605130075. ORNL/TM-9593. 88220:126.
located at Argonne Natonal Laboratory-East in Illinois and at The Heavy-Section Steel Technology (HSST) program is con-Oak Ridge National Laboratory. The study is designed to pro-ducted for the Nuclear Regulatory Commission (NRC) by Oak vide continuous data on nuclide release and movement, as well Ridge Natonal Laboratory (ORNL). The program focus is on the as environmental conditions, over a 20-year penod.
development and validation of technology for the assessment of NUREG/CR-5031 R02: CONTRIBUTION OF MATERNAL RADIO-fracture-prevention margins in commercial nuclear reactor pres-NUCLIDE BURDENS TO PRENATAL RADIATION DOSES.
sure vessels. The HSST Program is organized in seven tasks:
SlKOV,M.R.; HUI,T.E.; TRAUB.R.J.; et al. Battelle Memonal In-(1) program management (2) constraint effects analytical devel-opment and validation, (3) evaluation of cladding effects. (4) statute, Pacific Northwest Laboratory. May 1996. 389pp.
9606070092. PNL 7445. 88485:00f.
ductile-to-cleavage fracture-mode conversion, (5) fracture analy-sis rnethods development and apphcation, (6) matenal property This report describes approaches to calculating and express-data and test metnods, and (7) integraton of results. The pro.
ing radiaton doses to the embryo / fetus from internal radionu-gram tasks have been structured to place emphasis on resolu.
chdes. Informaton for occupatonally and medically significant radioelements was used to derive biokinetic transfer models tion fracture issues with near-term licensing significance. Re.
sources to execute the research tasks are drawn from ORNL and integrated with metabolic patterns. Placental transfer and with sub-contract support from universities and other research radioactivty levels in the embryo / fetus were calculated as a laboratories. Close contact is maintained with the sister Heavy.
function of stage of pregnancy and time after administraton and Section Steel irradiation (HSSI) Program at ORNL and with re.
are given as tables of deposition and retention in the embryo /
lated research programs both in the United States and abroad.
fetus. Methodologies described by MIRD were extended to cal-culate ra6stion absorbed doses to the embryo / fetus using a This report provides an overview of pnncipal developments in each of the seven program tasks from April 1994 to September scenario that assumed injection of a bolus into the woman's blood. Calculatons were performed for administration at suc-1994.
cessive months of pregnancy to accommodate stage depend-NUREG/CR-5068: PIPING INSPECTION ROUND ROBIN-ence of geometric relationships and biological behaviors of ra-HEASLER,P.G.; DOCTOR,S.R. Battelle Memorial institute, Pacif-donuclides. The gestational-stage-dependent dosimetric dose ic Northwest Laboratory. April 1996. 196pp. 9604230383.
factors are based on radiation absorbed doses. Multiplication by PNNL-10475. 87992:143.
appropnate quahty factors convert these to dose equivalent, the The piping inspection round robin was conducted in 1981 at most common quantity for stating prenatal dose limits in the the Pacific Northwest National Laboratory (PNNL) to quantify United States. The dose factor tabulatons are supplemented the capabikty of u!trasonics for inservice inspection and to ad' with tables of correlations and surrogate dose factors.
dress some aspects of rehability for this type of. nondestructive evaluaton (NDE). The research was sponsored by the U.S. Nu-NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN clear Regulatory Commisson Office of Research, under a pro-SAFETY TESTING. Technical Report On The Findings Of Task gram entitled, "Evaluaton and improvement of NDE Reliability 4 investigaton of Failed Nitinol Brachytherapy Wire, for Inservice inspection of Light Water Reactors." The round BENAC D.J.; BURGHARD,H.C. Southwest Research institute.
robin measured the crack detection capabihties of seven field March 1996. 268pp. 9605130090. 04-4448-010. 88228:047.
inspection teams who employed procedures that met or ex-This report covers an investigation of the nature and cause of ceeded tr.a 1977 editon through the 1978 addenda of the fadure in Nitinol brachytherapy sourcewires. The investigation American Society of Mechanical Engineers (ASME)Section XI was initiated after tv.o clinical incidents in which sourcewires Code requirements. Three different types of material were em-failed dunng or immediately after a treatment. The investigation ployed in the study (cast stainless steel, clad femtic, and determined that the two chnical Nitinol sourcewires failed in a wrought stainless steel), and two different types of flaws were bnttle manner, which is atypical for Nitinol. There were no mate-implanted into the specimens (intergranular stress corrosion nal anomahes or subentical flaws to explain the bnttle failures.
cracks (IGSCCs) and thermal fatigue cracks (TFCs)). When con-The bend tests also demonstrated that neither moist environ-sidenng near-side inspecton, far side inspection, and false call ment, radiation, nor low-temperature structure transformation rate, the overall performance was found to be best in clad ferrit-was a likely root cause of the failures. However degradaten of ic, less effective in wrought stainless steel and the worst in cast the PTFE was consistently evident, and those sourcewires
Main Citations and Abstracts 5
shipped or stored with PTFE sleeves consistently failed in labo-and the spatial reactivity effects of the distnbuted boron were ratory bend tests. On the basis of the results of this study, it determined. For pool flows that increase as a linear ramp, the was concluded that the root cause of the in-sennce failures of spatial reactivity effects of the distributed boron were very the sourcewires was environmentally induced embnttlement due small. In this case, a constant core-average boron reactivity co-to the breakdown of the PTFE protective sleeves in the pres-efficient can be used to model the PIUS scram reactivity.
ence of the high-radiation field and subsequent reaction or inter-action of the breakdown products with the Nibnot alloy.
NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS:
LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM NUREG/CR4210: COMPUTER CODES FOR EVALUATION OF LYSIMETER TEST RESULTS FOR FISCAL YEARS 1994 AND CONTROL ROOM HABITABILITY (HABIT). STAGE.S.A. Battelle 1995. MCCONNELL,J.W.; ROGERS.R.D. Idaho National Engi-Memonal institute, Pacific Northwest Laboratory. June 1996.
neering Laboratory. JASTROW,J.D.; et al. Argonne Natonal 173pp. 9606250169. PNL-10496. 88701:066's for evaluation ofLaboratory. June 1996.121pp. 9607090148. INEL-95/0073.
This report desenbes the computer code 88956:112 control room habitability (HABIT). HABIT is a package of com-The Fieid Lysimeter Investigations: Low-Level Waste Data puter codes designed to be used for the evaluation of control Base Development Program, funded by the U.S. Nuclear Regu-room habitability in the event of an accidental release of toxic latory Commission NRC), is (a) studying the degradation effects chemicals or radioactive materials. Given information about the in EPICOR-Il organic ion-exchange resins caused by rediation, design of a nuclear power plant, a scenario for the release of (b) examining the adequacy of test procedures recommended in toxic chemicals or radionuclides, and information about the air the Branch Technical Positen on Waste Form to meet the re-flows and protection systems of the control room; HABIT can quirements of 10 CFR 61 using solidified EPICOR-Il resins, (c) be used to eshmate the chemical exposure or radological dose obtaining performance information on sohdified EPICOR-il ion-of control room personnel. HABIT es an integrated package of exchange resins in a disposal environment, and (d) determining several programs that previously needed to be run separately the condstion of EPICOR-il liners. Resutts of the final 2 (10 total) and required considerable user intervention. These are years of data acquisition from operaton of the reld testing are EXTRAN, CHEM, TACT 5, FPFP-2, and CONHAB. New input presented and discussed. During the continuing f> eld teshng, routines have been wntten for these routines using data input both portland type I-il cement and Dow vinyl ester-styrene windows. These are designed for easy use entering, reviewing waste forms are being tested in fysimeter arrays located at Ar-and revising the data. The programs can now be run in se-gonne National Laboratory-East in Illinois and at Oak Ridge Na-quence as an integrated package. Improvements have been tional Laboratory. The experimental equipment is described and made in the computational methods used by some of the rou-results of waste form characterization using tests recommended tines. The programs produce files containing ASCll tables of by the NRC's " Technical Positen on Waste Form" are present-values and output fdes that can readily be imported into a com-ed. The study is designed to provide continuous data on nuclide mercial spreadsheet to be graphed or for further computations.
release and movement as well as environmental conditions.
NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS over a 20-year penod. At the end of the tenth year, the experi-FOR EDDY CURRENT INSPECTION OF STEAM GENERATOR ment was closed down. Examination of soil and waste forms is TUBING. KURTZ,RJ.; HEASLER,P.G.; ANDERSON,C.M. Bat-planned to be conducted next and will be reported later.
telle Memonal Institute, Pacific Northwest Laboratory. May NUREG/CR4270: ESTIMATING BOILING WATER REACTOR 1996. 54pp. 9606180253. PNNL-9433. 88630:275.
DECOMMISSIONING COSTS.A User's Manual For The BWR This report desenbes the methodology and results for devel-Cost Estimating Computer Program (CECP) Software. Final opment of performance demor'stration tests for eddy current (ET) inspection of steam generator tubes. Statistical test design Report. BIERSCHBACH,M. Ba!!elle Memorial institute, Pacific principle were used to develop the performance demonstraton Northwest Laboratory. June 1996. 216pp. 9607150168. PNL-10086. 89003:058.
tests. Thresholds on ET system inspechon performance were selected to ensure that field inspecten systems have a high Nuclear power plant licensees are required to submit to the probabdity of detecting and correctly sizing tube degradation.
U.S. Nuclear Regulatory Commission (NRC) for review decom-The technical basis for the ET system performance thresholds rmssiomng cost estimates. This user's manual and the accom-is presented in detail. Statistical test design calculatons for panying Cost Estimating Computer Program (CECP) software probability of detecten and flaw sizing tests are described. A provide a cost-calculatng methodology to the NRC staff that recommended performance demonstraton test based on the will assist them in assessing the adequacy of the hcensee sub-design calculations is presented. A computer program for grad, mittals. The CECP, designed to be used on a personal comput-er, provides estimates for the cost of decommissioning BWR ing the probability of detecten portion of the performance dem-power statens to the point of hcense termination. Such cost es-onstration test is given.
timates include component, piping, and equipment renoval NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.
costs; packagir,g costs; decontaminaten costs; transportation CAREW J.F.; ARONSON.A.; COKINOS D.M.; et al. Brookhaven costs; burial costs; and manpower costs. In addition to costs.
Natonal Laboratory. May 1996. 71pp. 9606070090. BNL-the CECP also calculates burial volumes, person-hours, crew-NUREG-52425. 88490:283.
hours, and exposure persomhours associated with decommis-A detailed evaluaton of the fuel bumup dependent power dis-sioning.
tribubon and the scram reactivity for the PlUS reactor design has been performed. The analyses were camed out using the NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSI-CPM lattice physics and NODE-P2 core neutronics/ thermal-hy.
TY b JLTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY draulics codes and are based on the informaton provided in the (PUMA) FOR GE SBWR.
ISHil,M.;
REVANKAR,S.T.;
PIUS Prehminary Safety information Document. Cycle depleton DOWLATI,R.; et al. Purdue Univ., West Lafayette, IN. Apnl calculations were periormed for a set of nine representative ini-1996 279pp. 9605130t41. PU-NE 94/1. 88238:001.
tial core loadings and the three-scw-hit core power distribu.
The scientific design of the scaled facility (PUMA) has been tions were determined These calculations indicate that the carned out under the project " Confirmatory Integral System PtUS radial F(a h) and total F(Q) power peaking is significantly Testing for GE SBWR Design". The design was based on the stronger than indicated by the PlUS reference design values.
three level scaling method developed for this task. The first The scram reactNity resutbng from the injection of highly borat-level of scaling is based on the integral response functon. The l
ed pool water was calculated for a senes of hme-dependent second level scahng is for the boundary flow of mass and linear ramp and square-wave pool flows. The three Gce Aal energy between components. The third level of scaling is fo-distribution of the pool water throughout the core was modeled cused on the key local phenomena and constitutive relations.
6 Main Citations and Abstracts I
The facihty has 1/4 height and 1/100 area ratio scaling. This influenced chemical attack on cement-sohdified LLW. The pro-I corresponds to a volume scale of 1/400 and power scaling of cedures that have been developed in this work are presented i
1/200. The time will run twice as fast in the model as predicted and discussed. Groups of microorganisms indigenous to LLW by the present scaling method. The PUMA is scaled for full disposal sites were employed that can metabolically convert or-pressure and is intended to operate at and below 150 psia foi-ganic and inorganic substrates into organic and mineral acids.
lowing scram. The facihty models all the major components of Such acids aggressively react with cement and can ultimately SBWR.
lead to structural failure. Results on the application of mecha-NUREG/CR-6314: OUALITY ASSURANCE INSPECTIONS FOR nisms inherent in microbially influenced degradation of cement-SHIPPING AND STORAGE CONTAINERS. STROMBERG,H.M.;
based matenal are the focus of this final report. Data-validated ROBERTS.G D.; BRYCE.J.H. Idaho Natonal Engineering Labo-evidence of the potent al for microbially influenced detenoration ratory. Apnl 1996. 77pp. 9605310158. INEL-95/0001.
of cement sohdified LLW and subsequent release of radionu-88395:119.
chdes developed during this study are presented.
1 This document is a guide for conducting quality assurance in-NUREG/CR-6345: RADIATION DOSE ESTIMATES FOR RADIO-spections of transportation packaging and dry spent fuel stor.
PHARMACEUTICALS.
STABIN,M.G.;
STUBBS,J.B.;
age system supphers. This document is used dunng an inspec.
TOOHEY,R.E. Oak Ridge Associated Universities. April 1996.
tion to determine regulatory comphance with Title 10 of the 92pp. 9605290091. 88375:133.
1 Code of Federal Regulabons, Part 71, Subpart H; Title 10 of the Tables of radiation dose estimates based on the Cristy-Ecker-Code of Federal Regulations, Part 72, Subpart G; and Title 10 man adult male phantom are provided for a number of radio-of the Code of Federal Regulations, Part 21, and quality assur-pharmaceuticals commonly used in nuclear medicine. Radiation ance program commitments. The guidance provides a frame-dose estimates are listed for all major source organs, and sev-I work for transportation packaging and dry spent fuel storaad eral other organs of interest. The dose estimates were calculat-system inspections. Inspectors are provided with the flexibihty to ed using the MIRD Technique as implemented in the MIR-tdapt the methods and concepts to meet the inspection re.
DOSE 3 computer code, developed by the Oak Ridge Institute quirements for the particular facihty. This guide was developed for Science and Education, Radiation Internal Dose information to provide a structured and consistent approach for inspections.
Center, in this code, residence times for source organs are The method separates each performance element into several used with decay data from the MIRD Radionuchde Data and areas for inspection and identifies guidehnes, based on regula.
Decay Schemes to produce estimates of radiaton dose to tory requirements, to qualitatively evaluate each area. This doc-organs of standardized phantoms representing individuals of dif-ument was also developed to serve as a field manual to facili-ferent ages.
tite the quality assurance inspection activities.
NUREG/CR-6332: MICROSTRUCTURAL CHARACTERIZATION NUREG/CR-6350: A TECHNIQUE FOR HUMAN ERROR ANALY-CF SELECTED AEA/UCSB MODEL FECUMN ALLOYS.
SIS (ATHEANA). Technical Basis And Methodology Desenption.
j RICE.P.M.; STOLLER R E. Oak Ridge National Laboratory. June COOPER.S E. Science Apphcations International Corp. (formerly 1996.63pp.9607090195. ORNL/TM 12980. 88958:266.
Science Applications, Inc.). RAMEY-SMITH,A. Division of Sys-A set of 22 model femtic alloys was purchased as part of a tems Technology (Post 941217). WREATHALL.J.; et al. Affih-collaborative research program by the AEA Harwell Laboratory ation Not Assigned. May 1996. 111pp. 9607090121. BNL-and the University of Cahfornia at Santa Barbara. Nine of these NUREG-52467. 88956:001, alloys were selected by the Oak Ridge National Laboratory for Probabihstic risk assessment (PRA) has become an important use in a series of ion irradiation experiments investigating dis-tool in the nuclear power industry, both for the Nuclear Regula-persed barrier hardening. These nine alloys contain varying tory Commission (NRC) and the operating utilities. Human reli-amounts of copper, manganese, titanium, carbon, and nitrogen.
abihty analysis (HRA) is a entical element of PRA; however, limi-The alloys have been charactenzed by transmission electron tations in the analysis of human actions in PRAs have long microscopy in the as-received condition to provide a baseline been recognized as a constraint when using PRA. A multdsci-for compenson with the irradiated specimens. A desenption of plinary HRA framework has been developed with the objective the microstructural observations is provided for future reference.
of providing a structured approach for analyzing operating expe-This summary focuses on the type and size distributions of the rience and understanding nuclear plant safety, human error, and j
precipitates present; grain size and dislocation measurements the undertying factors that affect them. The concepts of the 4
tre also included.
framework have matured into a rudimentary working HRA method. A trial application of the method has demonstrated that NUREG/CR-6341: MICROBIAL DEGRADATION OF LOW-LEVEL it is possible to identify potentially significant human failure RADIOACTIVE WASTE. Final Report.
ROGERS R.D.;
events from actual operating expenence which are not generally HAMILTON,M.A.; VEEH,R.H.; et al. Idaho National Engineenng included in current PRAs, as well as to identify associated per-Laboratory. June 1996. 116pp. 9607090197. INEL-95/0215.
formance shaping factors and plant conditions that have an ob-88958:001.
servable impact on the frequency of cose damage. A general The Nuclear Regulatory Commission stipulates in 10 CFR 61 process was developed, albeit in preliminary form, that address-that disposed low-level radioactive waste (LLW) be stabihzed.
es the iterative steps of defining human failure events and esti-To provide guidance to disposal vendors and nuclear station mating their probabilities using search schemes. Additionally, a wiste generators for implementing those requirements, the knowledge-base was developed which describes the links be-NRC developed the Technical Position on Waste Form, Revi-tween performance shaping factors and resulting unsafe ac-sion 1. That document details a specified set of recommended tions.
testing procedures and enteria, including several tests for deter.
mining the brodegradatiun properties of waste forms. Informa-NUREG/CR-636C:
SUMMARY
OF AIR PERMEABILITY DATA tion has been presented by a number of researchers. which in-FROM SINGLE-HOLE INJECTION TESTS IN UNSATURATED dicated that those tests may be inappropnate for examining mi-FRACTURED TUFFS AT THE APACHE LEAP RESEARCH crobial degradation of cement-solidified LLW. Cement has been SITE: RESULTS OF STEADY-STATE TEST INTERPRETATION.
widely used to sohdify LLW; however, the resulting waste forms GUZMAN A.G.; GEDDIS,A.M.; HENRICH,M.J.; et al. Arizona, are sometimes susceptible to failure due to the actions of waste Univ. of, Tucson, AZ. March 1996. 175pp. 9604230343.
constituents, stress, and environment. The purpose of this re-87997:011.
search program was to develop modified microbial degradation This document summanzes air permeabahty estimates ob-test procedures that would be more appropnate than the exist-tained from single hole pneumatic injection tests in unsaturated ing procedures for evaluation of the effects of mscrobiologically fractured tuffs at the Covered Borehole Site within the larger
Main Citations and Abstracts 7
Apache Leap Research Site. Only permeability estimates ob-NUREG/CR-6384 V01: LITERATURE REVIEW OF ENVIRON-tained from a steady state interpretation of relatively stable MENTAL QUALIFICATION OF SAFETY-RELATEC ELECTRIC pressure and flow rate data are included. Tests were conducted CABLES. Summary Of Past Work. SUBUDHl M. Brookhaven Na-in five boreholes inclined at 45 degrees to the horizontal, and tional Laboratory. April 1996. 300pp. 9605130112. BNL-one vertical borehole. Five of the boreholes are 30 m long, one NUREG-52480. 88219:001, has length of 45 m. Over 180 borehole segments were tested This report summarizes the findings from a review of pub-between packers set 1 m apart. Add tional tests were conduct.
lished documents dealing with research on the environmental ed in segments of longths 0.5, 2.0 and 3.0 m in one borehole, qualification of safety-related electric cables used in nuclear and 2.0 m in another borehole, bringing the total number of power plants. Simulations of accelerated aging and accident tests to over 270. Tests were conducted by maintaining a con, conditions are important considerations in qualifying the cables.
stant 9'ecton rate until air pressure became relatively stable Significant research in these two areas has been performed in and remained so for some time, The injection rate was then in-the United States and abroad. The results from studies in cremented by a constant value and the procedure repeated, France, Germany, and Japan are described in this report. In Three or more such incremental steps were conducted in each recent years, the development of methods to monitor the condi-borehole segment while recording the air injection rate, pres-tion of cables has received special attention. Tests involving chemical and physical examination of cable's insulation and sure, temperature, and relative humidity. A description of field jacket materials, and electncal measurements of the insulation operating procedures used to insure compliance with OA/OC properties of cables are discussed. Although there have been requirements is included.
significant advances in many areas, there is no single method which can provide the necessary information about the condi-NUREG/CR-6365: STEAM GENERATOR TUBE FAILURES.
MACDONALD P.E.; SHAH,V.N.; WARD.LW. Idaho National En-tion of a cable currently in service. However, it is possible that further research may identify a combination of several methods gineering Laboratory. April 1996. 303pp. 9607100298. INEL-95/
that can adequately charactenze the cable's condition.
0383. 88955:001.
A review and summary of the available information on steam NUREG/CR-6384 V02: LITERATURE REVIEW OF ENVIRON-generator tubing failures and the impact of these failures on MENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC plant safety is presented. The following topics are covered:
CABLES. Literature Analysis And Appendices. LOFARO,R.;
pressunzed water reactor (PWR), Canadian deuterium uranium BOWERMAN.B.; CARBONARO,J.; et al. Brookhaven National (CANDU) reactor, and Russian water moderated, watercooled Laboratory. Apnl 1996. 146pp. 9605130115. BNL-NUREG-52480. 88265:001.
energy reactor (VVER) steam generator degradation, PWR steam generator tube ruptures, the thermal-hydraulic response in support of the U.S. NRC Environmental Qualification (EO) of a PWR plant with a faulted steam generator, the risk signifi-Research Program, a literature review was performed to identify cance of steam generator tube rupture accidents, tubing inspec-past relevant work that could be used to help fully or partsally tion requirements and fitness-for-service critena in various coun-resolve issues of interest related to the qualification of low-voll-tries, and defect detection reliability. Steam generator tube age electric cable. A summary of the literature reviewed is doc-umented in Vuume i of this report. In this, Volume 2 of the damage is caused by many diverse degradation mechanisms-report, dossiers are presented which document the issues se-some of which are difficult to detect and predict. The frequency lected for investigation in this program, along with recommenda-of steam generator tube ruptures can be significantly reduced tsons for future work to resolve the issues, when necessary. The through appropriate and timely inspections and repairs or re-dossiers are based on an analysis of the literature reviewed, as moval from service. However, a continuing issue has been ex-well as export opinions. This analysis includes a entical review actly what constitutes an appropnate and timely inspection and of the information available from past and ongoing work in thir-which degraded tubes are still fit for service. There have been teen specific areas related to EO. The analysis for each area many different approaches to this problem throughout the world.
,ocuses on one or more questions which must be answered to Although steam generator tube ruptures are small contnbutors consider a particular issue resolved. Results of the analysis are to the total core damage frequency calculated in probabilistic presented, along with recommendations for future work. The risk assessments, they are risk significant because the radionu-analysis is documented in the form of a dossier for each of the clides are likely to bypass the reactor containment building.
areas analyzed.
NUREG/CR-6383: CORROSION FATIGUE OF ALLOYS 600 AND NUREG/CR-6392: THE EFFECTS OF AGING ON COMPRES-690 IN SIMULATED LWR ENVIRONMENTS. RUTHER,W.E.;
SIVE STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE SOPPET,W.K.; KASSNER T.F. Argonne National Laboratory.
FORMS, MCCONNELLJW.; NEILSON,R.M. Idaho National En-April 1996. 56pp. 9604230394. ANL-95/37. 87993:276.
gineering Laboratory. June 1996. 47pp. 9607090141. INEL-95/
0506,88956:233.
Crack growth data were obtained on fracture-mechanics specimens of Alloy 600 and 690 to investigate environmentally The Field Lysimeter investigations: Low-Level Waste Data Base Development Program, funded by the U.S. Nuclear Regu-assisted cracking (EAC) in simulated boiling water reactor and latory Commission (NRC), is (a) studying the degradation effects pressurized water reactor environments at 289 and 320 degrees in organic ion-exchange resins caused by ladiation, (b) examin-C. Preliminary information was obtained on the effect of temper-ng the adequacy of test procedures recommended in the ature, load ratio, stress intensity K, and dissolved-oxygen and -
Branch Technical Position on Waste Form to meet the require-hydrogen concentrations of the water on EAC. Specimens of ments of 10 CFR 61 using solidified ion-exchange resins, (c) ob-Type 316NG and sensitized Type 304 stainless steel (SS) were taining performance information on sohdified ion-exchange included in several of the expenments to assess the oehavior of resins in a disposal environment, and (d) determining the condL these materials and Alloy 600 under the same water chemistry tion of kners used to dispose ion-exchange resins. Compressive and loading conditions. The expenmental data are compared tests were performed periodically over a 12-year period as part with predictions from an Argonne National Laboratory (ANL) of the Technical Position testing. Results of that compressive model for crack growth rates (CGRs) of SSs in water and the testing are presented and discussed. Dunng the study, both ASME Code Section XI correlation for CGRs in air at the portland type I-il cement and Dow vinyl ester-styrene waste K(max) and load-ratio values in the vanous tests The data for form samples were tested. This testing was designed to exam-all of the matenals were bounded by ANL model predictions ine the effects of aging caused by self-irradiation on the com-and the ASME Section XI " air line."
pressive strength of the waste forms. Also presented is a bnef summary of the results of waste form characterization, which
l 8
Main Citations and Abstracts had been conducted in 1986, using tests recommended in the veillance power reactor data base (PR-EDB) and material test l
Technical Position on Waste Form. The aging test results are reactor data base (TR-EDB) are analyzed. The shift of the tran-I compared to the results of those earlier tests.
sition temperature at 30 ft-lb (T(30)) is considered as the pri-NUREG/CA4401: FAULTING IN THE YUCCA MOUNTAIN mary ruasure of radabn emMttlemwit in this repwt. The hy.
l REGION.Cntical Review And Analyses of Tectonic Data From pertolic tangent fitting rrodel and uncertainty of the fitting pa-l The Central Basin And Range. FERRILL.D.A.; STIREWALT,G.L.;
rameters for Charpy impact tests are presented in this report.
HENDERSON,D.B.; et al. Center for Nuclear Waste Regulatory For the surveillance CMM data, the transition temperature shifts Analyses. March 1996.108pp. 9606030250. CNWRA 95-017.
at 30 ft-Ib QT(30)) generally follow the predictions provided by 88421:231.
Revision 2 of Regulatory Guide 1.99 (R.G.1.99). Drfference in Yucca Mountain, Nevada, has been proposed as the potential capsule impwatures is a hely eWanabon fw large Mons kom 139 pmdctons Dwiatons from me R.G.1.99 pre-site for a high-level waste (HLW) repository. The tectonic setting dNs are carelated to s\\amlar dwiabns fu me acewnpany.
of Yucca Mountain presents several potential hazards for a pro-I posed reposrtory, such as potential for earthquake seismicity, N matenals in me same capsubs, but large rh Nctua-I fault disruption, basaltic volcanism, magma channehng along tions prevent precise quantitative determnation. Significant pre-existing fautts, and faults and fractures that may serve as scatter is noted in the surveillance data, some of which may be barriers or conduits for ground water flow. Charactenzotion of awed to vanah frwn om specimen set to anomer, w h geologic structures and tectonic processes will be necessary to herent in Charpy V-notch testing. In general, the embnttlement assess compliance with regulatory requirements for the pro-behavior of both the A302B and A5338-1 plate materials is posed HLW repository. In this report, we specifically investigate similar. There is evidence for a fluence-rate effect in the CMM fault slip, seismicity, contemporary stain, and fault-slip potential data irradiated in test reactors; thus its implication on power re.
in the Yucca Mountain region with regard to Key Technical Un-actor surveillance programs deserves special attention.
certainties outhned in the License Application Review Plan (Sec-NUREG/CR-6424: REPORT ON AGING OF NUCLEAR POWER bons 3.2.1.5 through 3.2.1.9 and 3.2.2.8). These investigations PLANT REINFORCED CONCRETE STRUCTURES. NAUS D.J..;
center on (i) alternative methods of determining the shp h4to y OLAND C.B.
Oak Ridge National Laboratory.
of the Bare Mountain Fault, (ii) cluster analysis of histonc earth-ELLINGWOOD,B.R. Johns Hopkins Urw., Baltimore, MD. March quakes, (iii) crustal strain determinations from Global Positioning 1996. 290pp. 9604230376. ORNL/TM 13148. 87974:001.
System measurements, and (iv) three-dimensional slip-tendency The Structural Aging Program provides the U.S. Nuclear Reg-analysis. The goal of this work is to assess uncertainties associ-ulatory Commission with potenbal structural safety issues and ated with neotectonc data sets entical to the Nuclear Regula-acceptance entena for continued service assessments of tory Commission and the Center for Nuclear Waste Regulatory safety-related nuclear power plant concrete structures. The pro-Analyses' ability to provide prehcensing guidance and perform gram was organized under four task areas - Program Manage-Icense applicatson review with respect to the proposed HLW re-ment, Matenals Property Data Base, Structural Component As-pository at Yucca Mountain.
sessment/ Repair Technology, and Quantitative Methodology for NUREG/CR-6411: A GEOSTATISTICAL METHODOLOGY TO Continued Service Determinations. Under these tasks, over 90 ASSESS THE ACCURACY OF UNSATURATED FLOW papers and reports were prepared addressing pertinent aspects MODELS. SMOOT J.L; WILLIAMS R.E. Battelle Memonal Insti.
associated with aging management of nuclear power plant rein-tute, Pacific Northwest Laboratory. April 1996. 70pp.
forced concrete structures. Contained in this ram h; a budima-9607090193. PNL 10866. 88958:200.
ry of program rm.as in the form of information related to lon-The Pacific Northwest Nabonal Laboratory (PNNL) has devel.
gevity of nuclear power plant reinforced concrete structures, a oped a Hydrologic Evaluation Methodology (HEM) to assist the data base presenting data and information on the time variation U.S. Nuclear Regulatory Commission in evaluating the potential of concrete materials under the influence of environmental that infiltrating meteoric water will produce teachate at commer, stressors and aging factors, in-service inspection and condition cial low-level radioactive waste disposal sites. Two key issues assessments techniques, repair materials and methods, evalua-are raised in the HEM: 1) evaluation of mathematcal models tson of nuclear power plar't reinforced concrete structures and a that predict fLeihty performance, and 2) estimabon of the uncer.
reliability-based methodobgy for current and future condition tainty associated with these mathematcal model predictions.
assessments. Recommendabons for future activities are also The technical objective of this research is to adapt geostatists_
provided.
j cal tools commonly used for model parameter eshmation to the NUREG/CR-6425: IMPACT OF STRUCTURAL AGING ON SEIS-problem of estimating the spabal distnbution of the dependent MIC RISK ASSESSMENT OF REINFORCED CONCRETE 1
vanable to be calculated by the model. To fulfill this objective, a STRUCTURES IN NUCLEAR POWER PLANTS.
database desenbing the spatsotemporal movement of water in.
jected into unsaturated sediments at the Hanford Site an Wash-ELLINGWOOD B.R.; SONG,J. Johns Hopkins Uriv., Baltimore, ington State was used to develop a new method for evaluating MD.
- Oak Ridge Natonal Laboratory. March 1996. 81pp.
9604230399. ORNL/TM-13149 87971:225.
mathematcal model predictions. Measured water content data were interpolated geostatisically to a 16 x 16 x 36 gnd at sever-The Structural Aging Program is addressing the potential for al time intervals. Then a mathematcal model was used to pre-degradation of concrete structural components and systems in det water content at the same gnd locations at the selected nuclear power plants over time due to aging and aggressive en-times. Node-by-node comparison of the mathematcal model vironmental stressors. Structures are passive under normal op-predictions with the geostatistcally interpolated values was con-erating conditions but play a key role in mitigating design-basis ducted The method facihtates a complete accounting and cate-events, particularly those arising from external challenges such gonzation of model error at every node. The comparison sug-as earthquakes, extreme winds, fire, and floods. Structures are 1
gests that model results generally are within measurement plant-specific and unique, often are diffcult to inspect, and are error. The worst model error occurs in silt lenses and is in v rtually impossible to replace. The importance of stuctural fail-excess of measurement error.
ures in accdent mitigation is amplified because such failures may lead to common-cause failures of other components. Struc-l NUREG/CR-6413: ANALYSIS OF THE IRRADIATION DATA FOR tural condition assessment and service hfe prediction must A3028 AND A533B CORRELATION MONITOR MATERIALS.
focus on a few entical components and systems within the WANG,J.A. Oak Ridge National Laboratory. April 1996. 318pp.
plant. Components and systems that are dominant contnbutors 1
I 9605220308. ORNL/TM-13133. 88320:029.
to risk and that require particular attention can be identmed J
The results of Charpy V-notch impact tests for A3028 and through the mathematical formalism of a probabilistic nsk as-A533B-1 Correlation Monitor Matenals (CMM) hsted in the sur-sessment, or PRA. To illustrate, the role of structural degrada-j
1 Main Citations and Abstracts 9
tion due to aging on plant risk is examined through the frame-analyses, the hoop stress was fixed to correspond to an aver.
work of a Level 1 seismic PRA of a nuclear power plant. Plausi-age S(m) value for typical U.S. nuclear piping materials. Further ble mechanisms of structural degradation are found to increase factors included in the analyses were vanous strain-hardening the core damage probability by approximately a factor of two.
exponents and a/t values; however, the circumferential crackod NUREG/CR-6428: EFFECTS OF THERMAL AGING ON FRAC-elbow was limited to one crack length, and the axial cracked TURE TOUGHNESS AND CHARPY lMPACT STRENGTH OF elbow was limited to one crack length on the elbow flank.
STAINLESS STEEL PIPE WELDS.
GAVENDA.D.J/
These analyses were implemented into a computer code called MICHAUD W.F.; GALVIN,T.M.; et al. Argonne National Labora:
IP2 ELBOW. The results from the computer code calculations showed that the moment values at crack initiation were 1.5 to 2 tory. May 1996 86pp. 9605310163. ANL-95/47. 88394:253.
The degradation of fracture toughness tensile, and Charpy-times lower for the axially cracked elbow than for the circumfer-impact properties of Type 308 stainless steel (SS) pipe welds entially cracked elbow. The moment values for pressunzod due to thermal aging has been characterized at room tempera-straight pipe were somewhat lower than for circumferentially ture and 290 degrees C. Thermal aging of SS welds results in cracked elbows for R(m)/t of 10, but were 1.5 greater for R(m)/
IO moderate decreases in Charpy-impact strength and fracture toughness. For the vanous welds in this study, upper-shelf NUREG/CR-6465: DEVELOPMENT OF TOOLS FOR SAFETY energy docreased by 50-80 J/cm(2). The decrease in fracture ANALYSIS OF CONTROL SOFTWARE IN ADVANCED REAC-toughness J-R curve or J(IC) is relatively small. Thermal aging TORS. GUARRO,S.; YAU.M.; MOTAMED,M. ASCA, Inc. Aprit had little or no effect on the tensile strength of the welds. Frac-1996.144pp. 9605130069. 88226:001.
ture properties of SS welds are controlled by the distribution Software based control systems have gained a pervasive and morphology of second phase particles. Failure occurs by presence in a wide variety of applications, including nuclear the formation and growth of microvoids near hard inclusions.
power plant control and protection systems which are within the Such processes are relatrvely insensitive to thermal aging. The oversight and licensing responsibility of the U.S. Nuclear Regu-ferrite phase has little or no effect on the fracture properties of latory Commission. While the cost effectiveness and flexibility of the welds. Differences in fracture resistance of the welds arise software based plant process control is widely recognized, it is from differences in the density and size of inclusions. The me-very difficult to achieve high levels of dependability and safety chanical-property data from the present study are consistent assurance for the functions performed by process control soft-with results from other investigations. The existing data have ware, due to the very flexibility and potential complexity of the been used to establish minimum expected fracture properties software itself. The development of tools to model, analyze and for SS welds.
test software design and implementations in the context of the NUREG/CR-6443: DETERMINISTIC AND PROBABILISTIC EVAL-system that the software is designed to control can greatly UATIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAM-assist the task of providing higher levels of assurance than ETERS IN LEAK-BEFORE-BREAK AND IN-SERVICE FLAW those obtainable by software tesbng alone. This report presents EVALUATIONS. GHADIAll,N.; RAHMAN.S.; CHOL,Y.H. Batteile and discucses the development of the Dynamic flowgraph meth-Memorial Institute, Columbus Laboratones. June 1996,134pp.
odology (DFM) and its application in the dependability and as-9607120198. BMI-2191. 88980:141.
surance analysis of software-based control systems. The fea-This report presents new results from deterministic and prob-tues of the methodology and full-scale examples of application abilistic ane'ym to wsuale the wyrscance of a number of to both generic process and nuclear power plant control sys-technical aspects that may affect LBB or in-service flaw evalua-tams are presented and d4 cussed in detail. The features of a tions. In most cases there are both deterministic and probabilis-workstauon software tool developed to assist users in the appli-tic results. The deterministic analyses were conducted inde.
cation of DFM are also desenbed.
pendently of the probabilistic analyses, which offered the oppor-tunity to validate conclusions from each of these independent NUREG/CR-6470: FITNESS FOR DUTY IN THE NUCLEAR IN-studies. The technical aspects evaluated relative to LBB uncer.
DUSTRY: UPDATE OF THE TECHNICAL ISSUES 1996.
tainties were: (1) evaluation of different crack morphology de-DURBIN,N.; GRANT T.; BITTNER,A.; et al. Battelle Seattle Re-1 fault values, (2) evaluation of COD dependent and independent search Center. May 1996. 272pp. 9605220322. BSRC-700/96/
004. 88319.001.
crack morphology models for tight crack leak-rate analyses, (3) changes of normal operating and N+SSE stress levels on con-
. This report provides an update of information on the technical 4
ditional failure probability, (4) dynamic and cyclic loads history issues surrounding the creation, implementation, and mainte-effects on load-carrying capacity of through-wall-cracked pipe, nance of fitness-for-duty (FFD) policies and programs. It has (5) evaluation of the effect of off-centered cracks (6) evaluation been prepared as a resource for Nuclear Regulatory Commis-of the effect of restraint of pressure induced bending, and (7) sion (NRC) and nuclear power plant personnel who deal with evaluation of the effect of residual stresses on leak-rate analy-FFD programs. It contains a general overview and update on ses. Uncertainty analyses conducted relative to in-service flaw the technical issues that the NRC considered prior to the puble-evaluations were: (1) dynamic and cyclic load history effects on cation of its original FFD rule and the revisions to that rule (pre-load-carrying capacity of surface-cracked pipe, and (2) effect of sented in earlier NUREG/CRs). It also includes chapters that uncertainty in UT flaw sizing. The relative ranking of importance address issues about which there is growing concem and/or about which there have been substantial changes since is given for the significance of each technical aspect investigat-ed.
NUREG/CR-5784 was published. Although this report is intend-ed to support the NRC's rulemaking on fitness for duty, the con-NUREG/CR-6445: DEVELOPMENT OF A J-ESTIMATION clusions of the authors are their own and do not necessarily SCHEME FOR INTERNAL CIRCUMFERENTIAL AND AXIAL represent the opinions of the NRC.
SURFACE CRACKS IN ELBOWS. MOHAN,R.; BRUST,F.W.;
GHADIALt,N.; et al. Battelle Memonal institute Columbus Lab.
NUREG/CR-6473: GLOBAL POSITIONING SYSTEM REOBSER-oratones. June 1996. 68pp. 9607090154. BMI-2193. 88957:252.
VATIONS OVER THE EASTERN UNITED STATES STRAIN This report summarizes efforts to develop elastic and elastic-MONITORING NETWORK. STRANGE,W.E. Commerce, Dept.
plastic fracture mechanics analyses for internal surface cracks of, National Oceanic & Atmosphenc Administration. June 19%.
in elbows. The analyses involved development of a GE/EPRI 33pp. 9607090248. 88957:315.
type J-estimation scheme from a matrix of finite element analy-In the penod March-May,1990, a 45 station geodetic net-ses. The following parameters were covered; 90-degree long-work, originally established in November-December,1987, was radius elbows, vanous R(m)/t ratios, and combined pressure reobserved using global positioning system (GPS) technology.
and in-plane bending For the combined pressure and bending This network, known as the Eastern U.S. Strain Network, was
10 Main Citations and Abstracts established for the purpose of determining strain and deforma-to take place over a decade in order to place meaningful con-tion in the central and eastern United States. This 1990 reob-straints on the small differential movements involved.
servaton was the frst of a senes of reobservations scheduled i
Secondary Report Number Index This index lists, in alphabetical order, the performing organization-issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.
SECONDARY REPORT NUM8ER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER 04-4448-010 NUREG/CR4074 V02 INEL-95/0215 NUREG/CR4341 ANL-95/37 NUREG/CR4383 INEL-95/0383 NUREG/CR4365 ANL 95/47 NUREG/CR4428 INEL-95/0506 NUREG/CR4392 BMI-2191 NUREG/CR-6443 ORNL/TM-12980 NUREG/CR4332 BMI-2193 NUREG/CR4445 ORNL/TM-13133 NUREG/CR4413 BNL-NUREG-52425 NUREG/CR 6253 ORNL/TM-13148 NUREG/CR4424 BNL-NUREG-52467 NUREG/CR4350 N8 U
-4 V11 N2 BNL-NUREG 52480 NUREG/CR4384 V01 PNL 10006 NUREG/CR4270 BNL-NUREG-52480 NUREG/CR4384 V02 PNL 10496 NUREG/r44210 BSRC 700/96/004 NUREG/CR4470 PNL-10866 NUREG/CR4411 CNWRA 95417 NUREG/CR4401 PNL-7445 NUREG/CR-5631 R02 FEMA-REP-1 NUREG4654 R1 S2 OFC PNNL 10475 NUREG/CR-5068 INEL-94/0278 NUREG/CR 5229 V08 PNNL 11134 NUREGrCR4470 INEL-95/0061 NUREG/CR4314 PNNL-9433 NUREG/CR-6227 INEL-95/0073 NUREG/CR-6256 V03 PU.NE 94/1 NUREG/CR4309 11 l
i 4
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.
ANDERSON,C.M.
BRUST,F.W.
NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.
INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN ELBOWS.
l ARONSON A.
NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.
BRYCE.J.H.
NUREG/CR4314: OUALITY ASSURANCE INSPECTIONS FOR SHIP.
l SABELLl,L PING AND STORAGE CONTAINERS.
NUREG/CR4309. SCIENTIFIC DESIGN OF PURDUE UNIVERSITY MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE BURGHARD,H.C.
SBWR.
NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN SAFETY TESTING.Techncal Report On The Findings Of Task 4 inves-l BAGCH1,G.
tigation of Failed Nitanol Brachytherapy Wire.
NUREG-1540: BWR STEEL CONTAINMENT CORROSION.
I SURKE,W.F.
BAKER.D.A.
NUREG/CR-6428: EFFECTS OF THERMAL AGING ON FRACTURE l
NUREG/CR-2850 Sot: DOSE COMMITMENTS DUE TO RADIOACTIVE TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS RELEASES FROM NUCLEAR POWER PLANT SITES Methodology STEEL PIPE WELDS.
And Data Base.
I CARBONARO.J.
BARCH1,T.
NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL NUREG-1415 V08 NO2: OFFICE OF THE INSPECTOR OUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES. Literature GENERALSemiannual Report To Congress. October 1,1995 - March Analysis And Appendees.
31,1996.
CAREW).F.
BARRIERE.M.T.
NUREG/CR4253: PIUS CORE PERFORMANCE ANALYSIS.
NUREG/CR-6350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS i
j (ATHEANA).Techncal Basis And Methodology Desenption.
CARFAGO.S.
t NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL i
8AXTER,8.
QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES. Literature NUREG/CR-6470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
Analyssa And Appendices.
UPDATE OF THE TECHNICAL ISSUES 1996.
CHOL,Y.H.
BENAC,D.J.
NUREG/CR4443: DETERMINISTIC AND PROBABILISTIC EVALUA-NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN TiONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN SAFETY TESTING.Techncal Report On The Findings Of Task 4 inves-LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATIONS.
tigation of Failed Natinot Brachytherapy Wire.
CHOPRA,0.K.
BERTODANO,M.L NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE NUREG/CR4309-SCIENTIFIC DESIGN OF PURDUE UNIVERSITY TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE STEEL PIPE WELDS.
SBWR.
COKINOS,D.M.
BIERSCHBACH,M.
NUREG/CR-6253: PIUS CORE PERFORMANCE ANALYSIS.
I NUREG/CR4270: ESTIMATING BOILING WATER REACTOR DECOM-l MISSIONING COSTS.A User's Manual For The BWR Cost Estimating CONNELLY,S.R.
Computer Program (CECP) Software Final Report.
NUREG-1542 V01: ACCOUNTABILITY REPORT FISCAL YEAR 1995.
BITTNER.A.
COOPER,5.E.
NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
NUREG/CR-6350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS UPDATE OF THE TECHNICAL ISSUES 1996.
(ATHEANA). Technical Basis And Methodology Desenption.
SLEY,D.C.
DOCTOR,S.R.
I NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR 5068: PIPING INSPECTION ROUND ROBIN.
(ATHEANA).Techncal Basis And Methodology Descnption.
BOWERMAN.B.
NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNfVERSITY NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL MULTI-D!MENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES Literature SBWR.
Analysis And Appendees.
DURBIN,N.
BROWN K.D.
NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
NUREG.1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-UPDATE OF THE TECHNICAL ISSUES 1996.
RIALS LICENSING PROCESS REDESIGN.
NUHEG 1541 DRFT FC: PROCESS AND DESIGN FOR CONSOLIDAT.
ELLINGWOOD.B.R.
ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT Report For Comment.
REINFOHCED CONCRETE STRUCTURES.
13
14 Personal Author Index q
NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC HAUTH,J.
RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUREG/CR4470; FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
NUCLEAR POWER PLANTS.
UPDATE OF THE TECHNICAL ISSUES 1996.
FERRILL.D.A.
HEASLER,P.G.
NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR-5068: PIPING INSPECTION ROUND ROBIN.
REGION Cntcal Revew And Analyses nf Tectonc Data Frorn The NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR Central Basin And Range.
EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.
FIELD,l.
HENDERSON D.B.
NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN UPDATE OF THE TECHNICAL ISSUES 1996.
REGION Cntcal Revew And Analyses of Tectonc Data From The Central Basan And Range.
NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
HENRICH,M.J.
UPDATE OF THE TECHNICAL ISSUES 1996.
NUREG/CR4360:
SUMMARY
OF AIR PERMEABILITY DATA FROM SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED PSX,E.F.
TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF NUREG 0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-STEADY-STATE TEST INTERPRETATION.
UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER HILTON.LD.
PLANTS.Cntena For Emergency Planning in An Early Site Permit NUREG/CR4256 V03. FIELD LYSIMETER INVESTIGATIONS: LOW-Apphcation. Draft Report For Comment LEVEL W/,STE DATA BASE DEVELOPMENT PROGRAM LYSIMETER TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
GALVIN,T.M.
NUREC/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE HUBER,0.
TOUGHNESS AND CHARPY.lMPACT STRENGTH OF STAINLESS NUREG-1415 V08 NO2: OFFICE OF THE INSPECTOR STEEL PIPE WELDS.
GENERAL. Semiannual Report To Congress,0ctober 1,1995 - March GAVENDA.D.J.
NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE HUI,T.E.
TOUGHNESS AND CHARPY.lMPACT STRENGTH OF STAINLESS NUREG/CR 5631 R02: CONTRIBUTION OF MATERNAL RADIONU-STEEL PIPE WELDS.
CLIDE BURDENS TO PRENATAL RADIATION DOSES.
OEDDIS,A.M.
ISHit,M.
SUMMARY
OF AIR PERMEABILITY DATA FROM NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UN:VERSITY SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF SBWR.
STEAUWSTATE TEST INTERPRETATION.
JASTROW,J.D.
OHADIALt.N.
NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CR4443. DETERMINISTIC AND PROBABILISTIC EVALUA-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR TlONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN FISCAL YEAR 1995. Annual Report LEAK 8EFORE BREAK AND IN-SERVCE FLAW EVALUATIONS.
NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-NOREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
ELBOWS.
JOHNSON,R.E.
GLEASON.J.
NUREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL VESSEL SUPPOR TS.
QUALIFCATION OF SAFETY-RELATED ELECTRIC CABLES. Literature Analyses And Appendees.
JOY,D.R.
NUREG 0430 V15:
LICENSED FUEL FACILl"Y STATUS GRANT.T.
REPORT inventory Difference Data. July 1,1994 - June 30,1995.(Gray NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
Book 11).
UPDATE OF THE TECHNICAL ISSUES 1996.
KANTOR F.
GRODIN,M.
NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-NUREG-1415 VO8 NO2: OFFICE OF THE INSPECTOR UATION OF RADIOLOGCAL EMERGENCY RESPONSE PLANS AND GENERALSemaannual Report To Congress. October 1,1995 - March PREPAREDNESS IN SUPPORT OF NUCLEAR POWER 31,1996.
PLANTS.Cntens For Emergency Planning in An Early Site Permit Appleation. Draft Report For Comment NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS KASSNER,T.F.
OF CONTROL SOFTWARE IN ADVANCED REACTORS, NUREG/CR4383 CORROSION FATIGUE OF ALLOYS 600 AND 690 IN St.JULATED LWR ENVIRONMENTS.
SUMMARY
OF AIR PERMEABILITY DATA FROM KASTURI,S.
SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED NUREG/CR 6384 V02: LITERATURE REVIEW OF ENVIRONMENTAL TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES.Lsterature STEADY-STATE TEST INTERPRETATION.
Analysis And Appendees.
HAMILTON,M.A.
KIMME.S.
NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
ACTIVE WASTE. Final Report.
UPDATE OF THE TECHNICAL ISSUES 1996.
HAN,J.T.
KURTZ,R.J.
NUREG/CR4309: SCIENTIFC DESIGN OF PURDUE UNIVERSITY NUREG/CR4227-PERFORMANCE DEMONSTRATION TESTS FOR MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING SBWR.
LARSONJ.L HARTFIELD,R.A.
NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW.
NUREG4020 V20 LICENSED OPERATING REACTORS STATUS SUM-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR MARY REPORT.Deta As Of December 31,1995.(Gray Book l)
FISCAL YEAR 1995. Annual Report.
Personal Author index 15 LEE,8.
NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.
QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES.LiteraNre Analysis And Appendees.
OLAND.C.S.
NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT LIPWSKWE.
REINFORCED CONCRETE STRUCTURES.
NUREG 1509: RADIATION EFFECTS ON REACTOR PRESSURE VESSEL SUPPORTS.
ORlANS,C.
NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
UREd CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL UPDATE OF THE TECHNICAL ISSUES 1996.
QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES. Literature PARRY,G.W.
Analysis And Appendees.
NUREG/CR4350: A TECHNIOUE FOR HUMAN ERROR ANAL,YSIS LUCKAS,W.J.
(ATHEANA).Techncal Basis And Methodology Desenption.
NUREG/CR4350: A TECHNIOUE FOR HUMAN ERROR ANALYSIS PE (ATHEANA).Technmal Basis And Methodology DesCnption.
NUR
- 9. METHODOLOGY AND FINDINGS OF THE NRC'S MATE-MACAULAY,J.
RIALS LICENSING PROCESS REDESIGN.
NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR (NDUSTRY:
UPDATE OF THE TECHNICAL ISSUES 1996.
PENNELL,W.E.
NUREG/CR 4219 V11 N2: HEAVY-SECTION STEEL TECHNOLOGY MACDONALD P.E.
PROGRAM.Serniannual Progress Report For Apni-September 1994.
NUREG/CR-6365: STEAM GENERATOR TUBE FAILURES.
POKHARNA.H.
NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY N RE 1 39: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-RIALS LICENSING PROCESS REDESIGN.
MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE SBWR.
MCCONNELL,J.W.
NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW.
PRINCE,A.
PROGRAM FOR NUREG/CR-6253: plUS CORE PERFORMANCE ANALYSIS.
LEVEL WASTE DATA BASE DEVELOPpENT FISCAL YEAR 1995 Annual Report.
NUREG/CR-6256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW.
RAHMAN,S.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER NUREG/CR4443: DETE RMINISTIC AND PROBABILISTIC EVALUA.
TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
TONS FOR UNCERT/INTY IN PIPE FRACTURE PARAMETERS IN NUREG/CR4341: MICROBIAL DEGRADAflON OF LOW-LEVEL RADIO-LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATONS.
1 ACTIVE WASTE. Final Report.
NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE RAME Y-SMITH,A.
STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.
NUREG/CR4350: A TECHNIOUE FOR HUMAN ERROR ANALYSIS (ATHEANA).Techncal Basis And Methodology Descnption.
NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL.
RANSOM,V.H.
i l
UATON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY PREPAREDNESS IN SUPPORT OF NUCLEAR POWER MULTI DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE l
PLANTS.Cntena For Ernergency Planrung in An Early Site Permit SBWR.
Appication. Draft Report For Comrnent RATH80N,P.A.
MEZNARICH.H.K.
NUREG 1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE.
NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.
RIALS LICENSING PROCESS REDESIGN.
CLIDE BURDENS TO PRENATAL RADIATION DOSES-NUREG-1541 DRFT CC: PROCESS AND DESIGN FOR CONSOLIDAT-ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft l
LrlCHAUD,W.F i
NUREG/CR ii428: EFFECTS OF THERMAL AGING ON FRACTURE Repor1 For Comment.
TOUGHNESS AND CHARPY-tMPACT STRENGTH OF STAINLESS REVANKAR.S.T.
STEEL PIPE WELDS.
NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY MOHAN.R.
MULTI-D!MENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATON SCHEME FOR SBWR.
INTERNAL CIRCUMFERENTIAL AND AXLAL SURFACE CRACKS IN ELBOWS' RICE,EM.
NUREG/CR4332: MICROSTRUCTURAL CHARACTERIZATION OF SE-MOORE,C.
LECTED AEA/UCSB MODEL FECUMN ALLOYS.
NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
I UPDATE OF THE TECHNICAL ISSUES 1996.
ROSERTS,G.D.
i NUREG/CR4314: OVALITY ASSURANCE INSPECTIONS FOR SHIP-MORIARTY,M.
PING AND STORAGE CONTAINERS.
NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE.
RIALS LICENSING PROCESS REDESIGN.
ROGERS,R.D.
NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATONS: LOW-MORRIS A.P.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN FISCAL YEAR 1995. Annual Report.
REGION.Cntcal Review And Analyses of Tectone Data From The NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW.
Central Basin And Range.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-NUR 4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS OF CONTROL SOFTWARE IN ADVANCED REACTORS ACTIVE WASTE. Final Report.
NAUS,0.J.
R*JTHER,W.E.
NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN REINFORCED CONCRETE STRUCTURES.
SIMULATED LWR ENVIRONMENTS.
NEILSON,R.M.
SANFORD,W.E.
NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW-
)
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
FISCAL YEAR 1995. Annual Report.
t..
- ~
i 16 Personal Author Index NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-SULLIVAN,T.M.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS. LOW-TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR FISCAL YEAR 1995. Annual Report.
SELCOW,E.C.
NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CR4253: Plus CORE PERFORMANCE ANALYSIS.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
SHAH,V.N.
l NUREG/CR-6365: STEAM GENERATOR TUBE FAILURES.
TAN,C.P.
NUREG 1540. BWR STEEL CONTAINMENT CORROSION.
l SIKOV,M.R.
I NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU-TA L CLIDE BURDENS TO PRENATAL RADIATION DOSES.
UR G/C 4350. A TECHNIOUE FOR HUMAN ERROR ANALYSIS SILBERMAGEL,M.
(ATHEANA).Techncal Basis And Methodology Desenption.
t NUREG/CR-6470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL UPDATE OF THE TECHNICAL ISSUES 1996.
OUALIFICATION OF SAFETY.RELATED ELECTRIC CABLES. Literature Analysis And Appendees.
SMOOT,J.L.
NUREG/CR4411: A GEOSTATISTICAL METHODOLOGY TO ASSESS THRALL,K.D.
THE ACCURACY OF UNSATURATED FLOW MODELS.
NUREG/CR 5631 R02: CONTRIBUTION OF MATERNAL RADIONU-CLIDE BURDENS TO PRENATAL RADIATION DOSES.
SONG,J.
NUREG/CR-6425: IMPACT OF STRUCTUCiAL AGING ON SEISMIC TOOHEY,R.E.
RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR.
NUCLEAR POWER PLANTS.
MACEUTICALS.
SOPPET.W.K.
TOQUAM J.
NUREG/CR4383. CORHOslON FATIGUE OF ALLOYS 600 AND 690 IN NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
SIMULATED LWR ENVIRONMENTS' UPDATE OF THE TECHNICAL ISSUES 1996.
SPlVEY,K.H.
TRAUS R.J NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.
REGION.Cntcal Review And Analyses of Tectonc Data From The CLlDE BURDENS TO PRENATAL RADIATION OOSES.
Central Basin And Range.
USILTON,W.K.
M.G STABIN'G/CR 6345:
NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-NURE RADIATION DOSE ESTIMATES FOR RADIOPHAR.
RIALS LICENSING PROCESS REDESIGN.
MACEUTICALS.
VACCA P.C.
STAGE.S.A.
NUREG/CR4210: COMPUTER CODES FOR EVALUATION OF CON.
NUREG 1539 METHODOLOGY AND FINDINGS OF THE NRC'S MATE-RIALS LICENSING PROCESS REDESIGN.
TROL ROOM HABITABILITY (HABIT).
NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOLIDAT.
STAMATAKOS.J.
ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft i
NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN Report For Comment.
REGION Cntcal Review And Analyses of Tectonc Data From The Centra! Basin And Range.
VEEH.R.H.
NUREG/CR4341: MICROBlAL DEGRADATION OF LOW LEVEL RADIO-STlREWALT,G.L.
ACTIVE WASTE. Final Report.
NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN REGION.Cntcal Revew And An dyses of Tectonec Data From The VILLARAN.M.
Central Basin And Range.
NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES Literature NUREG/C'R 6332; MICROSTRUCTURAL CHARACTERl2ATION OF SE-LECTED AEA/UCSB MODEL FECUMN ALLOYS VISKANTA,R.
NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY
^
N REG /Chl4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL B
R~
OUALIFICATION OF SAFETY.RELATED ELECTRIC CABLES. Literature Analysis And Apper4ces.
WANG,J.A.
NUREG/CR4413: ANALYSIS OF THE lARADIATION DATA FOR A3028 STRANGE,W.E AND A5338 CORRELATION MONITOR MATERIALS.
NUREG/CR4473: GLOBAL POSITIONING SYSTEM REOBSERVA.
TIONS OVER THE EASTERN UNITED STATES STRAIN MONITOR-WANG,W.
I ING NETWORK.
NUREG/CA-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE STROM8 ERG,H.M.
SBWR.
NUREG/CR4314: OUALITY ASSURANCE INSPECTIONS FOR SHIP.
PING AND STORAGE CONTAINRS.
WARD LW.
J NUREG/CR4365: STEAM GENERATOR TUBL FAILURES.
STRUCKMEYER,R.
NUREG-0837 V16 N01: NRC TLD DIRECT RADIATION MONITORING j
M NETWORK. Progress Report. January-March 1996.
NUREG 415 V08 NO2.
OFFICE OF THE INSPECTOR STUBBS,J.B..
GENERALSemiannual Report To Congress October 1,1995 - March NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR.
31,1996.
l MACEUTICALS.
I WERNICKE,8.P.
I SUBUDHI,M.
NUREG/CR 6401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR4384 V01: LITERATURE BEVIEW OF ENVIRONMENTAL REGION Cntcal Revew And Analyses of Tectonc Data From The OUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES Summary Central Basin And Range, i
Of Past Work.
l NUREG/CR-6384 V02: LITERATURE REVIEW OF ENVIRONMENTAL WHITTEN,J.E.
l QUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES. Literature NUREG 1539. METHOOOLOGY AND FINDINGS OF THE NRC'S MATE-Analysis And Appendees.
RIALS LICENSING PROCESS REDESIGN.
4 Personal Author index 17 NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOLIDAT-WINGERT,V.L ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft NUREG 0654 R1 S2 DFC. CRITERIA FOR PREPARATION AND EVAL-Repor1 For Comment.
UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER WILKOWSKI,G.
NUREG/CR-6445. DEVELOPMENT OF A J-ESTIMATION SCHEME FOR PLANTS Critena For Emergency Planning in An Earty Site Permit INTERNAL CIRCUMFERENTIAL AND AXlAL SURFACE CRACKS IN Appleation. Draft Report For Comment.
ELBOWS.
WREATHALL.J.
^
NUREG[CRd411: A GEOSTATISTICAL METHODOLOGY TO ASSESS (A
AA nial an A e
I gy senp m THE ACCURACY OF UNSATURATED FLOW MODELS.
T A'I'M-WILMARTH T.
NUREG/CR-6309. SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NUREG/CR-6465: DEVELOFMENT OF TOOLS FOR SAFETY ANALYSIS MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE OF CONTROL SOFTWARE IN ADVANCED REACTORS.
SBWR.
ZEBELMAN,A.
WILSON,R.
NUREG/CR4170: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
NUREG/CR-6470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
UPDATE OF THE TECHNICAL ISSUES 1996.
UPDATE OF THE TECHNICAL ISSUES 1996.
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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.
10 CFR Part 61 Compresolve Testing NUREG-1437 V01: GENERIC ENVIRONMENTAL IMPACT STATEMENT NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE FOR LICENSE RENEWAL OF NUCLEAR PLANTS. Main Report.
STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.
NUREG-1437 V02: GENERIC ENVIRONMENTAL IMPACT STATEMENT FOR LICENSE RENEWAL OF NUCLEAR PLANTS. Appendices.
Computer Code NUREG-1529 V01: PUBLIC COMMENTS ON THE PROPOSED 10 CFR NUREG/CR-6210: COMPUTER CODES FOR EVALUATION OF CON-PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP' TROL ROOM HABITABILITY (HAB!T).
ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF CONCERNS AND NRC STAFF RESPONSE Executive Summary.
Concrete NUREG 1529 V02: PUBLIC COMMENTS ON THE PROPOSED 10 CFR NUREG" R4341: MICROBIAL DEGRADATION OF LOW LEVEL RADIO.
PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.
ACTIVE WASTE. Final Report.
ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF CONCERNS AND NRC STAFF RESPONSE.Apperdces.
Consolidation NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOLIDAT-ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft NUR 5 V17: A COMPILATION OF REPORTS OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS.1995 Annual.
Repat 6 hnt Containment AccountatWi6ty Report WUREG-1542 Vot: ACCOUNTABILITY REPORT FISCAL YEAR 1995.
NUREG-1540: BWR STEEL CONTAINMENT CORROSION.
Advanced Reactor Control Room HetWtatWilty NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS NUREG/CR4210: COMPUTER CODES FOR EVALUATION OF CON-OF CONTROL SOFTWARE IN ADVANCED REACTORS.
TROL ROOM HABITABILITY (HABIT).
Aging Control Software NUREG/CR4365: STEAM GENERATOR TUBE FAILURES NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS NUREG/CR4384 V01: LITERATURE REVIEW OF ENVIRONMENTAL OF CONTROL SOFTWARE IN ADVANCED REACTORS.
OVALIFICATION OF SAFETY RELATED ELECTRIC CABLES. Summary Of Past Work.
Core Performance NUREG/C34392: THE EFFECTS OF AGING ON COMPRESSIVE NUREG/CR4253: PlVS CORE PERFORMANCE ANALYSIS.
STRENGTH OF LOW LEVEL RADIOACTIVE WASTE FORMS.
NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT Correlation Monitor Material NUREG/CR4413: ANALYSIS OF THE IRRADIATION DATA FOR A3028 NUR /CR44 5 4 S
RAL AGING ON SEISMIC AND A5338 CORRELATION MONITOR MATERIALS.
RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUCLEAR POWER PLANTS.
Corroolon Air PermeetWuty NUREG 1540: BWR STEEL CONTAINMENT CORROSION.
NUREG/CR4360:
SUMMARY
OF AIR PERMEABILITY DATA FROM NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF NUCLEAR POWER PLANTS.
i
(
STEADY-STATE TEST INTERPRETATION.
A80y 800 NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 600 IN SIMULATED LWR ENVIRONMENTS.
SIMULATED LWR ENVIRONMENTS.
Cost Analysis Axlel Surface Crack NUREG/CR4270: ESTIMATING BOILING WATER REACTOR DECOM-NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR MISSIONtNG COSTS.A User's Manual For The BWR Cost Estimating INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN Computer Program (CECP) Software.Finas Geport.
ELBOWS.
Crack Growth j
UREG-1540 BWR STEEL CONTAINMENT CORROSION.
S TE L R V MENT ~
NUREG/CR4270 ESTlMATING BOILING WATER REACTOR DECOM-MISSIONING COSTS.A User's Manual For The BWR Cost Estirnating Decommissioning
(
Computer Program (CECP) Software. Final Rem NUREG/CR4270: ESTIMATING BOILING WATER REACTOR DECOM-SoNing Water Reactor MISSIONING COSTS.A User's Manual For The BWR Cost Estimating NUREG-1540- BWR STEEL CONTAINMENT CORROSION.
Computer Program (CECP) Softwarennal Report.
NUREG/CR4270- ESTIMATING BOILING WATER REACTOR DECOM-MISSIONING COSTS.A User's Manual For The BWR Cost Estimating Degradenen Mechanism Computer Program (CECP) Software. Final Report.
NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.
Drachytherapy Dev6ce Des 6gn j
NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN f'
SAFETY TESTING.Techracal Report On The Firdngs Of Task 4 inves-SAFETY TESTINC Technical Report On The Findings Of Task 4 inves-tigation of Failed Nitinot Brachytherapy Wre.
tigation of Failed Natinot Brachytherapy Wire.
1 19
.. -~ - -
20 Subject index i
Does Commitment Fracture Mechanico NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREC/CR4443: DETERMINISTIC AND PROBABILISTIC EVALUA-RELEASES FROM NUCLEAR POWER PLANT SITES. Methodology TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN And Data Base.
LEAK-BEFORE BREAK AND IN-SERVICE FLAW EVALUATIONS.
NUREG/CR4445: DEVELOPMENT OF A SESTIMATION SCHEME FOR R
4470 FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
E WS UPDATE OF THE TECHNICAL ISSUES 1996.
Fracture Toughness NUREG/CR4i28: EFFECTS OF THERMAL AGING ON FRACTURE G/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR EEL PIPE WE S'
FISCAL YEAR 1995. Annual Report.
Fractured Rock R
R1 S2 OFC: CRITERIA FOR PREPARATION AND EVAL-NUREG/CR-6360:
SUMMARY
OF AIR PERMEABILITY DATA FROM UATON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED PREPAREDNESS IN SUPPORT OF NUCLEAR POWER TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF STEADY STATE TEST INTERPRETATION.
PLANTS.Cntena For Emergency Planning in An Early Site Permet Application. Draft Report For Comment.
Geostatiette Eddy Current NUREG/CR4411: A GEOSTATISTICAL METHODOLOGY TO ASSESS NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR THE ACCURACY OF UNSATURATED FLOW MODELS.
EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING
)
Global Posit 6oning System Elbow NUREG/CR4473: GLOBAL POSITIONING SYSTEM REOBSERVA.
NUREGICR4445: DEVELOPMENT OF A SESTIMATON SCHEME FOR TIONS OVER THE EASTERN UNITED STATES STRAIN MONITOR-1 INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN ING NETWORK.
Health Physic Electric Cable NUREG/CR-6345: RADIATION DOSE ESTIMATES FOR RADIOPHAR.
I NUREG/CR4384 V01: LITERATURE REVIEW OF ENVIRONMENTAL MACEUTICALS.
OUALIFICATION OF SAFETY-RELATED ELECTRIC CABLES. Summary Of Part Work.
Heat Transfer NUREG/CR4253: PlUS CORE PERFORMANCE ANALYSIS.
Embrittlement NUREG/CR4413: ANALYSIS OF THE IRRADIATION DATA FOR A3028 Heavy-Section Steel Technology Program AND A5338 CORRELATION MONITOR MATERIAL S.
NUREG/CR-4219 Vit N2: HEAVY SECTION STEEL TECHNOLOGY PROGRAM Sem. annual Progress Report For Apni-September 1994.
NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATON AND EVAL-H6gh-Level Weste Repooltory UATON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN PREPAREDNESS IN SUPPORT OF NUCLEAR POWER REGION.Cntical Review And Analyses of Tectonic Data From The PLANTS.Cntena For Emergency Plannen0 in An Early Site Permit Central Basin And Range.
ApplicatiortDraft Report For Comment.
Human Error Analysis Env6ronmental impact Statement NUREG/CR-6350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG-1437 V01: GENERIC ENVIRONMENTAL IMPACT STATEMENT (ATHEANA).Technscal Basis And Methodology Desenption.
FOR LICENSE RENEWAL OF NUCLEAR PLANTS Main Report.
1 I
NUREG-1437 V02: GENERIC ENVIRONMENTAL IMPACT STATEMENT Humen Factore EnCneering FOR LICENSE RENEWAL OF NUCLEAR PLANTS Appendices.
NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG-1529 V01: PUBLIC COMMENTS ON THE PROPOSED 10 CFR (ATHEANA). Technical Basis And Methodology Desenption.
PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF Hydrology CONCERNS AND NRC STAFF RESPONSE. Executive Summary.
NUREG/CR4411: A GEOSTATISTICAL METHODOLOGY TO ASSESS NUREG-1529 V02: PUBLIC COMMENTS ON THE PROPOSED 10 CFR THE ACCURACY OF UNSATURATED FLOW MODELS.
PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.
i ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF inservice Fisw CONCERNS AND NRC STAFF RESPONSE. Appendices-NUREG/CR4443. DETERMINISTIC AND PROBABILtSTIC EVALUA-TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN NA CR 63 TERATURE REVIEW OF ENVIRONMENTAL QUAllFICATION OF SAFETY RELATED ELECTRIC CABLES. Summary inservice inspection Of Past Work.
NUREG/CR-5068. PIPING INSPECTON ROUND ROBIN.
EnWonmental Review integral System Scaling NUREG-1440: REGULATORY ANALYSIS FOR AMENDMENTS TO REG-NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY ULATIONS FOR THE ENVIRONMENTAL REVIEW FOR RENEWAL OF MULTl DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUCLEAR POWER PLANT OPERATING LICENSES. Final Report SDWR.
Failure Mode NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NU E / 5229 V08. FIELD LYSIMETER INVESTIGATIONS. LOW-(ATHEANA). Technical Basis And Methodology Desenptson.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR Fault 6ng FISCAL YEAR 1995. Annual Report.
NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE REGION Cntical Review And Analyses of Tectonic Data From The STRENGTH OF LOW LEVEL RADIOACTIVE WASTE FORMS.
Central Basin And Range.
Financial Statement NUREG/CR-6332: MICROSTRUCTURAL CHARACTERIZATION OF SE-NUREG-1542 V01: ACCOUNTABILITY REPORT FISCAL YEAR 1995.
LECTED AEA/UCSB MODEL FECUMN ALLOYS.
Fitnese For Duty irradiation Data NUREG/CR-6470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
NUREG/CR4413: ANALYSIS OF THE IRRADIATION DATA FOR A302B UPDATE OF THE TECHNICAL ISSUES 1996.
AND A5338 CORRELATION MONITCR MATERIALS.
Subject index 21 J-Estimet6on Scheme Lysimeter NUREG/CR4445: DEVELOPMENT OF A J-ESTIMATION SCHEME FOR NUREG/CR-5229 V00: FIELD LYSIMETER INVESTIGATIONS: LOW-INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR ELBOWS.
FISCAL YEAR 1995. Annual Report.
NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS. LOW-LWR LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER NUREG/CR-6383; CORROSION FATIGUE OF ALLOYS 600 AND 690 IN TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
SIMULATED LWR ENVIRONMENTS.
LWR Edition NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOLIDAT-NUREG4800 DRFT FC. STANDARD REVIEW PLAN FOR THE REVIEW ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER Report For Comment.
PLANTS. LWR Edition. Draft Report For Comment.
Leak-Before-8reak Materials Licensing NUREG/CR4443: DETERMINISTIC AND PROBABILISTIC EVALUA.
NUREG 1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-TlONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN RIALS LICENSING PROCESS REDESIGN.
NUREG-1541 DRFT FC: PROCESS AND DESIGN FOR CONSOLIDAT-LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATIONS.
ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft Legal issuances Report For Comment.
NUREG-0750 V43101: INDEXES TO NUCLEAR REGULATORY COM-MISSION ISSUANCES. January-March 1996.
M6crobial Degradation NUREG-0750 V43 NO2: NUCLEAR REGULATORY COMMISSION IS-NUREG/CR-6341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-SUANCES FOR FEBRUARY 1996. Paoes 13-49.
ACTIVE WASTE. Final Report.
NUREG-0750 V43 NO3: NUCLEAR REGULATORY COMMISSION IS-SUANCES FOR MARCH 1996. Pages51-121.
M6crostructural Characterization NUREG-0750 V43 N04: NUCLEAR REGULATORY COMMISSION IS-NUREG/CR4332: MICROSTRUCTURAL CHARACTER 12ATION OF SE-SUANCES FOR APRIL 1996.Page 123-210.
LECTED AEA/UCSB MODEL FECUMN ALLOYS.
License Renewal Nitinoi NUREG 1437 VOI: GENERIC ENVIRONMENTAL IMPACT STATEMENT NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN NU EG 02 E ER NV NMEN AL I T
T'EMENT SAFETY TESTING. Technical Report On The Findings Of Task 4 inves.
tigation of Failed Nitinol Brachytherapy Wire.
FOR LICENSE RENEWAL OF NUCLEAR PLANTS Appendices.
NUREG-1440: REGULATORY ANALYSIS FOR AMENDMENTS TO REG-nDestrudve Eveen ULATIONS FOR THE ENVIRONMENTAL REVIEW FOR RENEWAL OF NUREG/CR-5068: PIPING INSPECTION ROUND ROBIN.
NUCLEAR POWER PLANT OPERATING LICENSES Final Report NUREG/CR4424 REPORT ON AGING OF NUCLEAR POWER PLANT NUREG-1529 V01: PUBLIC COMMENTS ON THE PROPOSED 10 CFR REINFORCED CONCRETE STRUCTURES.
PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF Nuclear industry NU EG VO B1 M
S T'H RO k1'O CFR NUREG/CR-6470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
UPDATE OF THE TECHNICAL ISSUES 1996.
PART 51 RULE FOR RENEWAL OF NUCLEAR POWER FLANT Op.
ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF Nuclear Material CONCERNS AND NRC STAFF RESPONSE. Appendices NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC*S MATE.
RIALS LICENSING PROCESS REDESIGN.
Licensed Fuel Facility Status Report NUREG 0430 V15:
LICENSED FUEL FACILITY STATUS O o n
or R
T. inventory Difference Data. July 1,1994 June 30,1995.(Gray p
OFFICE OF THE INSPECTOR GENERALSemiannual Report To Congress. October 1,1995 March Licensed Operating Reactor 31,1996.
NUREG-0020 V20: LICENSED OPERATING REACTORS STATUS SUM-l MARY REPORT. Data As Of December 31,1995.(Gray Book I)
PlOS NUREG/CR4253: PlUS CORE PERFORMANCE ANALYSIS.
Licensing Process
)
NUREG-1539: METHODOLOGY AND FINDINGS OF THE NRC'S MATE-Packaging inspection RIALS LICENSING PROCESS REDESIGN.
NUREG/CR4314: OUALITY ASSURANCE INSPECTIONS FOR SHIP-PING AND STORAGE CONTAINERS.
Light Water Reactor NUREG-0800 DRFT FC: STANDARD REVIEW PLAN FOR THE REVIEW Performance Assessment OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER NUREG/CP 0150: WORKSHOP ON ROCK MECHANICS ISSUES IN RE-PLANTS LWR Edition Draft Report For Comment.
POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN Holiday Inn Crowne Plaza, Rockville Maryland, September 19-20, 1994.
SIMULATED LWR ENVIRONMENTS.
Performance Measure NUREG 1542 V01: ACCOUNTABILITY REPORT FISCAL YEAR 1995.
/
ENTIFIC DESIGN OF PURDUE UNIVERSITY MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE
- pip, SBWR-NUREG/CR4443. DETERMINISTIC AND PROBABILISTIC EVALUA.
TlONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN I
Low-Level Rad 6oactive Waste LEAK BEFORE BREAK AND IN-SERVICE FLAW EVALUATIONS NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW, LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER NU EG/CR 5068: PtPING INSPECTION ROUND ROBIN.
Nt
/
1 RB DEGRADAT NO L LEVEL RADIO-ACTIVE WASTE. Final Report.
NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE Pneumatic inject 6on NUREG/CR-6360:
SUMMARY
OF AIR PERMEABILITY DATA FROM STRENGTH OF LOW LEVEL RADIOACTIVE WASTE FORMS.
S!NGLE HOLE INJECTION TESTS IN UNSATURATED FRACTURED Low-Level Weste Data Base TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF NUREG/CR-5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW.
STEADY STATE TEST INTERPRETATION.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR Practice And Procedure D6 gest FISCAL YEAR 1995. Annual Report.
NUREG/CR-6256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG-0386 D07: UNITED STATES NUCLEAR REGULATORY COM-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER MISSION STAFF PRACTICE AND PROCEDURE DIGEST.Commisson, TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
Appeal Board And Ucenssng Board Decisions. July 1972 - June 1995.
}
I 22 Subject index Prenstel Does Rock Mechanico NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU-NUREG/CP-0150: WORKSHOP ON ROCK MECHANICS ISSUES IN RE-CLIDE BURDENS TO PRENATAL RADIATION DOSES.
POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At y
Holiday Inn Crowne Plaza, Rockville, Maryland, September 19-20, 1994.
NUREG/CR4332: MICROSTRUCTURAL CHARACTER 12ATION OF SE-Rules Of Practice LECTED AEA/UCSB MODEL FECUMN ALLOYS-NUREG 0386 007: UNITED STATES NUCLEAR REGULATORY COM-MISSION STAFF PRACTICE AND PROCEDURE DIGEST.Comrnission, 1
NUREG-1529 V01: PUBLIC COMMENTS ON THE PROPOSED 10 CFR Appeal Board And Licensing Board DeosionsJuly 1972 - June 1995.
j PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-SSWR ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF NUREG/CR4309: SC!ENTIFIC DESIGN OF PURDUE UNIVERSITY W1'O CFR MULTI-DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NU 5
2 Bi M
TH R PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.
SBWR.
ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW OF CONCERNS AND NRC STAFF RESPONSE. Appendices.
N E R4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALYSIS Quelley Assurance OF CONTROL SOFTWARE IN ADVANCED HEACTORS.
{
NUREG/CR-6314: OUALITY ASSURANCE INSPECTIONS FOR SHIP-PING AND STORAGE CONTAINERS.
Safety Analysis Repwt NUREG-0800 DRFT FC: STANDARD REVYW PLAN FOR THE REVIEW Radletion Does OF SAFETY ANALYSIS REPORTb FOR NUCLEAR POWER NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.
PLANTS. LWR Edition. Draft Report For Comment CLIDE BURDENS TO PRENATAL RADIATION DOSES.
NUREG/CR-6345: RADIATION DOSE ESTIMATES FOR RADIOPHAR-Sealed Source MACEUTICALS.
NUREG/CR4074 V02: SEALED SOURCE AND DEVICE DESIGN SAFETY TESTING. Technical Report On The Findings Of Task 4 inves-
- 509 RADIATION EFFECTS ON REACTOR PRESSURE VESSEL SUPPORTS.
Seiernic P6ek Asessement NUREGiCR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC RISK SESSME OF R INFORCED CONCRETE STRUCTURES IN CR S01: DOSE COMMITMENTS DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES. Methodology
^
And Data Base.
Severe Accident m.uP=8 Emwgency Response Plan NUREG 1540: BWR STEEL CONTAINMENT CORROSION.
NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-UATiON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY 1
PREPAREDNESS (N
SUPPORT OF NUCLEAR POWER PLANTS.Cntens For Ernergency Planning in An Earty S6e Permit MU TI-DIMENS'ONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE Apphcaton. Draft Report For Comment.
Medionudde Site Cherectorizat6on NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.
NUREG/CP-0150: WORKSHOP ON ROCK MECHANICS ISSUES IN RE-CLIDE BURDENS TO PRENATAL RADIATION DOSES.
POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At NUREG/CR4210: COMPUTER CODES FOR EVALUATION 05 CON.
Holiday Inn Crowne Plaza Rockville, Maryland, September 19-20, 1994.
TROL ROOM HABITABILITY (HABIT).
Spent Fuel Dry Storage System Redlopharmaceutical NUREG/CR4314: QUALITY ASSURANCE INSPECTIONS FOR SHIP.
NUREG/CR4345: RADIATION DOSE ESTIMATES FOR RADIOPHAR.
PING AND STORAGE CONTAINERS.
MACEUTICALS.
Standard Revlow Plan Reactor Proeoure vessel NUREG-0800 DRFT FC: STANDARD REVIEW PLAN FOR THE REVIEW NUREG 1509: RADIATION EFFECTS ON REACTOR PRESSURE OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER VESSEL SUPPORTS-PLANTS. LWR Editen. Draft Report For Comment Reactor Safety Steam Generator NUREG/CR4350: A TECHNIQUE FvR HUMAN ERROR ANALYSIS NUREG/CR4227 PERFORMANCE DEMONSTRATION TESTS FOR (ATHEANA).Techrucal Basse And Methodology Descnpton.
EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.
twy hd TN W NUREG/CR4365: STEAM GENERATOR TUBE FAILURES.
NUREG-0304 V20 N04: REGULATORY AND TECHNICAL REPORTS Strain Monttwing Network CT R"^
F NUREG/CR4473: GLOBAL POSITIONING SYSTEM REOBSERVA.
PEG HN C EPORTS (ABSTRACT INDEX JOURNAL). Compilaton For First Quarter TlONS OVER THE EASTERN UNITED STATES STRAIN MONITOR-1996, January-March.
ING NETWORK.
Regulatory impact Analysis Structural Rollehditty NUREG-1440: REGULATORY ANALYSIS FOR AMENDMENTS TO REG-NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT ULATIONS FOR THE ENVIRONMENTAL REVIEW FOR RENEWAL OF REINFORCED CONCRETE STRUCTURES.
NUCLEAR POWER PLANT OPERATING LICENSES Final Report.
S el Supped Reinforced Concrete NUREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT VESSEL SUPPORTS.
REINFORCED CONCRETE STRUCTURES.
NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SEISMIC TLD RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUREG-0837 V16 N01: NRC TLD DIRECT RADIATION MONITORING NUCLEAR POWER PLANTS.
NETWORK. Progress Report. January-March 1996.
N - _%, Design Tectonic Date NUREG/CP-0150 WORKSHOP ON ROCK MECHANICS ISSUES IN RE.
NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At REGION Cntical Review And Analyses of Tectonic Data From The Hohday Inn Crowne Plaza, Roavwe, Maryland, September 19-20, 1994.
Central Basin And Rarige.
Subject index 23 l
I Thermal Aging Tube lnepect6on NUREG/CR4428: EFFECTS OF THERMAL AGING ON FRACTURE NUREG/CR4227: PERFORMANCE DEMONSTRATION TESTS FOR TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS EDDY CURRENT INSPECTION OF STEAM GENEl% TOR TUBING.
STEEL PIPE WELDS-Unasturated Flow NUREG/CR4360:
SUMMARY
OF AIR PERMEABILITY DATA FROM SINGLE + TOLE INJECTION TESTS IN UNSATURATED FRACTURED NUREG4837 V16 N01: NRC TLD DIRECT RAD:ATION MONITORING TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF NETWORK. Progress Report. January March 1996.
STEADY STATE TEST INTERPRETATION.
Tlt6e List Unnaturated Zone NUREG/CR-6411: A GEOSTATISTICAL METHODOLOGY TO ASSESS NUREG4540 V18 N01: TITLE LIST OF DOCUMENTS MADE PUBLICLY THE ACCURACY OF UNSATURATED FLOW MODELS.
AVAILABLE. January 1 31,1996.
NUREG-0540 V18 NO2: TITLE LIST OF DOCUMENTS MADE Pui3LICLY Vendor inspect 6on AVAILABLE. February 1-29,1996.
NUREG4040 V20 N01: LICENSEE CONTRACTOR AND VENDOR IN-NUREG4540 V18 NO3: TITLE LIST OF DOCUMENTS MADE PUBLICLY SPECTION STATUS REPORT. Quarterty Reportanuary-March AVAILABLE March 1-31,1996.
1996.(White Book)
NUREG4540 V18 N04. TITLE LIST OF DOCUMENTS MADE PUBLICLY W
AVAILABLE April 1 30,1996.
REG /CR4428: EFFECTS OF THERMAL AGING ON FRACTURE TOUGHNESS AND CHARPY lMPACT STRENGTH OF STAINLESS STEEL PIPE WELDS' NUREG/CR4314: QUALITY ASSURANCE INSPECTIONS FOR SHIP.
PING AND STORAGE CONTAINERS.
Yucca Mounta6n NUREG/CR4401: FAULTING IN THE YUCCA MOUNTAIN Tube Feliure REGION.Cntical Review nnd Analyses of Tectonic Data From The NUREG/CR4365: STEAM GENERATOR TUBE Fall URFS Central Basin And Rarge.
)
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1 1
I
NRC Originating Organization Index (Staff Reports)
This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by 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)
U.S. NUCLEAR REGULATORY COMMISSION ACRS ADVISORY COMMITTEE ON REACTOR SAFEGUARDS OFFICE OF THE GENERAL COUNSEL (POST 860701)
NUREG-1125 V17: A COMPILATION OF REPORTS OF THE ADVISO-NUREG-0386 D07: UNITED STATES NUCLEAR REGULATORY COM-RY COMMITTEE ON REACTOR SAFEGUARDS.1995 Annual-MISSION STAFF PRACTICE AND PROCEDURE
- mason, al M N Wnsq M OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
REGION 1 (POST 820201)
Decis ons July 1972 - June 1995.
NUREG 0837 V16 N01: NRC TLD DIRECT RADIATION MONITORING OFFICE OF THE INSPECTOR GENERAL (POST 890417)
NUREG 1415 V08 NO2: OFFICE OF THE INSPECTOR NETWORK. Progress Report. January-March 1996.
GENERAL.Semsannual Report To Congress October 1,1995 March 31,1996.
EDO - OFFICE OF ADMINISTRATION (PRE 870413 & POST $90205) RV-DIVISION OF FREEDOM OF INFORMATION & PUBLICATIONS SE ICES (POST 940714 EDO OFFICE OF NUCLEAR REGULATORY RESEARCH iPOST 820405)
NUREG 0304 V20 N04: REGULATORY AND TECHNICAL REPORTS DIVISION OF ENGINEERING TECHNOLOGY (POST 941217)
(ABSTRACT INDEX JOURNAL). Annual Compilation For 1995.
NUREG 1509: RADIATION EFFECTS ON REACTOR PRESSURE NUREG-0304 V21 NO1: REGULATORY AND TECHNICAL REPORTS VESSEL SUPPORTS (ABSTRACT INDEX JOURNAL). Compilation For First Quarter DIVISION OF REGULATORY APPLICATIONS (POST 941217) 1996. January March.
NUREG-1437 V01: GENERIC ENVIRONMENTAL IMPACT STATE-NUREG-0540 V18 NO1: TITLE LIST OF DOCUMENTS MADE PUBLIC.
MENT FOR LICENSE RENEWAL OF NUCLEAR PLANTS Main LY AVAILABLE. January 1 31,1996.
Report.
NUREG-0540 V18 NO2: TITLE LIST OF DOCUMENTS MADE FJBLIC-NUREG-1437 V02: GENERIC ENVIRONMENTAL IMPACT STATE-LY AVAILABLE. February 1 29,1996 MENT FOR LICENSE RENEWAL OF NUCLEAR NUREG 0540 V18 NO3: TITLE LIST OF DOCUMENTS MADE PUBLIC-PLANTS. Appendices.
LY AVAILABLE March 1 31,1996-NUREG-1440: REGULATORY ANALYSIS FOR AMENDMENTS TO NUREG-0540 V18 N04: TITLE LIST OF DOCUMENTS MADE PUBLIC-REGULATIONS FOR THE ENVIRONMENTAL REVIEW FOR RE-N EG-0 50 V4 10 1 E ES TO NUCLEAR REGULATORY COM-C S
Re h
LATORY COMMISSION IS.
NUREG-1529 V01: PUBLIC COMMENTS ON THE PROPOSED 10 CFR NU 4 NO2 NU A
PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP.
SUANCES FOR FEBRUARY 1996. Pa NUREG-0750 V43 NO3: NUCLEAR REbes 13-49 ULATORY COMMISSION IS.
ERATING LICENSES AND SUPPORTING DOCUMENTS. REVIEW SUANCES FOR MARCH 1996. Pa OF CONCERNS AND NRC STAFF RESPONSE. Executive Summary.
NUREG-0750 V43 N04. NUCLEAR hes 51121 EGULATORY COMM!S$ ION IS.
NUREG-1529 V02: PUBLIC COMMENTS ON THE PROPOSED 10 CFR SUANCES FOR APRIL 1996.Page 123-210.
PART 51 RULE FOR RENEWAL OF NUCLEAR POWER PLANT OP-ERATING LICENSES AND SUPPORTING DOCUMENTS: REVIEW EDO - OFFICE OF THE CONTROLLER (PRE 820418 & POST 890205)
OF CONCERNS AND NRC STAFF RES'ONSE. Appendices OFFICE OF THE CONTROLLER (POST 890205)
DIVISION OF SYSTEMS TECHNOLOGY (POST 941217)
NUREG-1542 V01: ACCOUNTABILITY REPORT FISCAL YEAR 1995.
NUREG/CR-6309: SCIENTIFIC DESIGN OF PURDUE UN!VERSITY
^
EDO-OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM SW NUREG/CR-6350: A TECHNIOUE FOR HUMAN THROR ANALYSIS O C l FORMATION RESOURCES MANAGEMENT (POST (ATHEANA). Technical Basis And Methodolog Ducnption.
890205)
NUREG-0020 V20. LICENSED OPERATING REACTORS STATUS EDO OFFICE OF NUCLEAR REAC10R REGULATION (POST 800428)
SUMMARY
REPORT Data As Of December 31,1995.(Gray Book 1)
OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)
NUREG-0040 V20 NO1: LICENSEE CONTRACTOR AND VENDOR IN-EDO - OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS SPECTION STATUS REPORT. Quarterly Report January-March NUREG-0430 V15: LICENSED FUEL FACluTY STATUS 1996 (White Bool()
REPORT. Inventory Difference Data. July 1,
1994 - June 30, NUREG-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-1995 (Gray Book 11)
UAGON OF RADIOLOGICAL EMERGENCY RESPONSE PLANS DIVISION OF INDUSTRlAL & MEDICAL NUCLEAR SAFETY (POST AND PREPAREDNESS IN SUPPORT OF NUCLEAR POWER 870729)
PLANTS.Cntena For Emergency Planning in An Early Site Permit NUREG 1539: METHODOLOGY AND FINDINGS OF THE NRC'S MA.
Apphcat on. Draft Report For Comment.
TERIALS LICENSING PROCESS REDESIGN NUREG-0800 DRFT FC: STANDARD REVIEW PLAN FOR THE NUREG-1541 DRFT FC. PROCESS AND DESIGN FOR CONSOLIDAT-REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR ING AND UPDATING MATERIALS LICENSING GUIDANCE. Draft POWER PLANTS LWR Editon Draft Report For Comment.
Report For Comment.
NUREG-1540 BWR STEEL CONTAINMENT CORROSION 25
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i NRC Originating Organization Index (International Agreements)
This index lists those NRC oraanizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where appropriate. Each entry is folbad by a NUREG number and title of the report (s). If further information is needed, rA a the main citation by NUREG number.
Thwe wwo no NUREGAA reporis putdehad dunng 2 quatw t
i 27
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NRC Contract Sponsor index (Contractor Reports)
This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) prepared by that organi-zation. If further information is needed, refer to the main citation by the NUREG/CR number.
EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR-6473 GLOBAL POSITIONING SYSTEM REOBSERVA-DATA TIONS OVER THE EASTERN UNITED STATES STRAIN MONITOR-DIVISION OF SAFETY PROGRAMS (POST 870413)
ING NETWORK.
NUREG/CR4365: STEAM GENERATOR TUBE FAILURES-DIVISION OF PEGULATORY APPLICATIONS (POST 941217)
NUREG/CR-5229 V08. FIELD LYSIMETER INVESTIGATIONS: LOW-EDO-OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR4314: OUALITY ASSURANCE INSPECTIONS FOR SHIP.
FISCAL YEAR 1995. Annual Report.
PING AND STORAGE CONTAINERS.
NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU-I DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST CLIDE BURDENS TO PRENATAL RADIATION DOSES.
[
870729)
NUREGiCR4256 V03 FIELD LYSIMETER INVESTIGATIONS. LOW-NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIME-SAFETY TESTING. Technical Report On The Findings Of Task 4 In-TER TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
vestigation of Failed Nitinol Brachytherapy Wae.
NUREG/CH4270 ESTIMATING BOILING WATER REACTOR DE-NUREG/CR-6345: RADIATION DOSE ESTIMATES FOR RADIOPHAR-COMM!SSIONING COSTS A User's Manual For The BWR Cost Esti.
MACEUTICALS-mating Computer Program (CECP) Software. Final Report NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RA-i EDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)
U' MARY AIR PERMEABILITY DATA FROM EG/CR-42 1
l PROGRAM Semiannual Progress Report For Apnt-September 1994.
SINGLE HOLE INJECTION TESTS IN UNSATURATED FRACTURED NUREG/CR-5068. PIPING INSPECTION ROUND ROBIN TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF L
NUREG/CR-6227 PERFORMANCE DEMONSTRATION TESTS FOR STEADY STATE TEST INTERPRETATION.
EDDY CURRENT INSPECTION OF STEAM GENERATOR TUBING.
NUREG/CR 6392. THE EFFECTS OF AGING ON COMPRES$1VE NUREG/CR4332: MICROSTRUCTURAL CHARACTERIZATION OF STRENGTH OF LOW-LEVEL RADIOACTIVE WASTE FORMS.
SELECTED AEA/UCSB MODEL FECUMN ALLOYS NUREG/CR-6401: FAULTING IN THE YUCCA MOUNTAIN NUREG/CR4383. CORROSION FATIGUE OF ALLOYS 600 AND 690 REGION.Cntcal Review And Analyses of Tectonc Data From The IN SIMULATED LWR ENVIRONMENTS-Central Basin And Range NUREG/CR4384 V01: LITERATURE REVIEW OF ENVIRCNMENTAL NUREG/CR 6411: A GEOSTATISTICAL METHODOLOGY TO ASSESS OUAllFICATION OF SAFETY-RELATED ELECTRIC THE ACCURACY OF UNSATURATED FLOW MODELS.
^
QUAL F CA N FET R LATED LECTR TOR A
B TY T
NADIATION DATA FOR NUREG/CR-6309. SCIENTIFIC DESIGN OF PURDUE UNIVERSITY NU E R-6 1 A AL S F MULTLDIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR A302B AND A5338 CORRELATION MONITOR MATERIALS.
NUREG/CR4424. REPORT ON AGING OF NUCLEAR POWER GE SBWR.
PLAld REINFORCED CONCRETE STRUCTURES.
NUREG/CR-6350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR-6425: IMPACT OF STRUCTURAL AGING ON SEISMIC (ATHEANA). Technical Basis And Methodology Descnption.
AlSK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES NUREG/CR4465: DEVELOPMENT OF TOOLS FOR SAFETY ANALY-IN NUCLEAR POWER PLANTS SIS OF CONTROL SOFTWARE IN ADVANCED REACTORS.
NUREG/CR4428. EFFECTS OF THERMAL AGING ON FRACTURE TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)
STEEL PIPE WELDS OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)
NUREG/CR-6443. DETERMINISTIC AND PROBABILISTIC EVALUA-NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADICAC-TIONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN TIVE RELEASES FROM NUCLEAR POWER PLANT LEAK-BEFORE-BREAK AND IN-SERVICE FLAW EVALUATIONS SITES Methodology And Data Base.
NUREG/CR4445: DEVELOPMENT OF A SESTIMATION SCHEME NUREG/CR4253 PIUS CORE PERFORMANCE ANALYSIS.
FOR INTERNAL CIRCUMFERENTIAL AND AXIAL SURFACE NUREG/CR4470 FITNESS FOR DUTY IN THE NUCLEAR INDUS-CRACKS IN EtBOWS.
TRY: UPDATE OF THE TECHNICAL ISCUES 1996.
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Contractor index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation. Listed below each contractor ere the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the rnain citation by the NUREG/CR number.
ARGONNE NATIONAL LABORATORY CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES NUREG/CR 5229 V08: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CP-0150: WORKSHOP ON ROCK MECHANICS ISSUES IN RE-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR POSITORY DESIGN AND PERFORMANCE ASSESSMENT. Held At FISCAL YEAR 1995. Annual Report.
Hohday Inn Crowne Plaza. Rockville, Maryland, September 19-20. 1994.
NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CR-6401: FAULTING IN THE YUCCA MOUNTAIN LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER REGION Cntical Renew And Analyses of Tectanc Data From The l
TEST RESULTS FOR FISCAL YEARL 1994 AND 1995.
Central Basm And Range.
i l
NUREG/CR4383: CORROSION FATIGUE OF ALLOYS 600 AND 690 IN SIMULATED LWR ENVIRONMENTS.
C! MMERCE. DEPT. OF, NATIONAL OCEANIC & ATMOSPHERIC NUREG/CR 6428: EFFECTS OF THERMAL AGING ON FRACTURE ADMINISTRATION TOUGHNESS AND CHARPY-lMPACT STRENGTH OF STAINLESS NUREG/CR4473; GLOBAL POSITIONING SYSTEM REOBSERVA-STEEL PIPE WELDS-TIONS OVER THE EASTERN UNITED STATES STRAIN MONITOR-NG NETWORK.
ARI2ONA UNIV. OF, TUCSON, AZ NUREG/CR4360:
SUMMARY
OF AIR PERMEABillTY DATA FROM FEDERAL EMERGENCY MANAGEMENT AGENCY l
l SINGLE-HOLE INJECTION TESTS IN UNSATURATED FRACTURED NUREC-0654 R1 S2 DFC: CRITERIA FOR PREPARATION AND EVAL-l TUFFS AT THE APACHE LEAP RESEARCH SITE: RESULTS OF UATION OF RADIOLOGICAL EMERGENCY RESPONSE PLANS AND l
STEADY-STATE TEST INTERPRETATION-PREPAREDNESS IN SUPPORT OF NUCLEAR POWER ASCA, INC PLANTSCntena For Emergency Planning in An Earty Site Permit NUREG/CR4465: DEVELOPMENT OC TOOLS FOR SAFETY ANALYSIS ationDan Npat Fw CanmenL OF CONTROL SOFTWARE IN ADVANCED REACTORS-HALLIBURTON NUS ENVIRONMENTAL CORP.
BATTELLE MEMORIAL INSTITUTE, COLUMBUS LABORATORIES NUREG/CR-6350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR4443 DETERMINISTIC AND PROBABILISTIC EVALUA-(ATHEANA).Technmal Basis And Methodology Desenption.
TlONS FOR UNCERTAINTY IN PIPE FRACTURE PARAMETERS IN IDAHO NATIONAL ENGINEERING LABORATORY NUREG-1509: RADIATION EFFECTS ON REACTOR PRESSURE NU
/CR 45 VEL NT F
-E IMAT EME FOR INTE AL CIRCUMFERENTIAL AND AXIAL SURFACE CRACKS IN NtRE R 22 V FIELD LYSIMETER INVESTIGATIONS LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR l
BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST FISCAL YEAR 1995. Annual Report.
I LABORATORY NUREG/CR-6256 V03-FIELD LYSIMETER INVESTIGATIONS: LOW-l NUREG/CR-2850 S01: DOSE COMMITMENTS DUE TO RADIOACTIVE LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER LEASES OM NUCLEAR POWER PLANT SITES Methodology NU E /CR4314 OUAll Y SSURAN E IN NS FOR SHIP.
NUREG/CR 5068: PIPING INSPECTION ROUND ROBIN, PING AND STORAGE CONTAINERS.
NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.
NUREG/CR4341: MICROBIAL DEGRADATION OF LOW-LEVEL RADIO-CLIDE BURDENS TO PRENATAL RADIATION DOSES _
ACTIVE WASTE. Final Report.
NUREG/CR4210: COMPUTER CODES FOR EVALUATION OF CON.
NUREG/CR-6365: STEAM GENERATOR TUBE FAILURES.
TROL ROOM HABITABILITY (HABIT)
NUREG/CR4392: THE EFFECTS OF AGING ON COMPRESSIVE NUREG/CFl4227: PERFORMANCE DEMONSTRATION TESTS FOR STRENGTH OF LOW LEVEL RADIOACTIVE WASTE FORMS.
EDOY CURRENT P'SPECTION OF STEAM GENERATOR TUBING NUREG/CR-6270 ESTIMATING BOILING WATER REACTOR DECOM.
JOHNS HOPKINS UNIV., BALTIMORE, MD MISSIONING COSTS.A User's Manual For The BWR Cost Estimatmg NUREG/CR4424: REPORT ON AGING OF NUCLEAR POWER PLANT Computer Program (CECP) Software. Final Report.
REINFORCED CONCRETE STRUCTURES.
NUREG/CR4411: A GEOSTATISTICAL METMODOLOGY TO ASSESS NUREG/CR 6425: IMPACT OF STRUCTURAL AGING ON SEISMIC THE ACCURACY OF UNSATURATED FLON MO7ELS.
RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUCLEAR POWER PLANTS.
BATTELLE SEATTLE RESEARCH CENTER NUREG/CR4470: FITNESS FOR DifTY IN THE NUCLE AR INDUSTRY:
OAK RIDGE ASSOCIATED UNIVEkSITIES 7
UPDATE OF THE TECHNICAL ISSUES 1996 NUREG/CR4345. RADIATION DOSE ESTIMATES FOR RADOPHAR-MACEUTICALS.
BROOKHAVEN NATIONAL LABORATORY NUREG/CR 5229 V08: FIELD LYSIMETER INVES'lGATIONS. LOW.
CAK RIDGE NATIONAL LABORATORY LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR-4219 Vit N2: HEAVY-SECTON STEEL TECHNOLOGY FISCAL YEAR 1995. Annual Report.
PROGRAM.Semsannual Progress Report For Apni-September 1994-i l
NUREG/CR4253: PluS CORE PERFORMAl4CE A'4AL%lS.
NUREG/CR-5229 V08 FIELD LYSIMETER INVESTIGATIONS: LOW-NUREG/CR4256 V03: FIELD LyslMETER INVESTIGATIONS: LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR l
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER FISCAL YEAR 1995. Annual Report.
TEST RESULTS FOR FISCAL YEARS 1994 AND 1995.
NUREG/CR4256 V03: FIELD LYSIMETER INVESTIGATIONS. LOW-NUREG/CR4350 A TECHNOUE FOR HUMAN ERROR ANALYSIS LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM LYSIMETER (ATHEANA). Technical Basis And Methodo6ogy Descopert TEST RESULTS FOR FISCAL YEARS 1994 AND 1995 3
NUREG/CR4384 VO1: LITERATURE REVIEW OF ENVIRONMENTAL NUREG/CR 6332: MICROSTRUCTURAL CHARACTERIZATON OF SE.
QUALIFICATION OF SAFETY RELATED ELECTRIC CABLES Summary LECTED AEA/UCSB MODEL FECUMN ALLOYS.
Of Past Work.
NUREG/CR-64t3 ANALYSIS OF THE tRRADIATON DATA FOR A3020 NUREG/CR4384 V02: LITERATURE REVIEW OF ENVIRONMENTAL AND A5338 CORRELATION MONITOR MATERIALS OUALIFICATON OF SAFETY-RELATED ELECTRIC CABLES.Uterature NUREGICR4424. REPORT ON AGING OF NUCLEAR POWER PLANT Anaysis And Appendices.
REINFORCED CONCRETE STRUCTURES.
ij 31 4
i 32 Contractor index NUREG/CR4425: IMPACT OF STRUCTURAL AGING ON SElSMIC SOUTHWEST RESEARCH INSTITUTE RISK ASSESSMENT OF REINFORCED CONCRETE STRUCTURES IN NUREG/CR-6074 V02: SEALED SOURCE AND DEVICE DESIGN j
NUCLEAR POWER PLANTS.
SAFETY TESTING Technical Report On The Findings Of Task 4 inves-i 9*
PURDUE UNIV, WEST LAFAYETTE, IN NUREG/CR4309: SCIENTIFIC DESIGN OF PURDUE UNIVERSITY WASHINGTON, UNIV. OF, SEATTLE, W A MU T -DIMENSIONAL INTEGRAL TEST ASSEMBLY (PUMA) FOR GE NUREG/CR4470: FITNESS FOR DUTY IN THE NUCLEAR INDUSTRY:
UPDATE OF THE TECHNICAL ISSUES 1996 SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY SCIENCE APPLICATIONS, WESTINGHOUSE HANFORD CO.
NUREG/CR4350: A TECHNIQUE FOR HUMAN ERROR ANALYSIS NUREG/CR-5631 R02: CONTRIBUTION OF MATERNAL RADIONU.
(ATHEANA). Technical Bases And Methodology Descnption.
CLIDE BURDENS TO PRENATAL RADIATION DOSES.
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i 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 pim ej6s we l
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i 33 I
Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number end followed by the report number. If further information is needed, refer to the main citation by the NUREG number.
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C 35
NRC FORM 336 U.S. E) CLEAR REGULATORY COMMISIlON
- 1. REPORT NUMBER Supp.gned by NRC, Add Vol.,
(Arsi (2-80)
, Rev., and Addendum Num-NRCM 1102, 320s,3202 BIBUOGRAPHIC DATA SHEET b"
d ""Y 3 (So. instructions on sn. revn )
NUREG-0304 Vol. 21, No. 2
- z. T TLE AND SusTirtE
- 3. DATE REPORT PUBUSHED Regulatory and 'Ibchnical Reports (Abstract Index Journal)
MONTH YEAR Compilation for Second Quarter 1996 August 1996 April-June
- 4. RN OR GRAMT NUMBER
- 6. AUTHOR (S) 6, TYPE OF RhPORT Reference
- 7. PERIOD COVERED (inclusive Dates)
April-June 1996
- 8. PERFORMING ORGANIZATION - NAME AND ADDRESS (if NRC, prov6de Division, Offce or Region, U.S. Nuclear Regulatory Commission, and malling address; if contractor, provido name and maillng address.)
Division of Freedom of Information and Publications Services Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 9. SPONSORING ORGANIZATION - NAME AND ADDRESS (if NRC, type 'Same as above"; if contractor, provide NRC Divis6on, Offee or Regicn.
U.S. Nuclear Regulatory Commission, and malling address.)
Same as 8, above.
- 10. SUPPLEMENTARY NOTES M. A. Sheehan, Project Manager
- 11. ABSTRACT (200 words or less)
This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceed-ings of conferences and workshops, grants, and 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.
- 12. KEY WORDS/DESCRIPTORS (Ust words or phrases that will assist researchere in locat.%g the report.)
- 13. AVAILABILITY STATEMENT Unlimited
- 14. SECUR'TY CLASSIFICATION compilaten g7,,,,,,,,
abstract index Unclassified (Thi. asport)
Unclassified
- 16. NUMtsER OF PAGE8
- 18. PRsCE NRC FORM 336 (2-ets)
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