ML20115A862
| ML20115A862 | |
| Person / Time | |
|---|---|
| Issue date: | 06/30/1996 |
| From: | NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V21-N01, NUREG-304, NUREG-304-V21-N1, NUDOCS 9607090048 | |
| Download: ML20115A862 (43) | |
Text
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Vol. 21, No.1 Regulatory and Technical Reports (Abstract Index Journal)
Compilation for First Quarter 1996 i
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l AVAILABILITY NOTICE l
Availability of Reference Materials Cited in NRC Publications i
Most documents cited in NRC publications will be available from one of the following sources:
1.
The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2.
The Superintendent of Documents, U.S. Government Printing Office P. O. Box 37082, Washington, DC 20402-9328 3.
The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive.
Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and cc respondence: Commission papers; and applicant and licensee docu-ments and correspondence.
The following documents in the NUREG series are available f or 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 litereture 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-tien cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001.
Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library Two White Flint North.11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards institute,1430 Broadway. New York, NY 10018-3308.
NUREG-0304 Vol. 21, No.1 l
Regulatory and Technical Reports (Abstract Index Journal) l Compilation for First Quarter 1996 January - March Date Published: June 1996 Publications Branch Division of Freedom ofInformation and Publications Services Omce of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
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CONTENTS Preface.............................................
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Tab Main Citations and Abstracts.............
1 e Staff Reports Conference Proceedings e
e Contractor Reports Grant Reports e
Irdernational Agreement Reports e
l Secondary Report Number index........
2 Personal Author index..............
3
(
subject index........................
4 l
' NRC Originating Organization Index (Staff Reports)................
5 l
NRC Originating Organization Index (International Agreements)................
...... 6 NRC Contract Sponsor index (Contractor Reports) 7 Contractor Index.....................
8 International Organization index....................
9 Licensed Facility index.................
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PREFACE This comp!'ation misists 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 in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/lA-XXXX. These precede the following indexes:
Secondary Report Number index Personal Authorindex Subject irr$ex NRC Originating Organization index (Staff Reports)
NRC Originating Organization index (International Agreements)
NRC Contract Sponsor index (Contractor Reports)
Contractor index International Organization index Licensed Facility Index A detailed explanation of the entries precedes each index.
The bitliographic elements of the main citations are the following:
Staff Report NUREG-0808 MARK 11 CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA.
ANDERSON, C. J. Division of Safety Technology. August 1981. 90 pp. 8109140048. 09570:200.
Where the entries are (1) report number, (2) report title, (3) report euthor, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the microfiche address (for internal NRC use).
Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND REUABluTY ENGINEERING IN NUCLEAR REGULATION. JANERP, J.S. Argonne National Laboratory. May 1981.141 pp.
8105280299 ANL-81-3. 08632:070.
Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization, (9) the microfiche address (for NRC intamal use).
l V
Contractor Report NUREG/CR-1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REAC-TORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R. Sandia Laboratories.
May 1981.100 pp. 81070104',9. SAND 80-0929. 08912:242.
Where the entr.es are (1) repor; number, (2) report title, (3) report authors, (4) organizational unit of authors or publisher, (5) date report was pubilshed, (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/GR-0013: APPLICATIONS OF A NEW MAGNETIC MONITORING TECHNIQUE TO IN SITU EVALUA-TION OF FATIQUE DAMAGE IN FERROUS COMPONENTS. JILES, D.C.; BINER, S.B.; GOVINDARAJU, M.; et al. Iowa State Univ., Ames, IA. June 1994. 41 pp. 9407250286. 80328:195.
Where the entries are(1) report number, (2) report title (3) report authvrs, (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).
In'emational Agreement Report NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA.
NEUMANN, U. Kraftweek Union. August 1986. 223 pp. 8608270424. 37659:138.
Where the entries are(1) report number, (2) report title, (3) report author, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization (if given), and (9) the microfiche address (for NRC internal use).
The following abbreviations are used to identify the document status of a report:
ADD
- addendum APP
- appendix DRFT - draft ERR
- errata N - number R - revision S - supplement V - volume Availability of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Govemment Printing Office (GPO) or from the National Technical Information 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. Government Printing Office Post Office Box 37082 Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge card by calling the GPO on (202) 512-2249 or (202) 512-2171. Non-U.S. customers must make payment in advance either 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.
vi
I NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated report.
j Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type of identification replaces contractor-established codes such as ORNUNUREG/TM-XXX and TREE-NUREG-XXXX, as well as various other numbers that could not be correlated with NRC sponsorship or the work being reported.
In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference pro-ceedings NUREG/GR is used for NRC grant reports, and NUREG/lA is used for international agreement reports.
Allthese report codes are controlled and assigned by the staff of the Technical Publications Section of the NP.C Division of Freedom of Information and Publications Services.
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Main Citations and Abstracts l
The report listings in this compilation are arranged by report number, where NUREG-XXXX is en NRC staff-onginated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CR-XXXX is an NRC contractor-prepared report, and NUREG/lA-XXXX is an inter-national agreement report. The bibliographic information (see Preface for details) is followed l
by a brief abstract of this report.
l NUREG-0040 V19 N04: LICENSEE CONTRACTOR AND NUREG-0304 V20 N03: REGULATORY AND TECHNICAL RE-
)
j VENDOR INSPECTION STATUS REPORT. Quarterly PORTS (ABSTRACT INDEX JOURNAL). Compilation for Third Report, October-December 1995.(White Book)
- Offee of Nucle-Quarter 1995. July-September.
- Division of Freedom of informa-ar Reactor Regulation (Post 941001). February 1996. 73pp.
tion & Publications Services (Post 940714). January 1996.48pp.
9603190117. 87510:219.
9602220246. 87210:306.
This periodical covers the results of inspectons performed by This joumal includes all formal reports in the NUREG series the NRC's Special inspecbon Branch, Vendor inspecton Sec-prepared by the NRC staff and contractors; proceedings of con-l tion, that have been distributed to the inspected organizations ferences and workshops; as well as intemational agreement re-during the period from October through December 1995, ports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal suthor, NUREG-0090 V18 N02: REPORT TO CONGRESS ON ABNOR-subject, NRC organization for staff and intemational agree-i MAL OCCURc1ENCES. April-June 1995.
- Office for Analysis &
ments, contractor, intematonal organizabon, and licensed facili-Evaluation of Operatonal Data. Director. October 1995. 29pp.
ty.
9602120369. 87081:158.
Section 208 of the Energy Peorganizabon Act of 1974 identi-NUREG-0325 R19: U.S. NUCLEAR REGULATORY COMMISSION fies abnormal occurrence (AO) as an unscheduled incident or ORGANIZATION CHARTS AND FUNCTIONAL event that the Nuclear Regulatory Commission determines to be STATEMENTS. January 31, 1996.
- Ofc of Personnel (Post significant frorn the standpoint of public health or safety requires 870413). January 1996. 67pp. 9603190108. 87510:293.
a quarterty report of such occurrences to be made to Congress.
Functional statements and organization charts for the U.S.
This report provides a desenpton of those incidents and events Nuclear Regulatory Commission offices, divisions, and branches i
that have been determined to be AOs dunng the period of April are pented.
1 through June 30,1995. This report addr3sses five AOs at NUREG-0390 V10: TOPICAL REPORT REVIEW STATUS.(Blue NRC-licensed facilities. One involved a reactor coolant system Book)
- Office of Nuclear Reactor Regulation (Post 941001).
blowdown at a pressurized water reactor (PWR) nuclear power March 1996. 36pp. 9604150318. 87865:283.
plant, one involved a previously unidentified path for the poten-This report provides industry with procedures for submitting tial release of radioactivity at a PWR nuclear power plant, two topical reports, guidance on how the U.S. Nuclear Regulatory involved medical brachytherapy misadministratons, and one in.
Commission (NRC) processes and responds to topical report volved a medical therapeutic radiopharmaceutical misadminis-submittals, and an accounbng, with review schedules, of all topi-tration. Four AOs submitted by the Agreement States are in-cal reports currently accepted for review by the NRC. This cluded. One involved a medical teletherapy misadministraton, report is published annually, two involved medical brachytherapy misadministratons, and one involved the overexposure of personnel at a medical center.
NUREG-0540 V17 N11: TITLE LIST OF DOCUMENTS MADE The report also contains an update of one AO previously report.
PUBLICLY AVAILABLE. November 1-30, 1995.
- Division of ed by an NRC licensee and two AOs previously reported by the Freedom of Information & Publications Services (Post 940714).
Agreement States. No "Other Events of Interest" items are January 1996. 286pp. 9602220190. 87212:001.
being reported.
This document is a monthly publicabon containing desenp-tions of information received and generated by the U.S. Nuclear NUREG4090 V18 NO3: REPORT TO CONGRESS ON ABNOR.
Regulatory Commission (NRC). This information includes (1)
MAL OCCURRENCES. July-September 1995.
- Office for Anaty-doceseted material associated with civilian nuclear power plants i
sis & Evaluation of Operational Data, Director. February 1996.
and other uses of radioactive materials, and (2) nondocketed 23pp. 9602280295. 87272:268.
material received and generated by NRC pertinent to its role as Secten 208 of the Energy Reorganizaton Act of 1974 identi.
a regulatory agency. The following indexes are included: Per-fies an abnormal occurrence (AO) as an unscheduled incident sonal Author, Corporate Source, Report Number, and Cross or event that the Nuclear Regulatory Commission determines to Reference of Enclosures to Principal Documents.
be sigruficant from the standpoint of public health or safety and
.,lREG-0540 V17 N12: TITLE LIST CF DOCUMENTS MADE requires a quarterty report of such occurrences to be made to
- 98LICLY AVAILABLE. December 1-31, 1995.
- Division of Congress. This report provides a deacription of those incidents h sdom cf Information & Publications Services (Post 940714).
and events that have been determined to be AOs during the i Jary 1996. 298pp. 9603260311. 87641:001.
period of July 1 through September 30,1995. This report ad-See NUREG 0540,V17,N11 abstract.
l dresses three AOs at NRC-heensed facihties. Two involved l
medical brachytherapy misadministrations and one involved in-NUREG-0713 V16: OCCUPATIONAL RADIATION EXPOSURE AT l
gestion of radioactive material by research workers. One AO COM'AERICAL NUCLEAR POWER REACTORS AND OTHER subrrutted by the Agreement States is included. It involved im.
FACILITIES,1994. Twenty-Seventh Annual Report.
j portaten into the United States of a package having excessive THOMAS,M.L Division of Regulatory Applications (Post radiation. No updates of previously reported AOs are included in 941217). HAGEMEYER,0. Science Applicatons International i
this report. No "Other Events of interest" items are being re-Corp. (formerly Science Applications, Inc.). January 1996.
ported.
302pp. 9602220240. 87211:001.
1
2 Main Citations and Abstracts This report summarizes the occupational radiation exposure Supplement No. 20 to the Safety Evaluation Report for the information that has been reported to the NRC's Radiation Ex-application filed by the Tennessee Valley Authonty for license to posure information Reporting System (REIRS) by nuclear power operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos.
facilities and certain other categones of NRC licensees during 50-390 and 50-391, located in Rhea County, Tennessee, has the years 1989 through 1994. The bulk of the data presented in been prepared by the Office of Nuclear Reactor Regulation of the report was obtained from annual radiabon exposure reports the Nuclear Regulatory Commission. The purpose of this sup-submitted in Eu.m6nce with the requirements of 10 CFR piement is to update the Safety Evaluation with (1) additional in-20.220 and the technical specifications of nuclear power plants.
formation submitted by the applicant since Supplement No.19 The 1994 annual reports submitted by about 303 licensees indi-was issued, and (2) matters that the staff had under review cated that approximately 152,028 individuals were monitored, when Supplement No.19 was issued.
141,901 of whom were monitored by nuclear power facilities.
NUREG-0910 R02 S02: NRC COMPREHENSIVE RECORDS dis-They incurred an average individual dose of 0.1 rem (cSv) and an average measurable dose of about 0.31 rem (cSv). Analyses POSITION SCHEDULE.
- Information 8 Records Management of transient worker data indicate that 18,176 individuals corn.
Branch (Post 890827). Februa.) 1996. 200pp. 9605220230.
88332:076.
pleted work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year The approved records dispositioa schedules specify the ap-to account for the duplicate reporung of transient workers by propriate duration of retention and the final disposition for multiple hcensees. In 1994, the average measurable dose calcu.
records created or maintained by the NRC. NUREG 0910, Revi-j lated from reported dela was 0.28 cSv (rem). The corrected sion 2, Supplement 2 makes editorial and administrative dose distribution resulted in an average measurable dose of changes to the NrWonal Archives and Records Administration *s O.31 cSv (rem).
General Record Schedule (GRS) and forwards an entire updat-ed set of the General Records Schedule including GRS Subject NUREG-0750 V41: NUCLEAR REGULATORY COMMISSION and Forms indexes.
ISSUANCES. Opinions And Decisions Of The Nuclear Regula-NUREG-0936 V14 N02:
NRC REGULATORY tory Comm.A,a With Selected Orders. January-June 1995.
- Di_
vision of Freedom of information & Publications Services (Post AGENDA. Semiannual Report. July-December 1995.
- Division of 940714). February 1996. 547pp. 9604020257. 87709:001.
Freedom of Information & Publications Services (Post 940714).
Legal issuances of the Commission, the Atomic Safety and Li.
February 19%. 57pp. 9602280332. 67272:290.
censing Board Panel, the Administrative Law Judges, and NRC The NRC Regulatory A9enda is a compilation of all rules on Program Offices are presented.
which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking NUREG-0750 V42102: INDEXES TO NUCLEAR REGULATORY which have been received by the Commission and are pending COMMISSION ISSUANCES. July-December 1995.
- Division of disposition by the Commission. The Regulatory Agenda is up-Freedom of Information & Publications Services (Post 940714).
dated and issued semiannually.
March 1996. 40pp. 9604020329. 87710:255.
Digests and indexes for issuances of the Commission, the NUREG-0940 V14N344P1: ENFORCEMENT ACTIONS: SIGNIFI-Atomic Safety and Licensing Board Panel, the Administrative CANT ACTIONS RESOLVED INDIVIDUAL Law Judges, the Directors' Decisions, and the Decisions on Pe.
ACTIONS. Semiannual Progress Report. July-December 1995.
- titions for Rulemaking are presented.
Ofc of Enforcement (Post 870413). February 1996. 363pp.
9003050127, 87335:001.
NUREG 0750 V42 N05: NUCLEAR REGULATORY COMMISSION This compilation summanzes significant enforcement actions ISSUANCES FOR NOVEMBER 1995. Pages 181219.
- Division that have been resolved dunng the period (July - December of Freedom of information & Publications Services (Post 1995) and includes copies of Orders and Notices of Violation 940714). January 1996. 45pp. 9602090022. 87066:244.
sent by the Nuclear Regulatory Commission to individuals with See NUREG-0750,V41 abstract.
respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to NUREG 0750 V42 N06: NUCLEAR REGULATORY COMMISSION managers and employees engaged in activities licensed by the ISSUANCES FOR DECEMBER 194. %s 22 b258.
- Division NRC. he Commisse Wves Ws informabon may be useM of Freedom of Information & Publications SeMces (Post to licensees in making employment decisions.
940714). February 1996. 44pp. 9602280302. 87272:185.
See NUREG-0750,V41 abstract.
NUREG-0940 V14N344P2: ENFORCEMENT ACTIONS: SIGNIFl-CANT ACTIONS RESOLVED REACTOR NUREG 0750 V43 N01: NUCLEAR REGULATORY COMMISSION LICENSEES. Semiannual Progress Report. July-December 1995.
ISSUANCES FOR JANUARY 1996. Pages 111.
- Division of Ofc of Enforcement (Post 870413). February 1996. 241pp.
Freedom of information & Publications Services (Post 940714).
O 3 abstrak hi lat mmarizes significant enforcement actions that have been resolved during the period (July December NUREG-0837 V15 N04: NRC TLD DIRECT RADIATION MONI-1995) and includes copies of letters, Notices, and Orders sem TORING NETWORK. Progress Report. October December 1995.
by the Nuclear Regulatory Commission to reactor licensees with STRUCKMEYER,R. Region 1 (Post 820201). March 1996.
respect to these enforcement actions. It is anticipated that the 326pp. 9603260299. 87623:001.
information in this publication will be widely disseminated to This report provides the status and results of the NRC Ther-managers and employees engaged in activities hcensed by the moluminescent Dosimeter (TLD) Direct Radiation Monitonng NRC, so that actions can be taken to improve safety by avoid-Network. It presents the radiation levels measured in the vicinity ing future violations similar to those described in this publica-of NRC licensed facemes throughout the country for the fourth tion.
NUREG-0940 V14N344P3: ENFORCEMENT ACTIONS: SIGNIFI-NUREG-0847 S20: SAFETY EVALUATION REPORT RELATED CANT ACTIONS RFSOLVED MATERIAL TO THE OPERATION OF WATTS BAR NUCLEAR LICENSEES. Semiannual Progress Report July-December 1995.
PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50-391.(Ten-
- Ofc of Enforcement (Post 870413). February 1996. 250pp.
nessee Valley Authonty) TAM,P.S. Office of Nuclear Reactor 9603260287. 87620:001.
Regulation (Post 941001). February 1996. 36pp. 9602280321.
This compilation summarizes significant enforcement actions 87272:231, that have been resolved during the period (July - December
l Main Citations afid Abstracts 3
1995) and includes copies of letters, Notices, and Orders sent application for the independent storage of spent nuclear fuel by the Nuclear Regulatory Commission to material licensees and high level radioactivo waste. Regulatory Guide 3.61 " Stand-with respect to these enforcement actions. It is anticipated that ard Format and Content for a Topical Safety Analysis Report for the information in this pubication will be widely disseminated to a Spent Fuel Dry Storage Cask" contains an outline of the spe-managers and employees engaged in activities licensed by the cife information required by the staff. The SRP is divided into NRC, so that actions can be taken to improve safety by avoid-14 esetions which reflect the standard application format. Regu-ing future violatory, almilar to those described in this publica-latory requirements, staff position, industry codes and stand-tiorL ards, acceptance criteria, and other information are discussed.
NUREG-1100 V1' BUDGET ESTIMATES Fiscal Year 1997,
- Di-Comments on this draft, will be considered and incorporated vision of Budget & Analysis (Post 890205). March 1996.168pp.
into the SRP as appropriate. The SRP is scheduled for publica-9604020325. 87714:001.
tion as an NRC NUREG document late in 1996. Comments, This report contains the fiscal year budget justifica. ion to Con-errors or omissions, and suggestions for improvement should be gross. The budget provxles estimates for salaries and expenses sent to the Director, Spent Fuel Project Office, U.S. Nuclear and for the Office of the inspector General for fiscal year 1997.
Regulatory Commission, Washington, DC 20555-0001.
NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT NUREG-1537 PT01: GUIDELINES FOR PREPARING AND RE-RELATED TO RECLAMATION OF THE URANIUM MILL TAIL-VIEWING APPLICATIONS FOR THE LICENSING OF NON-INGS AT THE ATuS SITE,MOAB, UTAH. Source Material Li-POWER REACTORS Part 1: Format And Content.
- Office of conse No. SUA-917 Docket No. 40-3453. (Atlas Corporation)
Niclear Reactor Regulation (Post 941001). February 1996, i
BLASING,T.S.; EASTERLY,C.E. Oak Ridge National Laboratory.
523pp. 9604020335. 87711:001.
FLIEGEL,M.; et al. Division of Waste Management (NMSS NUREG-1537, Part 1 gives guidance to non-power reactor li-940403). January 1996. 300pp. 9602050062. 86981:001.
censees and applicants on the format and content of applica-This Draft Environmental impact Statement (DEIS) has been tions to the Nuclear Regulatory Commission for Icensing ac-prepared by the Nuclear Regulatory Commission (NRC), Office tions. These hcensing actions include construction permits and of Nuclear Material Safety and Safeguards, to address potential initial operating licenses, heense renewals, amendments, con-environmental impacts associated with a request by Atlas Cor-versions from highly enriched uranium to ler.-ennched uranium, poration to amend its existing NRC License No. SUA-917 to re-decommissioning, and licerse termination.
claim an existing uranium mill tailings pile near Moab, Utah. The proposed reclamation would allow Atlas to (1) reclaim the tail-NUREG-1537 PT02: GUIDELlNES FOR PREPARING AND RE.
ings pile for permanent disposal and long-term custodial care by VIEWING APPLICATIONS FOR THE LICENSING OF NON-a government agency in its current location on the Moab site, POWER REACTORS.Part 2: Standard Review Plan And Accept-(2) prepare the 162-ha (400 acre) Moab site for site closure, ance Criteria.
- Office of Nuclear Reactor Regulation (Post and (3) relinquish responsibility of the site after having its NRO 941001). February 1996. 300pp. 9604020339. 87713:001.
license terminated. The DEIS describes and evaluates (1) tne NUREG-1537, Part 2 gives guidarre on the conduct of hcens-purpose of and need for the proposed action, (2) alternatives ing action reviews to NRC staff who review non-power reactor considered, (3) potentially affected environmental resources, (4) heensing applications. These licensing actions include construc-environmental consequences of the proposed action, and (5) tion permits and initial operating heenses, Icense renewals, costs and benefits associated with reclamation alternatives.
amendments, conversions from highly enriched uranium to low-Pubhc and agency comments on this DEIS will be considered in enriched uranium, decommissioning, and hcense termination.
the Final Environmental Impact Statement.
NUREG-1544: STATUS REPORT: INTERGRANULAR STRESS NUREG-1C32: DRAFT TECHNICAL EVALUATION REPORT FOR CORROSION CRACK!NG OF BWR CORE SHROUDS AND THE PROPOSED REVISED RECLAMATION PLAN FOR THE OTHEH INTERNAL COMPONENTS.
- Office of Nuclear Reac-ATLAS CORPORATION MOAB MILLSource Material License tor Regulation (Post 941001). March 1996.115pp. 9604150308.
No.
SUA-917, Docket No.
40-3453.(Atlas Corporation) 87877:165.
BRUMMETT,E.; FLIEGEL,M.; IBRAHIM A.; et at Division of On July 25, 1994, the U.S. Nuclear Regulatory Commission Waste Management (NMSS 940403). January 1996. 128pp.
(NRC) issued Genenc Letter (GL) 04-03 to obtain information 9602070045. 87015:139.
needed to assess compliance with regulatey requirements re-This Draft Technical Evaluation Report (DTER) summanzes garding the structural integnty of core shrouds in domestic boil-the U.S. Nuclear Regulatory Commission staff's review of Atlas ing water reactors (BWRs). This report begins with a brief de-Corporation's proposed reclamation plan for its uranium mill tail-senption of the safety signifcance of intergranular stress corro-ings pile near Moab, Utah. The proposed reclamation would sion cracking (IGSCC) as it relates to the design and function of al'ow Atlas to (1) reclaim the tailings pile for permanent disposal BWR core shrouds and other internal components, it then pre-tryl lontterm custodial care by a government agency in its cur.
sents a brief history of shroud cracking events both in the U.S.
v.st beation on the Moab site, (2) prepare the site for closure, and abroad, followed by an indepth summary of the industry ac-and (3) rehnquish responsibility of the site after having its NRC tions to address the issue of IGSCC in BWR core shrouds and hcense terminated. The NRC staff review has identified open other interral components. This report summarizes the staff's issues in geology, seismology, geotechnical engineenng, ero-basis for iswing GL 94-03, as well as the staff's assessment of sion protection, water resources protection and radon attenu-plant-specific responses to GL 94-03. The staff is continually ation. The NRC will not approve the proposed reclamation plan evaluating the hcensee inspection programs and the results until Atlas adequately resolves these open issues.
from examinations of BWR core shrouds and other internal w np n
- s. Ms W b ptene of WMs b W NUREG-1536 DRFT FC: STANDARD REVIEW PLAN FOR DRY SPENT FUEL STORAGE SYSTEMS. Draft Report For Com-s at a i dt ment.
- Office of Nuclear Material Safety & Safeguards. Febru-ary 1996.172pp. 9603190122. 87516:147.
NUREG/CP-0149 VD1: PROCEEDINGS OF THE TWENTY THIRD The Standard Review Plan (SRP) for Dry Cask Storage Sys-WATER REACTOR SAFETY INFORMATION MEETING. Plenary tems provides guidance to the Nuclear Regulatory Commrssion Session, High Burnup Fuel Behavior, Thermal Hydraulic Re-staff in the Spent Fuel Project Office for performing safety re-search. MONTELEONE,S. Brookhaven National Laboratory.
views of dry cask storage systems. The SRP is intended to March 1996. 278pp. 9604150352. 87868:001.
ensure the quality and untformity of the staff reviews and This three-volurr.e report contains papers presented at the present a basis for the review scope and requirements. Part 72, Twenty Third Water Reactor Safety Information Meeting held at Supart B generalty spWies the information needed in a license the Bethesda Mamott Hotel, Bethesda, Maryland, October 23-l f
4 Main Citations and Abstracts 25,1995. The papers are pnnted in the order of their presenta-atc.d in boiling water reactors were determined in slow-strain-tion in each session and describe progress and results of pro-rate-tensile tests at 289 degrees C. Microchemical changes in grams in nuclear safety research conducted in this country and the specimens were studied by Auger electron spectroscopy abroad. Foreign participation in the meeting included papers and scanning electron microscopy to determine whether trace presented by researchers from France, Italy, Japan, Norway, impunty elements may contnbute to IASCC of these materials.
Russia Sweden, and Switzerland. The titles of the papers and the names of the authors have been updated and may differ NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORM-from those that appeared in the final program of the meeting.
ERS IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
ROBERTS E.W.; EDSON,J.L; UDY,A.C. Idaho National Engi-NURE3/CP-0149 V02: PROCEEDINGS OF THE TWENTY-THIRD neering Laboratory. February 1996. 64pp. 9603010296. INEL-WATER REACTOR SAFETY INFORMATION MEETING. Human 95/0573. 87307:067.
Factors Research, Advanced l&C Hardware & Software, Severe This report discusses aging effects on safety-related power Accident Research, Probabihstic Risk Assessment Topics, Indi-transformers in nuclear power plants. It also evaluates mainte-vidual Plant Examination. MONTELEONE,S. Brookhaven Nabon-nance, testing, and monitoring practices, with respect to their El Laboratory. March 1996. 542pp. 9604150357. 87866:001.
effectiveness in detecting and mitigating the effects of aging.
See NUREG/CP-0149,V01 abstract.
The study follows the U.S. Ncclear Regulatory Commission's NUREG/CP-0149 V03: PROCEEDINGS OF THE TWENTY TM.1D (NRC) Nuclear Plant-Aging Research appr%A it investigates WATER REACTOR SAFETY INFORMATION the materials used in transformer com%ction, identifies stres-MEETING. Structural & Seismic Engineenng, Primary Systems sors and aging mechanisms, presents operating and testing ex-Integnty, Equipment Operability And Aging, ECCS Strainer perience with aging effects, analyzes transformer failure events Blockage Research & Regulatory Issues. MONTELEONE,S.
reported in various databases, and evaluates maintenance prac-Brookhaven National Laboratory. March 1996. 246pp.
tices. Databases that were analyzed included the NRC's Licens-9604150363. 87865:037.
ee Event Report (LER) system and the Institute for Nuclear See NUREG/CP-0149,V01 abstract.
Power Operations' Nuclear Plant Rehability Data System DSb NUREG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIO-ACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES NUREG/CR-5985 Sot: REVIEW OF P-SCAN COMPUTER-BASED IN 1992. AABERG R.L; BAKER,0.A. Battelle Memorial institute, ULTRASONIC INSERVICE INSPECTION SYSTEM.
Pacific Northwest Laboratory. March 1996.196pp.9604170363.
HARRIS,R.V.; ANGEL,L.J. Battelle Memorial Institute, Pacific PNL-4221. 87903:120.
Northwest Laboratory. December 1995.129pp. 96M090369.
Population and individual radiation dose commitments have PNL-8919. 87807:001.
been estimated from reported radionuclide releases from com-This supplement reviews the P-scan system, a computer.
mercial power reactors operating during 1992. Fifty-year dose based ultrasonic system used for inservice inspection of piping commitments for a one-year exposure from both liquid and at-and other components in nuclear power plants. The supplement mosphenc releases were calculated for four population groups was prepared using the methodology described in detail in Ap-(infant, child, teenager, and adult) residing between 2 and 80 pendix A of NUREG/CR-5985, and is based on one month of km fom each of 72 reactor sites. This report tabulates the re-using the system in a laboratory. This supplement desenbes sults of these calculations, showing the dose commitments for and charactenzes: computer system, ultrasonic components, both water and airborne pathways for each age group and and mechanical components; scanning, detection, digitizing, im-organ. Also included for each of the sites is an estimate of indi-aging, data interpretation, operator interaction, data handling, vidual doses that are compared with 10 CFR Part 50, Appendix and record-keeping. It includes a general description, a review I design objectives. The total collective dose commitments checklist, and detailed resutts of all tests performed.
(from both liquid and airborne pathways) for each site ranged from a high af 3.7 person-rem to a low of 0.0015 person-rem for NUREG/CR-6096:
APACHE LEAP TUFF INTRAVAL the sites with plants in operation and producing power during EXPERIMENTS.Results And Lessons Leamed.
the year. The anthmetic mean was 0.66 person-rem. The total RASMUSSEN,T.C.
- Georgia, Univ.
of,
- Athens, GA.
population dose for all sites was estimated at 47 person-rem for RHODES.S.C.; GUZMAN,A.; et al. Arizona, Univ. of, Tucson, the 130 million people considered at risk. The individual dose AZ. March 1996.110pp. 9604020277. 87714:170.
commitments estimated for all sites were below the Appendix i Data from laboratory and field experiments in unsaturated design objectives.
fractured rock are summarized and interpreted fe' the purpose of evaluating conceptual and numerical models of fluid, heat NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACK-and solute transport. The experiments were conducted at four ING IN UGHT WATER REACTORS.
Semiannual scales, in small cores (2.5-cm long by 6-cm across), a large Report, October 1904 - March 1995.
CHUNG H.M.;
core (12-cm long by 10-cm across), a small block containing a CHOPRA,0.K.; GAVENDA.D.J.; et al. Argonne National Labora-single fracture (20 x 21 x 93 cm), and at field scales in bore-tory. January 1996. 72pp. 9602050045. ANL-95/41. 86980:234.
holes (30-m long by 10-cm across) at three tiJes (1/2.,1-and This report summarizes work performed by Argonne National 3-meters). The smellest scale in the laboratory provided isother.
Laboratory on fatigue and environmentally assisted cracking mal hydraulic and thermal properties of unfractured rock. Noni-(EAC) in light water reactors (LWRs) from October 1994 to sothermal heat, fluid and solute transport expeiiments were March 1995. Topics that have been investigated include (a) fa' conducted using the large core. Isothermal gas and liquid flow tigue of carbon and low alloy steel used in reactor piping and experiments were conducted in the fractured block. Field-scale pressure vessels, (b) EAC of Alloy 600 and 690, and (c) irradia^
experiments using air were used to obtain in situ permeaoility tion-assisted stress corrosion cracking (IASCC) of Type 304 SS.
estimates as a function of the measurement scale. Interpreta-Fatigue tests were conducted on ferritic steels in water with tion of experimental results provides guidance for resolving un-several dissolved-oxygen (DO) concentrations to determine certainties related to radionuclide migration from high level whether a slow strain rate applied during different portions of a waste repositories in unsaturated fractured rock.
tensile-loading cycle are equally effective in decreasing fatigue life. Tensile properties and microstructures of several heats of NUREG/CR-6124: CHARACTERIZATION OF RADIONUCLIDE.
Alloy 600 and 690 were characterized for correlation with EAC CHELATING AGENT COMPLEXES FOUND IN LOW-LEVEL l
of the alloys h simulated LWR environments. Effects of DO and RADIOACTIVE DECONTAMINATION WASTE. Literature j
electrochemical potential on busceptibility to intergranular crack.
Review. SERNE,R.J.; FELMY,A.R.; CANTRELL,K.J.; et al. Bat-ing of high-and commercial-purity Type 304 SS specimens from telle Memonal Institute, Pacific Northwest Laboratory. March control-blade absorber tubes and a control-blade sheath irradi-1990.168pp. 9604160360. PNL-8856. 87884:011.
l
l Main Citations and Abstracts 5
The U.S. Nuclear Regulatory Commission is responsible for region. Cleavage fracture toughness scaling models were uti-regulating the safe land diopcaal of low-level radioactive wastes lized to correct the data for the loss of constraint in short crack that may contain organic chelating agents. Such agents include specimens and tension geometries. The toughness scaling EDTA, DTPA, picolinic acid, and citnc acid, which can form radi-models were effective in reducing the scatter in the data, but onuclide-chelate complexes that my enhance the migration of tended to over correct the results for the short crack bend radionuclides from disposal sites. Data from the available litera-specimens. A proposed ASTM Test Practice for Fracture ture indicate that chelates, can feath from solidified decontami-Toughness in the Transition Range, which employs a master nation wastes in moderate concentration and can potentially complex certain radionuclides in the leachates. The effects of curve concept, was applied to the results. The proposed master the formation of such radionuclide-chelate complexes on the mi-curve over predicted the fracture toughness in the mid-transition gration of radionuclides in groundwater systems is still difficult and a modified master curve was developed that more accu-to quantitatively predict. However, in general it appears that ratery modeled the transition behavior of the material. Finally, both EDTA and DTPA have the potential to mobilize radionu-the modified master curve and the fracture toughness scaling s
M M At the mM We clides,from waste disposal sites because such chelates can leach in moderate concentration, form strong radionuclide-che-g pec m.
i l
late complexos, and can be recalcitrant to biodegradation. It it was shown that wher the scaling models over correct the I
also appears that oxalic acid and citric acid will not greatly en-data for loss of constraint, they can also lead to non-conserva-l hance the mobility of radionuclides from waste disposal sites tive estimates of the increase in toughness for low constraint i
because these chelates do not appear to teach in high concen.
geometries.
tration tend to form relatively weak radionuclide<helate com-l plexes, and can be readily biodegraded. In the case of picolinic NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DE-l acid, insufficient data are available to make definitive predic.
COMMISSIONING A REFERENCE LARGE IRRADIATOR AND tions.
REFERENCE SEALED SOURCES.
HAFFNER D.R.;
I VILLEGAS,A.J. Battelle Memorial Institute, Pacific Northwest l
NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 Laboratory. January 1996.109pp. 9602290251. 87295:001.
(
CFR PART 61 AND OTHER SELECTED I
RADIONUCLIDES. Literature Review.
THOMAS,C.W.;
This report contains the results of a study sponsored by the THOMAS,V.W.; ROBERTSON.D.E. Battelle Memorial Institute, U.S. Nuclear Regulatory Comrnission (NRC) to examine the de-l Pactfic Northwest Laboratory. March 1996. 42pp. 9604150341.
commissioning of large radioactive irradiators and their respec-PNL-9444. 87865:319.
tive facilities, and a broad spectrum of sealed radioactive A comprehensive literature review and assessment was con-sources and their respective devices. Conceptual decommis-ducted to identify and evaluate radioanalytical technology and sioning activities are identified, and the technology, safety, and procedures used for measuring 10CFR61 radionuclides and costs (in early 1993 dollars) associated with decommissioning j
other long-lived isotopes. This review evaluated radiochemical the reference large irradiator and sealed source facilities are j
precedures currently in use at a number of laboratories in the evaluated. The study provides bases and background data for j
US, as well as identifying new advanced methods and tech.
possible future NRC rulemaking regarding decommissioning, for niques which could be adapted for routine radiochemical analy-evaluation of the reasonableness of planned decommissioning ses of low-level radioactive waste. The 10CFR61 radionuclides actions, and for determining if adequate funds are reserved by I
include (14)C, (60)Co, (59,63) Ni, (90)Sr, (94)Nb, (99)Tc, (129)l, the licensees for decommissioning of their large irradiator or l
(137)Cs and TRU lsotopes with half-lives greater than five sealed source facilities. Another purpose of this study is to pro-l years. The other low-level radionuchdes of interest include vide background and information to assist licensees in planning (7,10)Be, (26)Al, (36)Cl, (93)Mo, (109,113m)Cd, and and carrying out the decommissioning of their sealed radioac-(121m.126)Sn, which may be present in various types of waste tive sources and respective facilities.
streams from nuclear power stations.
l NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC ON MAIN STEAM ISOLATION VALVES AND VALVE OPERA-MOTORS IN NUCLEAR POWER PLANTS. VILLARAN M.;
TORS. CLARK,R.L Oak Ridge National Laboratory. March SUBUDHI,M. Brookhaven National Laboratory. March 1996.
1996.108pp. 9603260298. ORNL-6814. 87640:001.
136pp.9603260290. BNL-NUREG-52460. 87640:106.
In recent years main steam isolation valve (MSIV) operating Large electric motors serve as the prime movers to drive high problems have resulted in significant operational transients capacity pumps, fans, compressors, and generators in a variety (e.g., spurious reactor trips, steam generator dry out, excessive of nuclear plant systems. This study examined the stressors vane seat leakage), increased cost, and decreased plant avail-that cause degradation and aging in large electric motors oper-ability A key ingredient to an engineenng-onented reliability im-ating in various plant locations and environments. The operating provement effort is a thorough understanding of relevant histori-history of these machines in nuclear plant service was studied cal exponence. A detailed review of historical failure data avail-by review and analysis of failure reports in the NPRDS and LER able through the instrtute of Nuclear Power Operation's Nuc!aar databases. This was supplemented by a review of motor de-Plant Rehabiltty Data System has been conducted for several signs, and their nuclear and balance of plant applications, in types of MSIVs and valve operctors for both boiling-water reac-order to characterize the failure mechanisms that cause degra-tors and pressurtzed-water reactors. The focus of this review is dation, aging, and failure in large electric motors. A generic fail-on MSIV Failures modes, actuator failure modes, consequences of failure on plant operations method of failure detection, and ure modes and effects analysis for large squirrel cage induction motors was performed to identify the degradation and aging major streceors affecting both valves and valve operators.
mechanisms affecting various ;omponents of these large NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS motors, the failure modes that result, and their effects upon the SCALING MODELS TO THE DUCTILE-TO-BRITTLE TRANSI-function of the motor. The effects of large motor failures upon TION. LINK,R.E. Navy, Dept. of. JOYCE J.A. U.S. Naval Acade-the systems in which they are operating, and on the plant as a my, Annapohs, MD. Jcnuary 1996. 42pp. 9602220350.
whole, were aralyzed from failure reports in the databases. The 87234:102.
effectiveness of the industry's large motor maintenance pro-l An experimental investigatirn of fracture toughnoss in the grams was assessed based upon the failure reports in the data-ductile-bnttle transition range was conducted. A large number of bases and reviews of plant maintenance procedures and pro-ASTM A533, Grade B steel, bend and tension specimens with grams.
varying crack longths were tested throughout the transition
6 Main Citations and Abstracts HUREG/CR4337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 censee Event Reports (LERs), as well as plant specific data ROUND-ROBIN ANALYSES.
RAHMAN,S.;
OLSON,R.;
were reviewed and analyzed to understand the effects of aging ROSENFIELD,A.; et al. Battelle Memorial Institute, Columbus on the Cl functions. This study provided information on the ef.
Laboratories. February 1996.182pp. 9602290264. BMI-2186.
fects of aging on component failure frequency, failure modes, 87295:113.
and failure causes. Current inspection, survellance, and moni-This report presents a summary of the results from three one-toring practices were also reviewed.
day international round-robin workshops which were organized by Battelle in conjunction with the Second Intemational Piping NUREG/CR-6340: AGING ASSESSMENT OF SURGE PROTEC-Integrity Research Group (IPIRG-2) Program. The objective of TlVE DEVICES IN NUCLEAR POWER PLANTS. DAVIS,J.F.;
these workshops was to develop a consensus in handling diffi-SUBUDHI,M. Brookhaven National Laboratory. CARROLL,0.P.
cutt analytical problems in leak-before-break and pipe flaw eval.
Florida, Univ. of, Gainesville, FL January 1996. 179pp.
uabons. The workshops, which were held August 5,1993, 9603040082. BNL-NUREG-52a63. 87317:001.
March 4,1994, and October 21, 1994 at Columbus, Ohio, in.
A study has been performed that assesses the effects of volved various technical presentations on the related research aging on the periormance and availability of surge protective efforts by the IPIRG-2 member organizations and solutions to devices (SPDs), commonly called surge arresters and surge several round. robin problems. Following review by the IPIRG-2 suppressors, used in electrical power and control systems in members, four sets of round-robin problems were developed.
U.S. commercial nuclear power plants. This study is one of a They involved: (1) evaluations of fracture properties and pipe number of studies performed under the Nuclear Plant Aging Re-loads, (2) crack-opening and leak-rate evaluations, (3) dynamic search (NPAR) program. One of the many purposes of that pro-analysis of cracked pipes, and (4) fracture evaluations of gram is to provide a technical basis for the identification and elbows. A total of 18 organizations from the United States, evaluation of degradation caused by age. Although surge pro.
Japan, Korea, and Europe solved these round-robin problems.
tective devices have not been classified as safety-related, they The analysis techniques employed by the participants included are risk important because they can minimize the initiating event both firute element and engineering methods. Based on the re-frequencies associated with loss of offsite power (LOOP) and sults from these analyses, several important observations were reactor tnp. Conversely, their failure due to age, or other made conceming the predictive capability of the current frac-causes, might increase the initiating event frequencies. Because ture-mechanics and thermal-hydraulics models for their applica-of their importance, especially those in (lightning) high flash teons in nuclear piping and piping welds.
density regions to the U.S., the proper application and coordina-NUREG/CR-6338: RESOLUTION OF THE DIRECT CONTAIN.
tion of high voltage and low voltage SPDs are important in erk MENT HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS sunng that overvoltage transients will not increase plant risk.
WITH LARGE DRY CONTAINMENTS OR SU8 ATMOSPHERIC NUREG/CR-6346: HYDROLOGIC EVALUATION METHODOLO-CONTAINMENTS. PILCH,M.M.; ALLEN,M.D.; KLAMERUS,E.W.
GY FOR ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED ZONE AT COMMERCIAL LOW-LEVEL RADIO-603 7.
D9 23 624:
ACTIVE WASTE DISPOSAL SITES.
MEYER,P.D.;
This report uses the scenarios desenbed in NUREG/CR-6075 ROCKHOLD,M.L; NICHOLS,W.E.; et al. Battelle Memorial Insti-and NUREG/CR-6075, Supplement 1, to address the direct tute, Pacific Northwest Laboratory. January 1996. 134pp.
containment heating (DCH) issue for all Westinghouse plants 9603010318. PNL-10843. 87311:068.
with large dry or subatmospheric containments. DCH is consid-This report identifies key technical issues related to hydrolog-ered resolved if the conditional containment failure probability
.c assessment of water flow in the unsaturatec zone at low-level o
(CCFP) is less than 0.1. Loads versus strength evaluations of radioactive waste (LLW) disposal facilities. In addition, a meth-the CCFP were performed for each plant using plant-specific in-formation. The DCH issue is considered resolved for a plant if a odology fw inewpwabng these issues m the pafumance as-sessment of proposed LLW disposal facilities is idenbfied and screening phase results in a CCFP less than 0.01, which is evaluated. The issues discussed fall into four areas: estimating more stnngent than the overall success cnterion. If the screen-the water balance at a site (i.e., infiltration, runoff, water stor-ing phase CCFP for a plant is greater than 0.01, then refined age, evapotranspiration, and recharge); analyzing the hydrologic containment loads evaluations must be performed and/or the performance of engineered 0.nnpi,ents of a faciltty; evaluating probability of high pressure at vessel breach must be analyzed.
the application of models to the prediction of facility perform-These analyses could be used separately or could be integrated ance; and estimating the uncertainty n predicted facility per-together to re-calculate the CCFP for an individual plant to fumance. To illustrate the application of the methodology, two reduce the CCFP to meet the overall success criterion of less examples are presented. The first example es of a below ground j
than 0.1. The CCFPs for all of the Westinghouse plants with dry vault locat0J in a humid environment. The second example containments were less than 0.01 at the screening phase, and looks at a shallow land burial facility located in an arid environ-thus, the DCH issue is resolved for these plants based on con-ment. The examples ubHze actual sne-specific data and reansbc j
tainment loads alone. No additional analyses are required.
facility designs. The two examples illustrate the issues unique to NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE humid and arid sites as well as the issues comrnon to all LLW PWR AND GENERAL ELECTRIC BWR CONTAINMENT ISOLA-sites. Strategies for addressing the analybcal difficutbes arising TION FUNCTIONS. LEE,B.S.; TRAVIS,R.; GROVE.E.; et al-in any complex hydrologic evaluaton of the unsaturated zone Brookhaven Nabonal Laboratory. March 1996. 154pp.
are demonstrated.
9604020321. BNL-NUREG.52462. 87715:001.
A study was performed to assess the effects of aging on the NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED Containment isolation (Cl) funcbons of Westinghouse Pressur-RULE ON RADIOLOGICAL CRITERIA FOR DECOMMISSION.
tzed Water Reactors and General Electric Boiling Water Reac-ING AND RELATED DOCUMENTS. PAGE,G.; CAPLIN J.;
tors. This stady is part of the Nuclear Plant Aging Research SMITH,D.; et al. Advanced Systems Technology, Inc. March (NPAR) program, sponsored by the U.S. Nuclear Regulatory 1996.166pp. 9604020352. 87712:100.
CvwwassOn. The obtecbves of this program are to provide an The Nuclear Regulatory Co.
.a. Mon (NRC) is conducbng an understardng of the aging progress and how it affects plant enhanced parbcipatory rulemaking to establish radiological crtte-safety so that it can be property managed. This is one of a na for the (,ses.Ja.eavang of NRC licensed facikbes. As a part number of studies performed under the NPAR program which of this action, the CO,wia.Gon publL+ed in the Federal Register provide a technical basis for the idenbfication and evaluation of (59 FR 43200), on August 22,1994, a preposed rule on radio-degradabon caused by age. The failure data from national data-logical criteria for decommissioning, solidting comments both bases, Nuclear Plant Reliabihty Data System (NPRDS) and U-on the rule as proposed and on certain specific itens as identL
Main Citations and Abstracts 7
fied in its supplementary statement of considerations. A draft NUREG/CR 6396: EXAMPLES. CLARIFICATIONS, AND GUID-Generic Environmental Impact Statement (GEIS) in support of ANCE ON PREPARING REQUESTS FOR RELIEF FROM the rule, also published in August 1994 as NUREG 1496, along PUMP AND VALVE INSERVICE TESTING REQUIREMENTS.
with its Appendix A (NUREG-1501), were also made available RANSOM.C.B.; HARTLEY,R.S. Idaho National Engineering Lab-for comment. A staff working draft on regulatory guidance oratory. February 1996 186pp. 9603010300. INEL-95/0512.
(NUREG-1500) was also made available. This report summa-87307:131.
nzed the 1,309 comments on the proposed rule and supple-in this report, the Idaho National Engineering Laboratory re-mentary items and the 311 comments on the GEIS as excerpt-viewers discuss issues related to requests for relief from the ed from 101 docketed letters received as solicited in the Feder-American Society of Mechanical Engineers code requirements al Register notice. Comments from two NRC/ Agreement. States for inservice testing (IST) of safety-related pumps and valves at meetings are also summanzed, commercial nuclear power plants. This report compiles informa-NUREG/CR4366: POLYRES: A POLYGON-BASED R! CHARDS tion and examples that may be useful to licensees in developing EQUATION SOLVER. HILLS R.G. New Mexico State Univ., Las relief requests submitted to U.S. Nuclear Regulatory Commis-Cruces, NM. MEYER.P.D.; ROCKHOLD.M.L Battelle Memorial sion (NRC) for their consideration and provides insights and rec-Institute, Pacific Northwest Laboratory. December 1995. 68pp.
ommendations on related IST issues. The report also gives spe-9605220418. PNL-10709. 88314:235.
Ctfic guidance on relief requests acceptable and not acceptable This document desenbes the theory, implementation, and use to the NRC and advises licensees in the use of this information of a software package designed to solve the transient, two-di-for application at their facilities, mensional Richards equation for water flow in unsaturated-saturated soils. This package was specifically designed to NUREG/CR-6407: CLASSIFICATION OF TRANSPORTATION model complex geometnes with minimal input from the user.
PACKAGING AND DRY SPENT FUEL STORAGE SYSTEM The spatial variation of the hydraulic properties can be defined COMPONENTS ACCORDING TO IMPORTANCE TO SAFETY.
across individual polygon-shaped subdomains, called objects.
MCCONNELL,J.W.; AYERS,A.L; TYACKE M.J. Idaho National These objects combine to form a polygon-shaped model Engineering Laboratory. February 1996. 59pp. 9603190098.
domain. Each object can have its own distnbution of hydraulic INEL-95/0551. 87522:099.
parameters. The resulting model domain and polygon-shaped This report provides a graded approach for classification of internal objects are mapped onto a rectangular, finste-volume, components used in transportation packaging and dry spent fuel computational gnd by a preprocessor. This allows the user to storage systems. This approach provides a method for identify.
specify model geometry independently of the underlying grid ing the classification of components according to importance to and greatty simplifies user input for complex geometries. In ad-safety within transportation packagings and dry spent fuel stor-dition, this approach signrficantly reduces the computational re-age systems. Record retenton requirements are discussed to quirements since complex geometries are actually modeled on identify the documentaten necessary to validate that the indi-a rectangular grid. This results in well-structured, finite differ-vidual components were fabricated in accordance witt.. heir as-ence-like systems of equations that require minimal storage and signed classification. A review of the existing regulations per-are very efficient to solve. The documentation for this software taining to transportation packagings and dry storage systems package includes a user's manual, a detailed desenption of the was performed to identify current requirements. The general undertying theory, and a detailed discussion of prcgram flow, types of transportation packagings and dry storage systems Several example problems are presented that show the use and were identifled. Discussions were held with suppliers and fabri-features of the software package. The water flow predictions for cators of packagings and storage systems to determine current several of these example problems are compared to those of practicas. The methodology used in this report is based on Reg-i another algonthm (Kirkland et al.,1992) to test for prediction ulatory Guide 7.10. Establishing Quality Assurance Programs for l
equivalency. The computer code described in this document is Packaging Used in the Transport of Radioactive Material. This available from the Energy Science and Technology Software report also includes a list of generic components for each of the Center, P.O. Box 1020. Oak Ridge, TN 37831 1020.
general types of transportation packagings and spent fuel stor.
NUREG/CR-6367: EXPERIMENTAL STUDY OF HEAD LOSS age systems. The safety irnportance of each component is dis-AND FILTRATION FOR LOCA DEBRIS. RAO,D.V.; SOUTO,F.J.
cussed, and a classification category is assigned.
Science & Engineering Associates, Inc. February 1996.153pp.
9603190128. SEA 95-554-06A:8. 87520:130.
NUREG/CR 6415: APPLICATIONS OF RELIABluTY DEGRADA.
A series of controlled experiments were conducted to obtain TlON ANALYSIS. VESELY,W.E. Science Applications interna-head loss and filtration characteristics of debris beds formed of tional Corp.
(formerty Science Applicatons, Inc.).
NUKON(TM) fibrous fragments, and obtain data to validate the SAMANTA,P.K. Brookhaven National Laboratory. February semi-theoretical head loss model developed in NUREG/CR.
1996.47pp.9603260303. BNL-NUREG 52488. 87624:242.
6224. A thermally insulated closed-loop test set-up was used to Reliability degradaten analysis is the analysis of the occur-conduct experiments using beds formed of fibers only and fibers rences of degradations and the times of maintenance to deter-intermixed with particulate debris. A total of three particulate mine their reliability and risk implicatons. A program is present-mixes were used to simulate the partsculate debns. The head ed for applying reliability degradation analyses to maintenance loss data were obtained for theoretcal fiber bed thicknesses of data collected at nuclear power plants. As a specific part of the 0.125 inch to 4.0 inches; approach velocities of 0.15 to 1.5 ft/s; program, time trending of maintenance data is illustrated. Main-temperatures of 75 degrees F and 125 degrees F: and sludge-tenance data on residual heat removal (RHR) pumps and serv-to-fiber nominal concentration ratos of C to 60. Concentraton ice water (SW) pumps at selected boiling water reactor (BWR) measurements obtained during the first flushing cycle were plants are evaluated to show how trends in maintenance data, used to estimate the filtration efficiencies of the debris beds.
which generally do not involve failures, can be used to under.
For test condrtions where the beds are fairly uniform, the head stand effectiveness of maintenance. These trends also are loss data were predictable within an acceptable accuracy range translated to specific impacts on pump unavailability and on by the semi-theorstacal model. The model was equally applica-core-damage frequency (assuming that the trends in failure rate ble for both pure fiber beds and the mixed beds. Typcally the are the same as those observed for degradation rate). The model over-predcted the head losses for very than beds and for second appication shows the use of reliabildy degradation anal-thin beds at high sludge-to-fiber mass ratios. This is attnbutable ysis to quantitatively evaluate the effect of maintenance, i.e., the to thew norbuniformity of such debns beds. In this range the cor-quantitative change in component unavailability when no main-relaton can be interpreted to provide upper bound estimates of tenance is performed. Assessment of these impacts are impor-head loss.
tant since they measure the reliability and risk impacts of main-J
8 Main Citations and Abstracts 1
tenance and can be ted back to the maintenance program to ards in process control systems have been developed over I
improve its effectiveness.
many years, and are reasonably well understood. An example is NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON the protecton system in a melear power plant. The extension BREATHING-ZONE AND AREA AIR SAMPLES.
of these techniques to systems which include digital computers METZGER,R.L; JESSOP,0.H.; MCDOWELL B.L.
Radiation is not well developed, and there is httle consensus among soft-Safety Engineenng, Inc. February 1996. 55pp. 9603180378.
ware engineenng experts and safety experts on how to analyze 87509:248.
such systems. One possible technique is to extend hazard anal-A solubility testing method for several common actinides has ysis to include digital computer. based systems. Software is fre-been developed with sufficient sensttivity to allow profiles to be quently overlooked during system hazard analyses, but this is determined from routine breathing zone and area air samples in unacceptable when the software is in control of a potentially the workplace. Air samples are covered with a clean filter to hazardous operation. In such cases, hazard analysis should be form a filter-sample-filter sandwich which is immersed in an ex-extended to fully cover the software. A rnethod for performing tracellular lung serum simulant solution. The sample is moved to software hazard analysis is proposed in this paper.
a fresh beaker of the lung fluid simulant each day for one week' NUREG/CR-6432: ESTIMATED NET VALUE AND UNCERTAIN-and then weekly until the end of the 28-day test period. The TY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.
soak solutions are wet ashed with nitric acid and hydrogen per.
oxide to destroy the organic components of the lung simulant WALSH,B.; BRIDEAU,J.; COMES L; ot al. Science & Engineer-pnor to the extraction of the nuclides of interest directly into an ng Associates, Inc. February 1996. 125pp. 9605130079.
SEASF-DR-94-001 88220:001 ext / active scintillator for subsequent counting on a photon-elec-A central question for resolutson of GSI-24 is whether or not Solvent xtrac t s i ng t extr nti t PWRs that currently rely on a manual system for ECCS switch.
have been developed for the isotopes of uranium, plutonium, over to recirculation should be required to install an automatic and curium. The procedures normally produce an isotopic re-system. Risk estimates are obtained by reevaluating the contn-covery greater than 95% and have been used to develop solu-butions to core damage frequencies (CDFs) associated with fail-bility profiles for air samples with 40 pCi or less of U308. Pro-ures of manual and semiautomatic switchover at a representa-files developed for U308 samples show good agreement with in tive PWR. This study consider = each separate instruction of the vitro and in vivo tests performed by other investigators on sam _
corresponding emergency operating procedures (EOPs), the pies from the same uranium mills.
mechanism for each control, and the relationship of each con-trol to its neighbors. Important contnbutions to CDF include NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR human errors that result in completely coupled failure of both COMMERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN RE-trains and failure to enter the required EOP. This detailed study ACTOR APPLICATIONS. PRECKSHOT G.G.; SCOTT,J.A. Law-finds that changeover to a semiautoma'ic system is not justified rence Livermore National Laboratory. March 1996. 107pp.
on the basis of cost-benefit analysis: going from a manual to a 9604150345. UCRL-ID-122526. 87867:179.
semiautomate system reduces the CDF by 1.7x10-5 per reac-This paper proposes a process for acceptance of commercial tor year, but the probability that the net cost associated with the off-the-shelf- (COTS) software products for use in reactor sys-modifcation being less than $1,000 per person-rem is about tems important to safety. An irwtial set of four enteria estab-20% without license renewal. Scoping analyses, using optimistic lishes COTS software product identification and its safety cate-assumptions, were performed for a changeover to a semiauto-gory. Based on safety category, three sets of additional entena, matic system with automatic actuation and to a fully automatic graded in ngor, are applied to approve (or disapprove) the prod-system; in these cases the probability of having a net cost uct. These enteria fall roughly into three areas: product assur-being less than $1,000/ person-rem is about 50% without li-ance, venfication of safety function and safety impact, and ex*
conse renewal and over 95% with license renewal.
amination of usage expenence of the COTS product in circum-stances similar to the proposed applicaton. A report addressing NUREG/CR-6435: AN ANALYSIS OF THE IMPACTS OF ECO-the testing of existing software is included as an appendix.
NOMIC INCENTIVE PROGRAMS ON COMMERCIAL NUCLEAR NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH POWER PLANT OPERATIONS AND MAINTENANCE COSTS.
BURNUP CORES. DIAMOND,0.J.; NEYMOTIN,L.; KOHUT,P.
KAVANAUGH,D.C.; MONROE,W.K. Battelle Memoria' institute, Brookhaven National Laboratory. February 1996. 78pp.
Pacific Northwest Laboratory. WOOD,R.S. Office of Nuclear Re-9603260310. BNL-NUREG-52491. 87640:242.
actor Regulation (Post 941001). February 1996. 47pp.
A study has been undertaken to determine the fuel enthalpy 9603190137. PNL-10934. 87510:172.
during a rod drop accident (RDA) and dunng two thermal-hy-This study presents an analysis of the determinants of non-draulc transients in a boiling water reactor (BWR). The objec-fuel Operations and Maintenance expenses (O&M) for the tive was to understand the consequences to high burnup fuel period 1986 to 1990. Since the determinants of O&M outlays and the sources of urcertainty in the RDA calculations. The are likely to be many and varied, the potential linkages, both analysis was done with RAMONA-48, a computer code that direct and indirect, to plant safety can be substantial. This study models the neutron kinetes throughout the core along with the develops a framework to analyze the elements that affect these thermal-hydraulics in the core, vessel, and steamline. The re-expenditures to provide a basis for understanding these link-suits showed that the calculated maximum fuel enthalpy in high ages.
burnup fuel will be affected by core design, initial conditsons, NUREG/CR-6438: THE EFFECT OF CYCLIC AND DYNAMIC and modeling assumptons. The important parameters in each LOADS ON CARBON STEEL PIPE. RUDLAND D.L.;
of these categories are discussed in the report. An additional SCOTT P.M.; WiLKOWSKI,G.M. Batteile Memonal institute, Co-objective of this study was te identify BWR and pressunzed lumbus Laboratories. February 1996.102pp. 9603190145. BMI-water reactor (PWR) transients in which there is signifcant 2188 87511:187 f
energy deposition. This determined which BWR transients were This report presents the results of four 152-mm (6-inch) diam-to be calculated as part of this study and which might be calcu-ed W @ were to be done for PWRs.
eter, unpressurized, circumferential through-wall-cracked, dy-namic pipe expenments fabricated from STS410 carbon steel NUREG/CR4430- ~ "TWARE SAFETY HAZARD ANALYSIS.
pipe manufactured in Japan. For three of these experiments, LAWRENCE J.D. t = rence Livermore National Laboratory. Feb-the through-wall crack was in the base metal. The displacement ruary 1996. 91pp. 9602290270. UCRL-ID-122514. 87296:001.
histones applied to these experiments were a quasi-static mon-Techniques for analyzing the safety and reliability of analog-otonic, dynamic monotone, and dynamic, cyche (R = -1) histo-f based electronc protection systems that serve to mitigate haz-ry. The through-wall crack for the third expenment was in a
Main Citations and Abstracts 9
tungsten-inert-gas weld, fabricated in Japan, joining two lengths summaries of those reports, along with a companson of the var-of STS410 pipe. The desplacement history for this experiment ious statistical analysis methods used in the studies. The stud-was the same history applied to the dynamic, cyclic base metal ies indicate that with some exceptions, active components gen-experiment. The test temperature for each expenment was 300 erally do not present a significant aging problem in nuclear C (572 F). The objective of these expenments was to compare power plants. Design entena and effective preventative mainte-a Japanese carbon steel pipe material with United States pipe nance programs, including timely replacement of components, material, to ascertain whether this Japanese steel was as sensi-are effective in mitigating potential aging problems. However, tive to dynamic and cyclic effects as United States carbon steel aging studies (such as qualitative and statistical analyses of fail-pipe. In support of these pipe expenments, quasi-static and dy-ure modes and maintenance data) are an important part of ef-namic, tensile and fracture toughness tests were conducted. An forts to ident;fy and solve potential aging problems. Solving analysis effort was performed that involved comparing experi-these problems typically includes such strategies as replacing mental crack initiation and maximum moments with predictions suspect components with improved components, and imple-based on available fracture prediction models, and calculating menting improved maintenance programs.
J-R curves for the pipe expenments using the "-factor method.
NUREG/CR-6448 V01: EVALUATION OF NATIONAL SEISMO-NUREG/CR-6439: DESIGN OF THE IPIRG 2 SIMULATED SEIS-GRAPH NETWORK DETECTION CAPABILITIES. Annual MIC FORCING FUNCTION.
OLSON,R.;
SCOTT,P.M.;
WILKOWSKI,G.M. Battelle Memorial Institute, Columbus Labora-Report, July 1994 - July 1995.
MCLAUGHLIN,K.L; BENNETT T.J. S-Cubed. March 1996. 58pp. 9604150331. SSS-tories. February 1996. 86pp. 9602290278. BMI-2186.
TR 95-15216. 87867:286.
se of pipe system expenments was conducted in IPIRG.
s hrst annual W msents detech WesWs, deh l
2 thet used a realistic seismic forcing function. Because the tion probabilities, and location error ellipse projections for the seismic forcing function was more complex than the single-fre-United States National Seismic Network (USNSN) with and with-quency increasing-amplitude sinusoidal forcing function used in out cooperative stations in the eastern United States. Network the IPIRG-1 pipe system experiments, considerable effort went simulation methods are used with spectral noise levels at sta-into designing the function. This report documents the design tions to simulate the processes of excitation, propagatx)n, de-process for the seismic forcing function used in the IPIRG-2 tection, and processing of seismic phases. The USNSN alone pipe system expenments.
should be capable of detecting 4 or more P waves for shallow crustal earthquakes in nearty all of the eastern and central NUREG/CR 6442: EVIDENCE OF AGING EFFECTS ON CER-United States at the magnitude 3.8 level. When cooperative sta-TAIN SAFETY-RELATED COMPONENTS. MAGLEBY,H.L; tions are added, the network should be capable of detecting 4 ATWOOD.C.L; MACDONALD P E.; et al. Idaho National Engi-or more P waves from events 0.2 to 0.3 magnitude units lower.
neenng Laboratory. January 1996. 74pp. 9603180353. INEL-95/
The planned expansion of the USNSN and cooperative stations 0654. 87511:281.
should improve detection levels by an additional 0.2 to 0.3 mag-In response to interest shown by the Nuclear Energy Agency nitudes units in any areas. Location uncertainties for the (NEA), Pnncipal Working Group (PWG-1) of the Committee on USNSN can be significantly improved by addition of real-time the Safety of Nuclear installations (CSNI) conducted a generic cooperative stations. Median error ellipses for magnitude 4.5 study on the effects of aging of active components in nuclear earthquakes depend strongly on location, but uncertainties power plants. (This focus on active components is consistent should be less than 100 km(2) in the central United States and with PWG-1's mandate; passive components are primarily within degrade to 200 km(2) or more off-shore and south and north of the mandate of PWG-3.) RepresentatWes from France, Sweden, the international boundaries. Close cooperation with the Canadi-Finland, Japan, the United States, and the United Kingdom par-an National Network should substantially improve detection ticipated in the study by submitting reports documenting aging thresholds and location uncertainties along the Canadian studies performed in their countnes. This report consists of border.
Secondary Report Number Index This index lists, in alphabetical order, the performing organization-issued report codes for the NRC contractor and international agreement reports in this compilation. Each code is cross-referenced to the NUREG number for the report and to the 10-digit NRC Document Control System accession number.
SECONDARY REPORT NUMBER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER ANL-95/41 NUREG/CR-4667 V20 ORNL-6814 NUREG/CR-6248 BMI-2186 NUREG/CR4337 PNL 10709 NUREG/CR4366 BMI 2186 NUREG/CR4439 PNL 10643 NUREG/CR4346 j
BMI-2188 NUREG/CR4438 PNL 10934 NUREG/CR4435 BNL-NUREG-52460 NUREG/CR4336 PNL-4221 NUREG/CR-2850 V14 RNL-NUREG-52462 NUREG/CR4339 PNL4856 NUREG/CR4124 BNL-NUREG 52463 NUREG/CR4340 PNL-8919 NUREG/CR-5985 S01 BNL-NUREG 52486 NUREG/CR4415 PNL-9444 NUREG/CR4230 BNL-NUREG-52491 NUREG/CR4422 SAN 095-2381 NUREG/CR4338 INEL 95/0512 NUREG/CR4396 SEA 95 55446A.8 NUREG/CR4367 INEL-95/0551 NUREG/CR4407 SEASF-DR-94-001 NUREG/CR-6432 INEL 95/0573 NUREG/CR-5753 SSS-TR-9515216 NUREG/CR4448 V01 INEL-95/0654 NUREG/CR4442 UCRL-ID 122514 NUREG/CR4430 NEA/CSNI/R(95)9 NUREG/CR4442 UCAL-ID-122526 NUREG/CR4421 11
'Amhma-weem - u aw-m m -waAs-d.-43-J*E C-4 aA4 J-A mea-e-M.Dhh e es 4 5 -
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Personal Author index N
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-ticn by the NUREG number.
AAIERG,R.L CARROLL.D.P.
NUREG/CR-2950 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREG/CR-6340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.
VICES IN NUCLEAR POWER PLANTS.
ALLEN,M.D.
CHOPRA.O.K.
NUREG/CR4338: RESOLUTON OF THE DIRECT CONTAINMENT NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE LIGHT WATER REACTORS. Serniannual Report, October 1994 - March DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.
I995.
ANGEL LJ.
CHUNG H.M.
NUREG/CR.5985 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN TRASONIC INSERVICE INSPECTION SYSTEM.
LIGHT WATER REACTORS. Sermannual Report,0ctober 1994 - March ATWOOD,C.L 1995.
NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN CLARK R.L SAFETY RELATED COMPONENTS.
NUREG/CR-6246; EFFECTS OF AGING AND SERVICE WEAR ON AYERS,A.L MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.
NUREG/CR4407: CLASSIFICATON OF TRANSPORTATION PACKAG-L COMES'G/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FO ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-NURE CORDING TO IMPORTANCE TO SAFETY.
AUTOMATING ECCS SWITCHOVER AT PWRS.
EAKER.D.A.
NUREG/CR 2850 V14. DOSE COMMITMENTS DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992 NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.
SENNETT,T.J.
f NU R 4340 GIN SSES N OF SURGE PROTECTIVE DE-K E
ABI IE An 9
SLASING,T.S.
DIAMOND,D.J.
NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
NURZG/CR4422-POWER EXCURSION ANALYSIS FOR HIGH ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE BURNUP CORES.
ATLAS SITE,MOAB. UTAH. Source Material License No. SUA.
OlBIASIO,A-917, Docket No. 40 3453. (Atlas Corporation)
NUREG/CR-6339: AGING ASSESSMENT OF WESTINGHOUSE PWR COLTON,H.
AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC.
NUREG/CR4124: CHARACTER 12ATION OF RADIONUCUDE-CHELAT.
TONS.
ING AGENT COMPLEXES FOUND IN LOW LEVEL RADCACTIVE DE-AS CONTAMINATION WASTE. Uterature Review.
NURE
'5 DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-BRAMWELL.D.L ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN ATLAS SITE.MOAB. UTAH. Source Matenal Ucense No. SUA-SAFETY RELATED COMPONENTS.
917. Docket No. 40-3453. (Atlas Corporation)
BRIDEAU,J.
EDDLEMON,0.K.
NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-AUTOMATING ECCS SWITCHOVER AT PWRS.
ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE ATLAS SITE,MOAB, UTAH. Source Matenal Ucense No. SUA-BRUMMETT,E.
917, Docket No. 40-3453. (Atlas Corporation)
NUREG-1532: DRAFT TECHNICAL EVALUATON REPORT FOR THE PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-EDSON,J.L PORATION MOAB MILLSource Matenal Ucense No. SUA-917, Docket NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN No. 40-3453.(Atlas Corporation)
SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN CAMPBELL.J.A.
SAFETY-RELATED COMPONENTS.
NUREG/CR4124: CHARACTERIZATION OF RADIONUCUDE-CHELAT.
ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-FELMY,A.R.
CONTAMINATON WASTE. Uterature Review.
NOREG/CR4124: CHARACTERIZATION OF RADIONUCUDE-CHELAT-ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-CANTRELL,K.J.
CONTAMINATION WASTE. Uterature Review.
NUREG/CR4124: CHARACTER 12ATION OF RADIONUCUDE-CHELAT-ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADCACTIVE DE-FLIEGEL,M.
CONTAMINATION WASTE. Uterature Review.
NUREG-1531: ORAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
ED TO RECLAMATON OF THE URANIUM MILL TAILINGS AT THE CAPLIN,J.
ATLAS SITE,MOAB. UTAH. Source Matenal Ucense No. SUA-NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON gt7, Docket No. 40-3453. (Atlas Corporation)
RADCLOGICAL CRITERIA FOR DECOMMISSONING AND RELATED NUREG-1532: ORAFT TECHNICAL EVALUATION REPORT FOR THE DOCUMENTS.
PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-13
14 Personal Author index PORATION MOAB MILLSource Matonal Liense No. SUA-917, Docket JUSTUS,P.
No. 40-3453.(Atlas Corporation)
NUREG 1532: DRAFT TECHNICAL EVALUATON REPORT FOR THE PROPOSED REVISED RECLAMATON PLAN FOR THE ATLAS COR-NU EG CR 2 : CHARACTER 12ATON OF RADIONUCUDE-CHELAT.
40-34 3 Atla tion)
ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-CONTAMINATION WASTE. Uterature Renew KASSNER,T.F.
NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG 667 V20. ENVIRONMENTALLY ASSISTED CRACKING IN 99 '
UGHT WATER REACTORS. Semiannual Report,0ctober 1994. March 1995-KAVANAJGH,0.C.
NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN.
GEE G.W' CR4346: HYDROLOGIC EVALUATON METHODOLOGY FOR CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT NUREG/
OPERATIONS AND MAINTENANCE COSTS.
ESTIMATING WATER MOVEMENT THP.OUGH THE UNSATURATED ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-KLAMERUS.E.W.
POSAL SITES-NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT GROVE.E.
HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.
AN GENERAL ELECTRIC BWR CONTAINMENT ISOI.ATION FUNC.
KNOODSMA.R.L NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
GUTTMANN,H.
ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR ATMS SITE.MOAB, UTAH. Source Matenal License No. SUA.
AUTOMATING ECCS SWITCHOVER AT PWRS.
917. Docket No. 40-3453. (Atlas Corporation)
GUZMAN A.
KOHUT,P.
NUREG/CR4096:
APACHE LEAP TUFF INTRAVAL NUREG/CR4422: POWER EXOURSION ANALYSIS FOR HIGH FXPERIMENTS.Results And Lessons Leamed.
BURNUP CORES.
HAFFNER,D.R.
KRUPKA.K.M.
NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECOM-NUREG/CR4124: CHARACTERIZATION OF RADIONUCUDE-CHELAT.
MISSIONING A REFERENOE LARGE IRRADIATOR AND REFER-ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE CE-ENCE SEALED SOURCES.
CONTAMINATION WASTE. Uterature Rewow.
HAGEMEYER.D.
LAWRENCE,J.D.
NUREG-0713 V16: OCCUPATIONAL RADIATION EXPOSURE AT COM-NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.
MERICAL NUCLEAR POWER REACTORS AND OTHER FACILITIES,1994. Twenty-Seventh Annual Report.
LAYTON,M.
NUREG 1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE HARRIS,R.V.
PROPOSED REVISED RECLAMATON PLAN FOR THE ATLAS COR-NUREG/CR-5985 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-PORATON MOAB MILLSource Matenal Ucense No. SUA-917, Docket TRASONIC INSERVICE INSPECTION SYSTEM.
No. 40-3453.(Atlas Corporation)
HARTLEY,R.S' 396:
LEE B.S.
NUREG/CR4 EXAMPLES. CLARIFICATIONS. AND GUIDANCE ON NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN.
AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC-SERVICE TESTING REQU!REMENTS.
TONS.
HILLS,R.G.
lI NUR /CR
- POLYRES: A POLYGON-BASED RICHARDS EQUA.
b/CR4279: APPLICATON OF FRACTURE TOUGHNESS SCAL-N ING MODELS TO THE DUCTILE-TO-BRITTLE TRANSITION.
HINS,A.G.
NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN MACDONALD,P.E.
LIGHT WATER REACTORS. Semiannual Report,0ctober 1994. March NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN 1995.
SAFETY-RELATED COMPONENTS.
10RAHIM,A.
MAGLE8Y,H.L NUREG 1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE NUREG/CR4442 EVOENCE OF AGING EFFECTS ON CERTAIN PROPOSED REVISED RECLAMATON PLAN FOR THE ATLAS COR-SAFETY-RELATED COMPONENTS.
PORATION MOAB MILLSource Matenal Ucense No. SUA.917, Docket No. 40-3453.(Atlas Corporattori)
MCCONNELL,J.W.
NUREG/CR4407: CLASSlFICATON OF TRANSPORTATON PACKAG-JESSOP,5.H.
ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-NUREG/CR4419: SOLUBluTY TESTING OF ACTINIDES ON BREATH-CORDING TO IMPORTANCE TO SAFETY.
ING-ZONE AND AREA AIR SAMPLES.
MCDOWELL,8.L JOHNSON,R.O.
NUREG/CR4419: SOLUBluTY TESTING OF ACTINIDES ON E9EATH-NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-ING-ZONE AND AREA AIR SAMPLES.
ED TO RECLAMATON OF THE URANIUM LILL TAluNGS AT THE ATLAS SITE.MOAB, UTAH. Source Matenal Ucense No. SUA-MCLAUGHUN,K.L 917, Docket No. 40-3453. (Atlas Corporation)
NUREG/CR4448 V01: EVALUATION OF NATONAL SEISMOGRAPH NETWORK DETECTION CAPABILITIES. Annual Report, July 1994 July JOHNSON,T.
1995.
NUREG-1532-DRAFT TECHNICAL EVALUATION REPORT FOR THE PROPOSED REVISED RECLAMATON PLAN FOR THE ATLAS COR-METZGER,R.L PORATION MOAB MILLSource Matenal Ucense No. SUA-917, Docket NUREG/CR4419: SOLUBluTY TESTING OF ACTINIDES ON BREATH-No. 40-3453.(Atlas Corporation)
ING ZONE AND AREA AIR SAMPLES.
JOYCE J.A.
MEYER,P.D.
NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL.
NUREG/CR4346: HYDROLOGIC EVALUATION METHOOOLOGY FOR ING MODELS TO THE DUCTILE TO-BRITTLE TRANSITION.
ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED
1 Personal Author Index 15 ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-REED,R.M.
POSAL SITES.
NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA-ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE TION SOLVER-ATLAS SITE.MOAB. UTAH. Source Matenal License No. SUA.
MONROE #.K.
917, Docket No. 40-3453. (Atlas Corporation)
NUREG/CR4435. AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-RHODES.S.C CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT NUREG/Ch4098:
APACHE LEAP TUFF INTRAVAL OPERATIONS AND MAINTENANCE COSTS.
EXPERIMENTS.Results And Lessons Learned.
MONTELEONES.
NUREG/CP 0149 V01: PROCEEDINGS OF THE TWENTY THIRD ERTS,EM.
WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses-NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN sion. High Burnup Fuel Behavior Thermal Hydraulic Research.
SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
NUREG/CP.0149 V02: PROCEEDINGS OF THE TWENTY. THIRD WATER REACTOR SAFETY INFORMATION MEETING. Human Factors RO8ERTSON.D.E.
Research, Advanced l&C Hardware & Software Severe Accident Re.
NUREG/CR4230 RADIOANALYTICAL TECHNOLOGY FOR 10 CFR search, Probabilistic Risk Assessment Topics, Individual Plant Examina_
PAAT 61 AND OTHER SELECTED RADIONUCLlDES. Literature tion.
Review.
NUREG/CP 0149 V03. PROCEEDINGS OF THE TWENTY. THIRD WATER REACTOR SAFETY INFORMATION MEETING. Structural &
ROCKHOLD,M.L i
l Seismic Engineenng. Pnmary Systems integrity. Egi.mpment Operatulity NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR And Aging. ECCS Strainer Blockage Research & Regulatory lasues.
ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED i
ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE WASTE DIS-l MULLINS.A.T.
POSAL SITES.
l NUREG-1531: DRAFT ENVIROf' MENTAL IMPACT STATEMENT REL AT.
NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA-l ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE TION SOLVER.
ATLAS SITE.MOAB UTAH. Source Matenal License No. SUA-i i
'917. Docket No. 40-3453. (Atlas Corporation)
ROM,D.
NUREG 1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE NEUMAN S.P.
PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR.
NUREG/CR4096:
APACHE LEAP TUFF INTRAVAL PORATION MOAB MILL. Source Matenal License No. SUA-917. Docket EXPERIMENTS.Results And Lessons Learned.
No. 40-34S3 (Atlas Corporation)
NEYMOTIN,L ROSENFIELD,A.
NUREG/CR4422: POWER EXCURSION ANAL YSIS FOR HIGH BURNUP CORES.
NUREG/CR4337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 ROUND-ROBIN ANALYSES.
NICHOLS,W.E.
NU EG/C 4438 THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON EST ATI WATE MO MENT R H THE U A AT D ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE WASTE DIS-CARBON STEEL PIPE.
POSAL SITES.
RUTHER,W.E.
OLSON,R.
NUREG/CR 4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR-6337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 LIGHT WATER REACTORS. Semiannual Report,0ctober 1994 March ROUND-ROBIN ANALYSES.
1995.
NUREG/CR4439: DESIGN OF THE IPIRG-2 S!MULATED SEISMIC FORCING FUNCTION.
SAMANTA.P.K.
NUREG/CR-6415: APPLICATIONS OF RELIABILITY DEGRADATION PAGE.G.
ANALYSIS.
NUREG/CR4353: COMMENTS TECEIVED ON PROPOSED RULE ON RADIOLOGICAL CRITERIA FOR MCOMMISSIONING AND RELATED SCIACCA,F.
DOCUMENTS.
NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.
PETRICH C.H.
NUREG 1531: DRAFT ENVIRONMENTAL NPACT STATEMENT RELAT-SCOTT,J.A.
ED TO RECLAMATION OF THE URANIUC W L TAILINGS AT THE NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR COM-ATLAS SITE,MOAB. UTAH. Source Matenal License No. SUA.
MERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN REACTOR APPLl-917. Docket No. 40-3453. (Atlas Corporation)
CATIONS.
PILCH,M.M.
SCOTT.P.M.
NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT NUREG/CR4438: THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON HEATING ISSUE FOR ALL WESTINGitOUSE PLANTS WITH LARGE CARBON STEEL PIPE.
DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.
NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC FORCING FUNCTION.
PRECKSHOT,G.G.
NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR COM-SERNE,R.J.
MERCIAL OFF.THE-SHELF (COTS) SOFTWARE IN REACTOR APPLI-NI' REG /CR4124 CHARACTERIZATION OF RADIONUCLIDECHELAT-CATIONS.
ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE.
RAHMAN,S.
CONTAMINATION WASTE. Literature Review.
SUMMARY
OF RESULTS FROM THE IPIRG 2 SHACK,W.J.
ROUND-ROBIN ANALYSES.
NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN RANSOM.C.B.
LIGHT WATER REACTORS. Semiannual Report. October 1994 - March NUREG/CR4396: EXAMPLES, CLARIFICATIONS, AND GUIDANCE ON 1995.
PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN.
SERVICE TESTING REQUIREMENTS.
N R G/CR4353: COMMENTS RECElVED ON PROPOSED RULE ON RAO,D.V.
RADIOLOGICAL CRITERIA FOR DFCOMMISSIONING AND RELATED NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL.
DOCUMENTS.
TRATION FOR LOCA DEBRIS.
RASMUSSEN,T.C.
NUREG/CR.4667 V20 ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR 6096:
APACHE LEAP TUFF INTRAVAL LIGHT WATER REACTORS. Semiannual Report, October 1994 - March EXPERIMENTS.Results And Lessons Leamed.
1995.
l 16 Personal Author Index SOUTO,F.
UDY,A.C.
NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN AUTOMATING ECCS SWITCHOVER AT PWRS.
SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
SOUTO,F.J.
VAN DYKE,J.W.
NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
TRATION FOR LOCA DEBRIS.
ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE ATLAS SITE.MOAB. UTAH. Source Material Ucense No. SUA-STAUS,W.P.
NUREG 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
917, Docket No. 443453. (Anas Corporaton)
ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE
^
N RE 4415: APPLICATIONS OF RELIABILITY DEGRADATION 7
tN 0-
. tlas a )
ANALYSIS.
STRUCKMEYER,R.
NUREG-0837 V15 N04: NRC TLD DIRECT RADIATION MONITORING VILLARAN,M.
NETWORK. Progress Report. October-December 1995.
NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC MOTORS IN NUCLEAR POWER PLANTS.
SUBUDHI,M.
NURFG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC VILLEGAS.A.J.
MOTORS IN NUCLEAR POWER PLANTS-NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECOM-NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER-VICES IN NUCLEAR POWER PLANTS.
ENCE SEALED SOURCES.
TAM,P.S.
WALSH'G/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR 8
NUREG-0647 S20: SAFETY EVALUATION REPORT RELATED TO THE NURE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND AUTOMATING ECCS SWITCHOVER AT PWRS'
- 2. Docket Nos. 50-390 And 50-391.(Tennessee Valley Authonty)
WALSH,P.J.
THOMAS,C.W.
J NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR NUREG 1531: DW.FT ENVIRONMENTAL IMPACT STATEMENT RELAT.
PART 61 AND OTHER SELECTED RADIONUCLIDES t aerature ED TO RECLAMATON OF THE URANIUM MILL TAILINGS AT THE payiew.
ATLAS SITE.MOAB, UTAH. Source Matenal Ucense No. SUA-917, Docket No. 40-3453. (Atlas Corporation)
THOMAS.M.L NUREG-0713 V16: OCCUPATIONAL RADIATION EXPOSURE AT COM-WISLIN,C.
MERICAL NUCLEAR POWER REACTORS AND OTHER NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON FACILITIES,1994. Twenty-Seventh Annual Report.
RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED THOMAS,V.W.
NUREG/CR4230 RADIOANALYTICAL TECHNOLOGY FOR 10 CFR WILKOWSKI,G.M.
PART 61 AND OTHER SELECTED RADIONUCLIDES. Literature NUREG/CR4337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 Review-ROUND-ROBIN ANALYSES.
NUREG/CR4438: THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON THOMAS,W NUREG/CR4432 ESTIMATED NET VALUE AND UNCERTAINTY FOR RB,0
. ENGN OF THE IPIRG-2 SIMULATED SEISMIC L
NU G AUTOMATING ECCS SWITCHOVER AT PWRS.
FORCING FUNCTION.
TRAYlSR.
NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR WOOO.R.S.
GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC.
NURE 443 AN AN Y THEIMPACT CC OM OPERATIONS AND MAINTENANCE COSTS.
TYACKE,M.J.
NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG.
ZlGLER.G.
ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC.
NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR CORDING TO IMPORTANCE TO SAFETY.
AUTOMATING ECCS SWITCHOVER AT PWRS.
i Subject index 1
1 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.
1 10 CFR "MRT s1 Brittle Fracture NUREG/CR4230 RADf0 ANALYTICAL TECHNOLOGY FOR 10 CFR NUREG/CR4279: APPLICATON OF FRACTURE TOUGHNESS SCAL-l PART 61 AND OTHER SELECTED RADIONUCLOES. Literature Rowew.
ING MODELS TO THE DUCTILE TO-BRITTLE TRANSITION.
Budget N
NO2: REPORT TO CONGRESS ON ABNORMAL OCCURRENCES. April-June 1995-Certson Stoet NUREG4090 V18 NO3. REPORT TO CONGRESS ON ABNORMAL OCCURRENCES. July-September 1995.
NUREG/CR4438: THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON CARBON STEEL PIPE.
Actinids NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON BREATH.
Cheinung Agent ING-ZONE AND AREA AIR SAMPLES.
NUREG/CR4124; CHARACTER 12ATION OF RADIONUCLlDE-CHELAT-ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-Aging CONTAMINATON WASTE. Literature Rowew.
NUREG/CP-0149 V03: PROCEEDINGS OF THE TWENTY-THIRD WATER REACTOR SAFETY INFORMATON MEETING. Structural &
Collective Does Seesmic Engineenng. Pnmary Systems integnty Equipment Operatulity NUREG 0713 V16 OCCUPATONAL RADIATON EXPOSURE AT COM-And Aging. ECCS Strainer Blockage Research & Regulatory. lssues.
MERICAL NUCLEAR POWER REACTORS AND OTHER NUREG/Cm5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN FACILITIES,1994. Twenty-Seventh Annual Report SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
NUREG/CR-6246: EFFECTS OF AGING AND SERVICE WEAR ON Commercial Software MAIN STEAM ISOLATON VALVES AND VALVE OPERATORS.
NUREG/CR-6421: A PROPOSED ACCEPTANCE PROCESS FOR COM-NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC MOTORS IN NUCLEAR POWER PLANTS.
MERCIAL OFF THE-SHELF (COTS) SOFTWARE IN REACTOR APPLl-NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR CATIONS' AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC-Containment teolation NUR /CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR VICES IN NUCLEAR POWER PLANTS.
AND GENERAL ELECTRIC BWR CONTAINMENT PSOLATION FUNC-NUREG/CR4442: EVIDENCE OF AGIM EFFECTS ON CERTAIN TONS.
SAFETY-RELATED COMPONENTS.
Air 6 _ : 7, NUREG-1544: STATUS REPORT: INTERGRANULAR STRESS CORRO.
NOREG/CR-6096:
APACHE LEAP TUFF INTRAVAL SiON CRACKING OF BWR CORE SHROUDS AND OTHER INTERNAL EXPERIMENTS.Results And Lessons Leamed.
COMPONENTS.
Apache Leap Tuff Corroe6on Fetigue NUREG/CR4096:
APACHE LEAP TUFF INTRAVAL EXPERIMENTS.Results And Lessons Leamed.
NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS. Semiannual Report,0ctober 1994 - March h Air W 1995.
NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON BREATH-ING-ZONE AND AREA AIR SAMPLES.
Cost Estime*e NUREG/CR4280; TECHNOLOGY, SAFETY,AND COSTS OF DECOM-Atmospheric Rolesse MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER-NUREG/CR-2850 V14: DOSE COMMITirNTS DUE TO RADIOACTIVE ENCE SEALED SOURCES.
RELEASES FROM NUCLEAR POWE. 'NT SITES IN 1992.
Dec,_
flWR
..i, NUREG/CR-6280 TECHNOLOGY, SAFETY,AND COSTS OF DECOM-NUREG-1544: STATUS REPORT: INTERGRANULAR STRESS CORRO-MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER.
SiON CRACKING OF BWR CORE SHROUDS AND OTHER INTERNAL ENCE SEALED SOURCES.
COMPONENTS.
NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON TRATION FOR LOCA DEBRIS.
RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED DOCUMENTS.
NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH BURNUP CORES.
Decontamination Bomng h Reactor NUREG/CR4124; CHARACTERIZATION OF RADIONUCUDE CHELAT.
NUREG 1544: STATUS REPORT: INTERGRANULAR STRESS CORRO.
ING AGENT COMPLEXES FOUND IN LOW LEVEL RADCACTIVE DE-SiON CRACKING OF BWR CORE SHROUDS AND OTHER INTERNAL CONTAMINATION WASTE. Uterature Review.
COMPONENTS.
NUR /CR 7: PE NTAL STUDY OF HEAD LOSS AND FIL-R4415; APPLICATONS OF REUABILITY DEGRADATION NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH ANALYSIS.
BURNUP CORES.
Detection Throehold Greething-Zone NUREG/CR4448 V01: EVALUATON OF NATIONAL SEISMOGRAPH NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON BREATH.
NETWORK DETECTON CAPABlUTIES. Annual Report. July 1994 - July ING-ZONE AND AREA AIR SAMPLES.
1995.
17
l l
18 Subject index Direet Containment Homun0 Guidollne NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT NUREG-1537 PT01: GUIDELINES FOR PREPARING AND REVIEWING HEATING ISSUE FOR ALL WESTINGHOUSE PUNTS WITH LARGE APPLICATONS FOR THE LICENSING OF NON-POWER DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.
REACTORS.Part 1: Format And Content.
NUREG-1537 PT02: GUIDELINES FOR PREPARING AND REVIEWING Does Commitment APPLICATIONS FOR THE LICENSING OF NON-POWER NUREG/CR-2650 V14: DOSE COMMITMENTS DUE TO RADCACTIVE REACTORS.Part 2: Standard Review Plan And Acceptance Cntena.
RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.
Hazard Analyele
^
U 4338: RESOLUTON OF THE DIRECT CONTAINMENT HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE Hood Loes DAY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS-NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-TRATON FOR LOCA DEDRIS.
TW NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL
- High Burnup Core ING MODELS TO THE DUCTILE TO-BRnTLE TRANSITON.
NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH BURNUP CORES.
p%
NUREG/CR4438:THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON Human RollatWilty CARBON STEEL PlPE.
NUREG/CR-6432: ESTIMATED NET VALUE AND UNCERTAINTY FOR AUTOMATING ECCS SWITCHOVER AT PWRS.
ECCS NUREG/CP4149 V03: PROCEEDINGS OF THE TWENTY THIRD Hy WATER REACTOR SAFETY INFORMATION MEETING. Structural &
NU
/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR Seisme Engmeenng, Pnmary Systems integnty, Equipment Operatulity ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED And Aging. ECCS Stra nor Blockage Research & Regulatory issues.
ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-ECCS SwMchovsr POSAL SITES.
NUREG/CR4432-ESTIMATED NET VALUE AND UNCERTAINTY FOR NUREG/CR-6366: POLYRES: A POLYGON. BASED RICHARDS EQUA.
AUTOMATING ECCS SWITCHOVER AT PWRS.
TION SOLVER.
Economic Incentive Program INTRAVAL Experiment NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-NUREG/CR-6096:
APACHE LEAP TU"F INTRAVAL CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT EXPERIMENTS.Results And Lessons Leamed.
OPERATIONS AND MAINTENANCE COSTS.
IPIRG-2 Electric Motor NUREG/CR-6337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC ROUND-ROBIN ANALYSES.
MOTORS IN NUCLEAR POWER PLANTS.
NVREG/CR-6439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC FORCING FUNCTION.
Enforcement Action NUREG 0940 V14N3&4P1: ENFORCEMENT ACTONS: SIGk.FICANT ISFSI ACTONS RESOLVED INDIVIDUAL ACTIONS. Semiannual Progress NUREG-1536 DAFT FC: STANDARD REVIEW PLAN FOR DRY SPENT R
-December 1995.
FUEL STORAGE SYSTEnnS. Draft Report For Comment.
NUR G-094 V14N3&4P2: ENFORCEMENT ACTONS: SIGNIFICANT ACTIONS RESOLVED REACTOR LICENSEES. Semiannual Progress inservice inspection System Report, July-December 1995.
NUREG/CR-5985 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-NUREG-0940 V14N384P3: ENFORCEMENT ACTONS: SIGNIFICANT TRASONIC INSERVICE INSPECTION SYSTEM.
ACTIONS RESOLVED MATERIAL LICENSEES. Semiannual Progress Report, July-December 1995.
Ineervice Testing NUREG/CR4396: EXAMPLES. CLARIFICATIONS, AND GUIDANCE ON Enytronmental impact Statement PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN-NUREG 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT*
SERVICE TESTING REQUIREMENTS.
ED TO RECLAMATON OF THE URANIUM MILL TAILINGS AT THE ATLAS SITE,MOAB. UTAH. Source Matenal Ucense No. SUA-lntergranular Strees Corrosion Cracking 917, Docket No. 40-3453. (Atias Corporation)
NUREG 1544: STATUS REPORT: INTERGRANULAR STRESS CORRO-NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON SiON CRACKING OF BWR CORE SHROUDS AND OTHER INTERNAL RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED COMPONENTS.
DOCUMENTS.
Irradiator Fault Tro NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECOM-NUREG/CR4430 SOFTWARE SAFETY HAZARD ANALYSIS.
MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER-ENCE SEALED SOURCES.
Format And Content Gulde NUREG-1537 PT01: GUIDELINES FOR PREPARING AND REVIEWING LOCA APPLICATIONS FOR THE UCENSING OF NON-POWER NUREG/CR-6367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL.
REACTORS.Part 1: Format And Content TRATON FOR LOCA DEBRIS.
Fracture Flow NUREG/CA-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN EXPE E Result And Lessons earW*
UGHT WATER REACTORS. Semiannual Report, October 1994 March 1995.
Fracture Toughnese NUREG/CR4279: APPUCA. TION OF FRACTURE TOUGHNESS SCAL-Leak-Rate ING MODELS TO THE DUCTILE TO-BRITTLE TRANSITION.
NUREG/CR4438: THE EFFECT OF CYCLIC AND DYNAMIC LOADS ON NUREG/CR4337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 CARBON STEEL PIPE.
ROUND-ROBIN ANALYSES.
Fuel Seheylor Legalleeuences NUREG/CP-0149 V01: PROCEEDINGS OF THE TWENTY-THIRD NUREG 0750 V41: NUCLEAR REGULATORY COMMISSION WATER REACTO1 SAFETY INFORMATON MEETING. Plenary Ses.
ISSUANCES.Opruons And Deciseens Of The Nuclear Regulatory Com-soon. High Bumup Fuel Behavior, Thermal Hydraulc Research.
rrussion With Selected Orders. January-June 1995.
NUREG-0750 V42102: INDEXES TO NUCLEAR REGULATORY COM-Generic Safety leeue 24 MGSION ISSUANCES. July _ December 1995.
NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR NUREG-0750 V42 N05: NUCLEAR REGULATORY COMMISSION IS.
AUTOMATING ECCS SWITCHOVER AT PWRS.
SU ANCES FOR NOVEMBER 1995 Pages 181219.
Subject Index 19 NUREG 0750 V42 N06. NUCLEAR REGULATORY COMMISSION IS-Research, Advanced l&C Hardware & Software, Severe Accident Re-SUANCES FOR DECEMBER 1995. Pages 221258.
Search, Probatxlistic Risk Assessment Topics, Iridividual Plant Examina-NUREG4750 V43 NO1: NUCLEAR REGULATORY COMMISSION IS-tion.
SUANCES FOR JANUARY 1996. Pages 1 11.
Proposed Rute Ught Water Reactor NUREG/CR-6353: COMMENTS RECElVED ON PROPOSED RULE ON NUREG/CR-4667 V20 ENVIRONMENTALLY ASSISTED CRACKING IN RADIOLOGIO^L CRITERIA FOR DECOMMISSIONING AND RELATED LIGHT WATER REACTORS. Semiannual Report October 1994 March DOCUMENTS.
1995.
Low-Lavel Radioactive Waste urnp TeeUng NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR NUREG/CR4396: EXAMPLES.CLAHIFICATIONS, AND GUIDANCE ON PART 61 AND OTHER SELECTED RADIONUCLIDES Literature PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN-Rm SERVICE TESTING REQUIREMENTS.
NUREG/CR4346: HYDROLOGtC EVALUATION METHODOLOGY FOR ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED Radiation Exposure ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-NUREG-0713 V16: OCCUPATIONAL RADIATION EXPOSURE AT COM-POSAL SITES.
MERICAL NUCLEAR POWER REACTORS AND OTHER FACILITIES,1994. Twenty-Seventh Annual Report.
Main Steam loolation Valve NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON Rad 6oactive Release MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.
NUREG/CR-2650 V14-DOSE COMMITMENTS DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.
Maintenance NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN Radioanalytical Technology SAFETY-RELATED COMPONENTS.
NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR PART 61 AND OTHER SELECTED RADONUCLIDES. Literature NUHEG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-
~
CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT Radiological Criteria OPERATIONS AND MAINTENANCE COSTS-NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON Motor Operated Valve RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED NUREG/CR4396: EXAMPLES. CLARIFICATIONS, AND GUIDANCE ON DOCUMENTS.
PREPARING REQUESTS FOR AELIEF FROM PUMP AND VALVE IN-Radionuclide SERVICE TESTING REQUIREMENTS
- NUREG/CR4124: CHARACTERIZATION OF RADIONUCLIDE-CHELAT-Not Value ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR CONTAMINATION WASTE. Literature Review.
AUTOMATING ECCS SWITCHOVER AT PWRS.
NUREG/CR-6230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR PART 61 AND OTHER SELECTED RADIONUCLIDES. Literature Network Simulation Review.
NUREG/CR4448 V01: EVALUATION OF NATIONAL SEISMOGRAPH NETWORK DETECTION CAPABILITIES. Annual Report. July 1994 - July Reactor Application 1995.
NUREG/CR-6421: A PROPOSED ACCEPTANCE PROCESS FOR COM-MERCIAL OFF THE-SHELF (COTS) SOFTWARE IN REACTOR APPLl-l l
Non Power Reactor CATIONS.
NUREG-1537 PT01: GUIDELINES FOR PREPARING AND REVIEWING APPLICATONS FOR THE LICENSING OF NON-POWER Reactor Component REACTORS.Part 1: Format And Content NUREG/CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR NUREG-1537 PT02: GUIDELINES FOR PREPARING AND REVIEWING AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION FUNC-APPLICATONS FOR THE LICENSING OF NON-POWER TONS.
REACTORS.Part 2: Standard Review Plan And Acceptance Cntena-NUREG/CR4415: APPLICATIONS OF RELIABILITY DEGRADATION A SIS.
Nondestructive Evaluation NUREG/CR-5985 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-Reactor Protection System TRASONIC INSERVICE INSPECTION SYSTEM-NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE.
Nuclear Power Plant VICES IN NUCLEAR POWER PLANTS.
NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-MM R A NUCLEAR POWER PLANT NUR G P-0149 V01: PROCEEDINGS OF THE TWENTY THIRD T S DM N
WATER REACTOR SAFETY INFORMATION MEETING. Plenary Ses.
Organization Chart 8'on High Bumup Fuel Behavior, Thermal Hydraulic Research.
NUREG-0325 R19: U.S. NUCLEAR REGULATORY COMMISSION OR.
NUREG/CP-0149 V02: PROCEEDINGS OF THE TWENTY THIRD GANIZATON CHARTS AND FUNCTIONAL STATEMENTS. January 31 WATER REACTOR SAFETY INFORMATON MEETING. Human Factors 1996.
Research, Advanced l&C Hardware & Software, Severe Accident Re-search, Probabilestic Risk Assessment Topics, Individual Plant Examina-Petitions For Rulemaking tion.
NUREG-0936 V14 NO2: NRC REGULATORY AGENDA.Semsannual NUREG/CP-0149 V03: PROCEEDINGS OF THE TWENTY-THIRD Report. July-December 1995.
WATER REACTOR SAFETY INFORMATON MEETING. Structural &
Seismic Engineenrg Pnmary Systems integrity, Equipment Operability Pipe And Aging. ECCS Strainer Blockage Research & Regulatory lasues.
NUREG/CR4337:
SUMMARY
OF RESULTS FROM THE lPIRG-2 NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE-
^
NUR C/
H F ECT OF CYCLIC AND DYNAMIC LOADS ON CARBON STEEL PIPE.
NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC Reactor System CD NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR COM-MERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN REACTOR APPLl-Obwer Excursion CATIONS.
NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH BURNUP CORES.
Reclamation NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-Probabastic Risk Assessment ED TO RECLAMATON OF THE URANIUM MILL TAILINGS AT THE NUREG/CP 0149 V02: PROCEEDINGS OF THE TWENTY-THIRD ATLAS SITE,MOAB, UTAH. Source Material License No. SUA-WATER REACTOR SAFETY INFORMATON MEETING. Human Factors 917, Docket No. 40-3453. (Atlas Corporation)
20 Subject Index NUREG-1532: DRAFT TECHNICAL EVALUATON REPORT FOR THE Research, Advanced l&C Hardware & Software, Severe Accsdent Re-PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-search, Probatulistic Risk Assessment Topics, Indmdual Plant Examina-PORATON MOAB MILLSource Matenal License No. SUA-917, Docket tion.
No. 40-3453.(Atlas Corporation)
Software Recorde Disposition NUREG/CR-6430: SOFTWARE SAFETY HAZARD ANALYSIS.
NUREG4910 R02 SO2: NRC COMPREHENSIVE RECORDS DISPOSI-TION SCHEDULE.
Spent Fuel NUREG-1536 DRFT FC: STANDARD REVIEW PLAN FOR DAY SPENT FUEL STORAGE SYSTEMS. Draft Report For Comrnent.
G-0936 4 NO2: NRC REGULATORY AGENDA. Semiannual NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG-Report. July-December 1995.
ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-Regulatory And Technical Report CORDING TO IMPORTANCE TO SAFETY.
NUREG 0304 V20 NO3: REGULATORY AND TECHN! CAL REPORTS (ABSTRACT INDEX JOURNAL). Compilaton for Third Quarte, Standard Review Plan 1995 July-September.
NUREG-1536 DAFT FC: STANDARD REVIEW PLAN FOR DRY SPENT FUEL STORAGE SYSTEMS. Draft Report For Comment.
Report To Congrees NUREG-1537 PT02: GUIDELINES FOA PREPARING AND REVIEWING NUREG-0090 V18 NO2: REPORT TO CONGRESS ON ABNORMAL APPLICATIONS FOR THE UCENSING OF NON-POWER OCCURRENCES.Aptd-June 1995.
REACTORS.Part 2. Standard Rewew Plan And Acceptance Cntena.
NUREG4090 V18 NO3: REPORT TO CONGRESS ON ABNORMAL OCCURRENCES. July September 1995.
Storage Cask NUREG 1536 DRFT FC: STANDARD REVIEN PLAN FOR DRY SPENT FUEL STORAGE SYSTEMS. Draft Report Fu Comment.
NR R02 S02: NRC COMPREHENSIVE RECORDS DISPOSI-TON SCHEDULE.
Storage System R6 chards Equation Sotver NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG-NUREG/CR-6366. POLYRES: A POLYGON-BASED RICHARDS EQUA.
ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-TION SOLVER.
CORDING TO IMPORTANCE TO SAFETY.
Rules Stress Corrosion Cracking NUREG-0936 V14 NO2: NRC REGULATORY AGENDA. Semiannual NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN Report. July-December 1995.
LIGHT WATER REACTORS. Semiannual Report, October 1994 - March 1995.
Safety Evaluation Report NUREG-0847 S20: SAFETY EVALUATON REPORT RELATED TO THE Substmospheric Containment OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND NUREG/CR-6338: RESOLUTION OF THE DIRECT CONTAINMENT 2 Docket Nos. 50-390 And 50-391.(Tennessee Valley Authonty)
HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS Wl'!H LARGE DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.
g gy,g NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN Subsur' fan Flow SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
NUREG/CR-6368: POLYRES: A POLYGON-BASED RICHARDS EOUA-Safety Related Componong TION SOLVER.
NUREG/CR4442 EVIDENCE OF AGING EFFECTS ON CERTAIN SAFETY-RELATED COMPONENTS.
Surtsco Crack NUREG/CR4337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 Schedule ROUND-ROBIN ANALYSES.
NUREG-0910 R02 S02: NRC COMPREHENSIVE RECORDS DISPOSI-NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC TON SCHEDULE.
FORCING FUNCTION.
Sealed Source Surge Protective Device NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECOM-NUREG/CR4340 AGING ASSESSMENT OF SURGE PROTECTIVE DE-MISSONING A REFERENCE URGE IRRADIATOR AND REFER-VICES IN NUCLEAR POWER PUNTS.
ENCE SEALED SOURCES.
System Analysis NUREG/CR4415: APPUCATONS OF REUABluTY DEGRADATION REG /CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMIC ANALYSIS.
FORCING FUNCTION.
Setemic Engineering TLD NUREG/CP-0149 V03: PROCEEDINGS OF THE TWENTY THIRD NUREG-0837 V15 N04. NRC TLD DIRECT RADIATION MONITORING WATER REACTOR SAFETY INFORMATION MEETING. Structural &
NETWORK. Progress Report. October-December 1995.
Seismic Engineenng, Pnmary Systems integnty Equipment Operability Ta And Aging, ECCS Strainer Blockage Research & Regulatory issues.
EG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT-U yaph ED TO RECLAMATON OF THE URANIUM MILL TAluNGS AT THE NUREG/CR4448 V01: EVALUATION OF NATIONAL SEISMOGRAPH ATLAS SITE.MOAB, UTAH. Source Material License No. SUA-NETWORK DETECTION CAPABIUTIES. Annual Report. July 1994 July 917. Docket No. 40-3453. (Atlas Corporation) 1995.
NUREG 1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE PROPOSED REVISED RECLAMATON PLAN FOR THE ATLAS COR.
EG CR4339: AGING ASSESSMENT OF WESTINGHOUSE PWR 4 3453 A tion AND GENERAL ELECTRIC BWR CONTAst. MENT ISOLATON FUNC-TONS-Technical Evaluation Report NUREG/CR4415: APPUCATIONS OF RELIABILITY DEGRADATON NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE ANALYSIS-PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR-Service Wear PORATON MOAB MILLSource Matenal License No. SUA-917, Docket NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON No. 40-3453.(Atlas Corporation)
MAIN S1EAM ISOLATION VALVES AND VALVE OPERATORS.
Severo Accident NUREG/CP-0149 V01: PROCEEDINGS OF THE TWENTY-THIRD NUREG/CP4149 V02: PROCEEDINGS OF THE TWENTY-THIRD WATER REACTOR SAFETY INFORMATON MEETING Plenary Ses-WATER REACTOR SAFETY INFORMATION MEETING. Human Factors sion, High Bumup Fuel Behavor. Thermal Hydraulic Research.
l l
Subject index 21 T;.. : _..
cent Dosimeter ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-NUREG4637 V15 N04: NRC TLD DIRECT RADIATION MONITORING POSAL SITES.
NETWORK. Progress Report. October. December 1995.
NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA.
TlON SOLVER.
NUREG4540 V17 N"1: TITLE LIST OF DOCUMENTS MADE PUBLICLY Utenium NUIE V
2 TITLE Li OF DOCUMENTS MADE PUBLICLY NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON BREATH-AVAILABLE. Decembei 1 31, 1995.
ING-ZONE AND AREA AIR SAMPLES.
Topical Report Urenium Mill NUREG 0390 V10: TOPICAL REPORT REVIEW STATUS.(Blue Book)
NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
i.
TrWormer ED TO RECLAMATION OF THE URANIUM MILL TAILINGS AT THE ATLAS SITE,MOAB, UTAH. Source Matenal License No. SUA-l NUREG/CR-5753: AGING OF SJETY CLASS 1E TRANSFORMERS IN 917. Docket No. 40 3453. (Atlas Corporation)
SAFETY SYSTEMS OF NUCLEA7 POWER PLANTS.
NUREG-1532: DRAFT TECHNICAL EVALUATION REPORT FOR THE Trenetont Worker PROPOSED REVISED RECLAMATION PLAN FOR THE ATLAS COR.
NUREG-0713 V16: OCCUPATIONAL MDIATION EXPOSURE AT COM-PORATION MOAB MILLSource Matenal License No. SUA 917, Docket MERICAL NUCLEAR POWER REACTORS AND OTHER No. 40 3453.(Atlas Corporeton)
FACILITIES,1994 Twenty-Seventh Annual Report.
yg Treneportetton Packaging NUREG/CR4246: EFFECTS OF AGING AND SERVICE WEAR ON NUREG/CR4407; CLASSIFICATION OF TRANSPORTATION PACKAG-MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.
ING AND DRY SPENT FUEL STORAGE SYSTEM COMPONENTS AC-CORDING TO IMPORTANCE TO SAFETY.
Veno Testing N
NUREG/CR4396: EXAMPLES. CLARIFICATIONS, AND GUlOANCE ON PREPARING REQUESTS FOR RELIEF FROM PUMP AND VALVE IN-NUREG/CR-5985 S01: REVIEW OF P. SCAN COMPUTER-BASED UL-SERVICE TESTING REQUIREMENTS.
TRASONIC INSERVICE INSPECTION SYSTEM.
Underground D6sposal V'"d '"*P''*"
NUREG/CR4346: HYDROLOGIC EVALUATION METHODOLOGY FOR NUREG-0040 V19 N04: LICENSEE CONTRACTOR AND VENDOR IN-ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED SPECTION STATUS REPORT. Quarterly Report, October December ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-1995Mbite BaA)
POSAL SITES.
Uneaturated Zone NUREG/CR4124: CHARACTERl2ATION OF RADIONUCLIDE CHELAT.
NUREG/CR4346: HYDROLOGIO EVALUATION METHODOLOGY FOR ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-ESTIMATING WATER MOVEMENT THROUGH THE UNSATURATED CONTAMINATION WASTE. Literature Review.
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 crganizations (e.g., program offices) and then by sub-I 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.
OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
NUREG-0090 V18 NO3: REPORT TO CONGRESS ON ABNORMAL REGION 1 (POST 820201)
OCCURRENCES. July-September 1995.
NUREG 0837 V15 N04: NRC TLD DIRECT RADIATION MONITORING NETWORK. Progress Report. October December 1995.
EDO - OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM OFC OF ENFORCEMENT (POST 870413)
(POST 861100)
NUREG-0940 V14N344P1: ENFORCEMENT ACTIONS: SIGN!FICANT INFORMATON & RECORDS MANAGEMENT BRANCH (POST 890827)
ACTONS RESOLVED INDIVIDUAL ACTIONS.Sermannual Progress NUREG4910 R02 S02: NRC COMPREHENSIVE RECORDS DISPOSI-Renort. July-December 1995-TION SCHEDULE.
NUREG-0940 V14N3&4P2: ENFORCEMENT ACTIONS: SIGNIFICANT ACTIONS RESOLVED REACTOR UCENSEES. Semiannual Progress EDO. OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS Report. July-December 1995.
OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS NUREG-0940 V14N3&4P3: ENFORCEMENT ACTIONS: SIGNIFICANT NUREG 1536 DRFT FC: STANDARD REVIEW PLAN FOR DAY ACTIONS RESOLVED MATERIAL UCENSEES.Semaannual Progress SPENT FUEL STORAGE SYSTEMS. Draft Report For Comment Report. July-December 1995.
DIVISION OF WASTE MANAGEMENT (NMSS 940403)
OFC OF PERSONNEL (POST 870413)
NUREG-1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RE.
NUREG4325 R19. U.S. NUCLEAR REGULATORY COMMISSON OR.
LATED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT GANIZATON CHARTS AND FUNCTIONAL STATEMENTS. January THE ATLAS SITE,MOAB, UTAH. Source Matenal License No. SUA-917. Docket No. 40-3453. (Atlas Corporation)
EDO OFFICE OF ADMINISTRATION (PRE 870413 & POST 890205)
NUREG-1532-DRAFT TECHNICAL EVALUATION REPOR' 'OR THE DIVISION OF FREEDOM OF INFORMATION & PUBLICATIONS SERV.
PROPOSED REVISED RECLAMATON PLAN FOR THE ATLAS ICES (POST 940714 CORPORATON MOAB MILLSource Material Ucense No. SUA-NUREG-0304 V20 NO3: REGULATORY AND TECHNICAL REPORTS 917, Docket No. 40-3453.(Atlas Corporation)
(ABSTRACT INDEX JOURNAL). Compilation for TNrd Quarter 1995. July-September.
EDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820406)
NUREG4540 V17 N11: TITLE UST OF DOCUMENTS MADE PUBUC-DIVISION OF REGULATORY APPUCATIONS (POST 941217)
LY AVAILABLE. November 1-30, 1995.
NUREG4713 V18: OCCUPATONAL RADIATION EXPOSURE AT NUREG-0540 V17 N12: TITLE UST OF DOCUMENTS MADE PUBLIC-COMMERICAL NUCLEAR POWER REACTORS AND OTHER LY AVAILABLE. December 1 31.1995 FACluTIES.1994. Twenty-Seventh Annual Report NUREG-0750 V41: NUCLEAR REGULATORY COMMISSION ISSUANCES.Opensons And Decesions Of The Nuclear Regulatory EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 800426)
Comrmsason With Selected Orders. January-June 1995.
OFFICE OF NCLEAR REACTOR REGULATION (POST 941001)
NUREG4750 V42102: INDEXES TO NUCLEAR REGULATORY COM-NUREG-0040 V19 N04: UCENSEE CONTRACTOR AND VENDOR IN-MISSION ISSUANCES. July-December 1995-SPECTON STATUS REPORT. Quarterty Report, October-December NUREG-0750 V42 N05: NUCLEAR REGULATORY COMMISSION IS-1995.(WNte Book)
SUANCES FOR NOVEMBER 1995. Pages 181219-NUREG-0390 V10 TOPICAL REPORT REVIEW STATUS (Blue Book)
NUREG-0750 V42 N06. NUCLEAR REGULATORY COMMISSON IS-NUREG-0847 S20: SAFETY EVALUATION REPORT RELATED TO NUREG V43 NO N L RE LA COMMISSION IS.
THE OPERATION OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND SUANCES FOR JANUARY 1996. P 1 11
- 2. Docket Nos. 50-390 And 50-391.(Tennesase Vasey Authortly)
NUREG-0936 V14 NO2: NRC REG TOR AGENDA. Semiannual NUREG-1537 PT01: GUIDELINES FOR PREPARING AND REVIEW.
ReportJuly-December 1995.
ING APPUCATONS FOR THE UCENSING OF NON-POWER REACTORS.Part 1: Format And Content.
EDO. OFFICE OF THE CONTROLLER (PRE 820418 & POST 890205)
NUREG-1537 PT02: GUOELINES FOR PREPARING AND REVIEW-DIVISION OF BUDGET & ANALYSIS (POST 890205)
ING APPUCATIONS FOR THE UCENSING OF NON-POWER NUREG-1100 V12: BUDGET ESTIMATES. Fiscal Year 1997-REACTORS.Part 2 Standard Review Plan And Acceptanos Crtlerla.
[
EDO OFFICE FOR ANALYSIS n EVALUATON OF OPERATIONAL RS G
O OFF OR ANALYSIS & EVALUATON OF OPERATONAL DATA, Dl-ER PONENT YSIS OF THE IMPACTS OF ECONOMIC NUREG-0090 Vf B NO2 REPORT TO CONGRESS ON ABNORMAL INCENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER OCCURRENCES. April-June 1995.
PLANT OPERATIONS AND MAINTENANCE COSTS.
23
E
NRC Orig!nating Organization Index (International Agreements)
This index lists those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where appropriate. Each 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.
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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 alphabeticall and then by subsections of these (e.g., y by major NRC organization (e.g., program off 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 ANALYS48 & EVALUATION OF OPERATIONAL DIVISION OF REGULATORY APPLICATIONS (POST 941217)
DATA NUREG/CR4096:
APACHE LEAP TUFF INTRAVAL DIVISION OF SAFETY PROGRAMS (POST 870413) CTS ON CERTAIN EXPERIMENTS.Results And Lessons Learned.
NUREG/CR4442: EVIDENCE OF AGING EFFE NUREG/CR4124: CHARACTERIZATION OF RADIONUCUDE-CHE-SAFETY-RELATED COMPONENTS.
LATING AG' INT COMPLEXES FOUND IN LOW-LEVEL RADIOAC-EDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS TlVE DECONTAMINATION WASTE. Utarature Review.
DIVISION OF INDUSTRIAL & MEDICAL NUCLEAR SAFETY (POST NUREG/CR4230 RADIOANALYTCAL TECHNOLOGY FOR 10 CFR 870729)
PART 61 AND OTHER SELECTED RADIONUCLIDES.uterature NUREG/CR4407: CLASSIFICATION OF TR/WSPORTATION PACK.
Review.
AGING AND DRY SPENT FUEL STORAGE SYSTEM COMPO.
NUREG/CR4280: TECHNOLOGY, SAFETY,AND COSTS OF DECCC NENTS ACCORDING TO IMPORTANCE TO SAFETY.
MISSIONING A REFERENCE LARGE IRRADIATOR AND REFER-ENCE SEALED SOURCES.
EDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)
NUREG/CR4346: HYDROLOGC EVALUATION METHODOLOGY DIVISION OF ENGINEERING TECHNOLOGY (POST 94 ~717)
FOR ESTIMATING WATER MOVEMENT THROUGH THE UNSATU-NUREG/CR 4667 V20: ENVIRONMENTALLY ASSISThD CRACKING RATED ZONE AT COMMERCIAL LOW LEVEL RADIOACTIVE IN LIGHT WATER REACTORS. Serruannual Report, October 1994 -
WASTE DISPOSAL SITES.
NUR /
753: AGING OF SAFETY CLASS 1E TRANSFORMERS NUREG/CR4353: COMMENTS RECEIVED ON PROPOSED RULE ON IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
RADIOLOGCAL CRITERIA FOR DECOMMISSIONING AND RELAT.
NUREG/CR 5985 S01: REVIEW OF P-SCAN COMPUTER-BASED UL-ED DOCUMENTS.
TRASONIC INSERVICE INSPECTION SYSTEM.
NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS NUREG/CR4246: EFFECTS OF AGING AND SERVCE WEAR ON EQUATION SOLVER.
MAIN STEAM ISOLATION VALVE 3 AND VALVE OPERATORS.
NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS BREATHING-ZONE AND AREA AIR SAMPLES.
SCAUNG MODELS TO THE DUCTILE-TO-BRITTLE TRANSITION.
DWiSION OF SYSTEMS TECHNOLOGY (POST 941217)
NUREG/CR4336: AGING ASSESSMENT OF LARGE ELECTRIC NUREG/CR4338: RESOLUTION OF THE DIRECT CONTAINMENT MOTORS IN NUCLEAR POWER PLANTS.
HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH NUREG/CR4337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 LARGE DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAIN-ROUND. ROBIN ANALYSES.
MENTT NUREG/CR4339: AGING ASSESSMENT OF 'VESTINGHOUSE PWR NUREG/CR4422: POWER EXCURSION ANALYSIS FOR HIGH AND GENERAL ELECTRIC BWR CONTAINMENT ISOLATION BURNUP CORES.
FUNCTIONS.
NUF EG/CR4340: AGING A6SESSMENT OF SURGE PROTECTIVE DEVICES IN NUCLEAR POWER PLANTS.
EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)
NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL-OFFICE OF NUCLEAR REACTOR REGULATION (POST 941001)
NUREG/CR 2850 V14: DOSE COMMITMENTS DUE TO RADIOAC-NLRE CR 15-L T NS OF REUABluTY DEGRADATION TlVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.
ANALYSIS NUREG/CR4396: EXAMPLES CLARIFICATIONS. AND GUIDANCE i
NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY ON PREPARING REQUESTS FOR REUEF FR(*8 OUMP AND FOR AUTOMATING ECCS SwiTCHOVER AT PWRS.
VALVE INSERVICE TESTING REQUIREMENTS.
NUREG/CR4438: THE EFFECT OF CYCLC AND DYNAMIC LOADS NUREG/CR4421: A PROPOSED ACCEPTANCE PROCESS FOR ON CARBON STEEL PIPE.
COMMERCIAL OFF THE-SHELF (COTS) SOFTWARE IN REACTOR NUREG/CR4439: DESIGN OF THE IPIRG-2 SIMULATED SEISMC APPUCATIONS.
]
FORCING FUNCTION.
NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.
NUREG/CR4448 V01: EVALUATION OF NATIONAL SEISMOGRAPH NUREG/CR4435. AN ANALYSIS OF THE IMPACTS OF ECONOMC NETWORK DETECTION CAFABILITIES. Annual Report. July 1994.
INCENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER July 1995.
PLANT OPERATIONS AND MAINTEtwrLE COSTS.
27
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Contractor Index This index lists, in alphabetical order, the contractors that prepared tha NUREG/CR reports listed in this compilation. Listed below each contractor are the NUREG/CR numbers and titles of their reports. If further iniormation is needed, refer to the rnain citation by the NUREG/CR number.
ADVANCED SYSTEMS TECHNOLOGY, INC.
NUREG/CR4422. POWER EXCURSION ANALYSIS FOR HIGH NUREG/CR4353. COMMENTS RECEIVED ON PROPOSED RULE ON BURNUP CORES.
RADIOLOGICAL CRITERIA FOR DECOMMISSIONING AND RELATED DOCUMENTS.
FLORIDA, UNIV. OF, GAINESVILLE, FL NUREG/CR4340: AGING ASSESSMENT OF SURGE PROTECTIVE DE.
ARGONNE NATIONAL LABORATORY VICES IN NUCLEAR POWER PLANTS' NUREG/CR-4667 V20: ENVIRONMENTALLY ASSISTED CRACKING IN UGHT WATER REACTORS. Sermannual Report. October 1994 March GEORGIA, UNIV. OF, ATHENS, GA NUREG/CR4096:
APACHE LEAP TUFF INTRAVAL ARIZONA, UNIV. OF, TUCSON, AZ EXPERIMENTS.Results And Lessons Learned.
NUREG/CR4096:
APACHE LEAP TUFF INTRAVAL EXPERIMENTS.Results And Lessons barner IDAHO NATIONAL ENGINEERING LABORATORY NUREG/CR-5753: AGING OF SAFETY CLASS 1E TRANSFORMERS IN BATTELLE MEMORIAL INSTITUTE, COLUMSUS LABORATORIES SAFETY SYSTEMS OF NUCLEAR POWER PLANTS.
NUREG/CR4337:
SUMMARY
OF RESULTS FROM THE IPIRG-2 NUREG/CR4396: EXAMPLES. CLARIFICATIONS. AND GUIDANCE ON VfCE TEST NG RE NUR G/
- H FFECT OF CYCLIC AND DYNAMC LOADS ON
' REM T NU G CR IGN OF THE IPIRG-2 SIMULATED SEISMIC NUREG/CR4407: CLASSIFICATION OF TRANSPORTATION PACKAG-FORCING FUNCTION' ING AND DRY SPENT FUE! STORAGE SYSTEM COMPONENTS AC-CORDING TO IMPORTANCE TO SAFETY.
BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWEST NUREG/CR4442: EVIDENCE OF AGING EFFECTS ON CERTAIN LABORATORY SAFETY RELATED COMPONENTS.
NUREG/CR-2850 V14: DOSE COMMITMENTS DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1992.
LAWRENCE LIVERMORE NATIONAL LABORATORY NUREG/CR 5985 S01: REVIEW OF P-SCAN COMPUTER BASED UL-NUREG/CR-6421: A PROPOSED ACCEPTANCE PROCESS FOR COM-TRASONIC INSERVCE INSPECTION SYSTEM.
MERCIAL OFF-THE-SHELF (COTS) SOFTWARE IN REACTOR APPLI-NUREG/CR4124: CHARACTERIZATION OF RADIONUCLlDE CHELAT*
CATIONS.
ING AGENT COMPLEXES FOUND IN LOW-LEVEL RADIOACTIVE DE-NUREG/CR4430: SOFTWARE SAFETY HAZARD ANALYSIS.
CONTAMINATION WASTE Uterature Review.
NUREG/CR4230: RADIOANALYTICAL TECHNOLOGY FOR 10 CFR NAVY DEPT,OF PA 61 AND OTHER SELECTED RADIONUCUDES Literature NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL-NUREG/CR4280 TECHNOLOGY, SAFETY,AND COSTS OF DECOM.
ING MODELS TO THE DUCTILE TO-BRITTLE TRANSITION, MISSIONING A REFERENCE LARGE 1RRADIATOR AND REFER.
ENCE SEALED SOURCES.
NEW MEXICO STATE UNIV., LAS CRUCES, NM NUREG/CR4346: HYDROLOGC EVALUATION METHOOOLOGY FOR NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA-ESTIMATING WATER MOVEMENT THRCidGH THE UNSATURATED TlON SOLVER.
ZONE AT COMMERCIAL LOW-LEVEL RADIOACTIVE WASTE DIS-POSAL SITES.
OAK RIDGE NATIONAL LABORATORY NUREG/CR4366: POLYRES: A POLYGON-BASED RICHARDS EQUA-NUREG 1531: DRAFT ENVIRONMENTAL IMPACT STATEMENT RELAT.
TION SOLVER.
ED TO RECLAMATION OF THE URANIUM MILL TAluNGS AT THE NUREG/CR4435: AN ANALYSIS OF THE IMPACTS OF ECONOMIC IN-ATLAS SITE.MOAB. UTAH. Source Matenal Ucense No. SUA-CENTIVE PROGRAMS ON COMMERCIAL NUCLEAR POWER PLANT 017. Docket No. 40 3453. (Atlas Corporation)
OPERATIONS AND MAINTENANCE COSTS.
NUREG/CR-6246. EFFECTS OF AGING AND SERVICE WEAR ON BROOKHAVEN NATIONAL LA90RATORY MAIN STEAM ISOLATION VALVES AND VALVE OPERATORS.
NUREG/CP-0149 V01: PROCEEDINGS OF THE TWENTY THIRD WATER REACTOR SAFETY INFORMATION MEETING Plenary Ses, RADIATION SAFETY ENGINEERING,1NC.
l soon, High Burnup Fuel Behavior, T: anal Hydrevlic Research.
NUREG/CR4419: SOLUBILITY TESTING OF ACTINIDES ON BREATH.
NUREG/CP-0149 V02: PROCEEDINGS OF THE TWENTY-THIRD ING-ZONE AND AREA AIR SAMPLES t
WATER REACTOR SAFETY INFORMATION MEETING Human Factors Research, Advanced l&C Hardware & Software. Severe Accsdent Re-54USED search, Probotniestic Risk Assessrnent Topics, indnndual Plant Exarmna-NUREG/CR 8448 V01: EVALUATION OF NATIONAL SEISMOGRAPH tion.
NETWORK DETECTION CAPABILITIES. Annual Report. July 1994 July NUREG/CP 0149 V03: PROCEEDINGS OF THE TWENTY THIRD 1995 WATER REACTOR SAFETY lh9CFMATION MEETING. Structural &
Soestmc Engineenn0, Pnrnary Syttens integnty. Equiprnent Operatxlity SANDIA NATIONAL LABORATORIES Am$ Ageng. ECCS Strainer Blockage Hesearch & R atory lasues NUREG/CR4338. RESOLUTION OF THE DIRECT CONTAINMENT NUREG/CR4336: AGING ASSESSMENT OF GE ELECTRC HEATING ISSUE FOR ALL WESTINGHOUSE PLANTS WITH LARGE DRY CONTAINMENTS OR SUBATMOSPHERIC CONTAINMENTS.
NU G CR 9 AG NG AS SS OF WESTINGHOUSE PWR GCNERAL ELECTRC BWR CONTAINMENT ISOLATION FUNC-SCIENCE & ENGINEERING ASSOCIATES,INC, ICU9EG/CR4340 AGING ASSESSMENT OF SURGE PROTECTIVE DE.
NUREG/CR4367: EXPERIMENTAL STUDY OF HEAD LOSS AND FIL.
VCES IN NUCLEAR POWER PLANTS.
TRATION FOR LOCA DEBRIS.
NUMEG/CR4415: APPLICATIONS OF RELIABILITY DEGRADATION NUREG/CR4432: ESTIMATED NET VALUE AND UNCERTAINTY FOR ANALYSIS.
AUTOMATING ECCS SWITCHOVER AT PWHS.
2TP
l l
l 30 Contractor Index l
l l
SCIENC' APPUCATIONS INTERNATIONAL CORP. (FORMERLY NUREG/CR4415: APPLICATIONS OF RELIABILITY DEGRADATION l
Scat.MCE APPUCATIONS, ANALYSIS.
NUREG 0713 Vie: OCCUPATIONAL RADMTION EXPOSURE Al COM-U.S. NAVAL ACADEMY. ANNAPOLIS MD MERICAL NUCLEAR POWER REACTORS AND OTHER NUREG/CR4279: APPLICATION OF FRACTURE TOUGHNESS SCAL.
FACILITIES.1904. Twenty-Seventh Amuel Report ING MODELS TO THE DUCTILE-TO-BRITTLE TRANSITION.
l l
l l
l l
l l
l
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-form ng 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 e no NUREG/lA reports published during this quarter I
\\
31
I
Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The ficility names are arranged in alphabetical order. They are preceded by their Docket number cnd followed by'the report number. If further information is needed, refer to the main citation by the NUREG number.
]
l 20 2R2:8:
S!!E
- ",'g%
r h % W 2, Tm NUREGN7 S20 50 300 Wens Bar Nudeer Plant, UnN 1, Tennesese NUREGM7 S20 vesey Atwny i
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33 I
I
NRC FORM 335 U.S. m^Jt REGULATORY COMMISSION
- 1. REPORT NUMBER (1 89)
(Assigned by NRC, AdG Vol.,
NRCM 1102, Supp., Rev., and Addendum Nurn-szoi,3202 BIBLIOGRAPHIC DATA SHEET b* - " *aY- )
(see hatructions on the revers.)
- 2. TITLE AND SUBTITLE Vol. 21, No.1
- 3. DATE REPORT PUBLISHED Regulatory and Technical Reports (Abstract Index Journal)
Compilation for First Quarter 1996 June 1996 January-March
- 6. AUTHOR (5)
- 6. TYPE OF REPORT Reference
- 7. PERIOD COVERED (inclusive Dates)
January-March 1996
- 8. PERFORMING ORGANtZATION - NAME AND ADDRESS (if NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and malling aJdress; if contractor, provide name and malling address.)
Division of Freedom of Information and Publications Services Officeof Administration U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 9. SPONSORING ORGANIZATION - NAME AND ADDRESS (if NRC, type 'Sarne as above; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, and malling address.)
Same as 8, above.
- 10. SL.U'PLEMENTARY 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. KEV WORDS/DESCRPTORS (List words or phrases that will assist researchers M locating the report.)
- 13. AVALABUTY STATEMENT Unlimited
- 14. SECURITY CLASSFICATION abstract inder Unclassified (Tha Report)
Unclassified
- 15. NUMULH OF PAGES
- 16. PRICL NRC FORM 336 (2-89)
1 J
l Printed on recycled paper Federal Recycling Program
~
c NUREG-0304,%I.21 No.1 REGUIATORY ANDMREPORTS COMPIIATION FOR FIRST QUARTER 1996 JUNE 1996 0
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 POS AGE ND FE AfD USNRC PERMIT NO. G-67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. $300 y
{
IANIACIA51cy2 fhfy'."[f'NUCE ELICATIO4s SVCS WASHINGTON DC 2c555 I
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