ML20045A557
| ML20045A557 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1993 |
| From: | NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | |
| References | |
| NUREG-0304, NUREG-0304-V18-N01, NUREG-304, NUREG-304-V18-N1, NUDOCS 9306110059 | |
| Download: ML20045A557 (48) | |
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Vol.18, No.1
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l Regulatory and Technical Reports
) <' Abstract Inc ex Journal)l
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l Compilation for 4
First Quarter 1993 January - March 3
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1 Available from Superintendent of Documents U.S. Govemment Printing Office Post Office Box 37082 Washington, D.C. 20013-7082 i
l A year's subscription consists of 4 issues for this publication.
Single copies of this publication are available from National Technical information Service, Springfield, VA 22161 i
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NUREG-0304 Vol.18, No.1 J
'l Regulatory and Technical Reports (Abstract Index Journal) i i
Compilation for First Quarter 1993 January - March Date Published: May 1993 i
Regulatory Publications Branch Division of Freedom ofInformation and Publications Services Ollice of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555
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l CONTENTS Preface
. v Index Tab Main Citations and Abstracts 1
Staff Reports e
Conference Proceedings e
Contractor Reports e
j international Agreement Reports e
l Secondary Report Number Index 2
Perscnal ALcor index 3
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Subject index 4
NRC Originating Organization index (Staff Reports) 5 i
NRC Originating Organization Index (international Agreements).
6 NRC Contract Sponsor Index (Contractor Reports) 7 Contractor Index.
8 Intemational Organization Index 9
Licensed Facility index 10 I
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i PREFACE This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. Your comments will be appreciated. Please send them to:
Technical Publications Section l
Regulatory Publications Branch Division of Freedom of Information and Publications Services P-223 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 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 Author Index Subject Index i
NRC Originating Organization index (Staff Reports)
NRC Originating Organization Index (Intemational 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 bibliographic 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 author, (4) organizational unit of author, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Controf System accession number, (8) the microfiche address (for intemal NRC use).
Conference Report NUREG/CP-0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT AND RELIABILITY ENGINEERING IN NUCLEAR REGULATION. JANERP,J.S. Argonne National Laboratory. May 1981.141 pp.
8105280299. ANL-81-3. 08632:070.
Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiled the proceedings, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization, (9) the microfiche address (for NRC intemal use).
Contractor Report NUREG/CR-1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATER REAC-l l
TORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.; BENNETT, P.R. Sandia Laboratories.
May 1981.100 pp. 8107010449. SAND 80-0929. 08912:242.
Where the entries are (1) report number, (2) report title, (3) report authors, (4) organizational unit of authors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRC Document Control System accession number, (8) the report number of the originating organization (if given), (9) the microfiche address (for NRC internal use).
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International Agreement Report s
v NUREG/lA-0001: ASSESSMENT OF TRAC-PD2 USING SUPER CANNON AND HDR EXPERIMENTAL DATA. NEUMANN, U. Kraftwerk 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 r
Avabbility of NRC Publications Copies of NRC staff and contractor reports may be purchased either from the Government 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 l
Washington, DC 20013-7082 You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA charge l
l card by calling the GPO on (202)275-2060 or (202)275-2171. Non-U.S. customers must make payrnent in
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advance either by international Postal Money Order, payable to the Superintendent of Documents, or by draft on a United States or Canadian bar'k, payable to the Superintendent of Documents.
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t NRC Report Codes The NUREG designation, NUREG-XXXX, indicates that the document is a formal NRC staff-generated report. Contractor-prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type of identification replaces contractor-established codes such as ORNL/NUREG/TM-XXX and TREE-NUREG-X.XXX, as well as various other numbers that could not be correlated with NRC sponsorship of the work being reported.
i In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC-sponsored conference proceedings and NUREG/lA is used for international agreement reports.
All these report codes are controlled and assigned by the staff of the Publishing and Translations Section of the NRC Division of Publications Services.
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1 Main Citations and Abstracts i
The report listings in this compilation are arranged by report number, where NUREG-XXXX is an NRC staff-originated report, NUREG/CP-XXXX is an NRC-sponsored conference report, NUREG/CR-XXXX is an NRC contractor-prepared report, and NUREG/lA-XXXX is an inter-national agreement report. The bibliographic information (see Preface for details) is followed by a brief abstract of this report.
NUREG-0020 V17: LICENSED OPERATING REACTORS STATUS This 5th revision of the sixth edition of the NRC Practice and
SUMMARY
REPORT Data As Of December 31, 19921 Gray Procedure Digest contains a digest of a number of Commission, Book l) HARTFIELD,R.A. D+ vision of Computer & Telecommuni-Atomic Eately and Licensing Appeal Board, and Atomic Safety cations Services (Post 890205). March 1993. 335pp and Licensing Board decisions issued dunng the period of July 9304080036. 74493.001.
1,1972 to March 31, 1992, interpreting the NRC's Rules of The Nuclear Regulatory Commission's annual summary of h-Practice in 10 CFR Part 2.
censed nuclear power reactor data is based pnmanly on the report of operating data submitted by hcensees ivi ccch unit for NUREG-0540 V14 N11: TITLE LtST OF DOCUMENTS MADE I
the month of December because that report contains data for PUBLICLY AVAILABLE. November 1-30, 1992.
- Division of the month of December, the year to date (in this case calendar Freedom of lnformation & Pubhcations Services (Post 890205).
year 1992) and cumulative data usually from the date of com.
January 1993. 333pp. 9302230138. 64980901 mercial operation. The data is not independently venhed, but This document is a monthly publication containing descnp-vanous computer checks are made. The report is d'vided into tions of information received and generated by the U.S. Nuclear two sections The first contains summary highlights and the Regulatory Commission (NRC). This information includes (1) second contains data on each individual unit in commercial op.
docketed matenal associated with civilian nuclear power plants eration Section 1 capacity and availabihty factors are simple and other uses of radioactive materials, and (2) nondocketed anthmetic averages. Section 2 items in the cumulative column material received and generated by NRC pertinent to its role as are generaHy as reported by the hcensee and notes as to the a regulatory agency. The following indexes are included. Per-use of weighted averages and starting dates other than com.
sonal Author, Corporate Source, Report Number, and Cross mercial operation are provided.
Reference of Enclosures to Pnncipal Documents.
NUREG-0040 V16 N04: LICENSEE CONTRACTOR AND NUREG-0540 V14 N12: TITLE LIST OF DOCUMENTS MADE VENDOR INSPECTION STATUS REPORT.
Qua-terly PUBLICLY AVAILABLE. December 1-31, 1992.
- Division of Repo.1,0ctober-December 1992.(White Book)
- Division of Re.
Freedom of information & Pubhcations Services (Post 890205).
j actor inspection & Licensee Periormance (Post 921004) Janu.
February 1993 343pp. 9303110330. 74213 085.
ary 1993.198pp. 9302230396. 64961:001.
See NUREG-0540,V14.N11 abstract.
This periodical covers the results of inspections performed by NUREG-0540 V15 N01: TITLE LtST OF DOCUMENTS MADE the NRC s Vendor inspection Branch that have been distobuted PUBL.lCLY AVAILABLE. January 1-31.1993.
- Division of Free-P" dom of information & Pubhcations Services (Post 890205).
r ugh De e ber 1 9 '
March 1993. 320pp. 9304020324. 74448:001.
NUREG-0304 V17 N04: REGULATORY AND TECHNICAL RE.
See NUREG-0540,V14,N11 abstract.
PORTS (ABSTRACT INDEX JOURNAL). Annual Compilation NUREG-0713 V12: OCCUPATIONAL RADIATION EXPOSURE AT For 1992, Divtsion of Freedom of information & Pubhcations COMMERCIAL NUCLEAR POWER REACTORS AND OTHER Serv es Post 890205) February 1993.130pp. 9303240099 FACILITIES,1990. Twenty-Third Annual Report. RADDATZ,C.T.
Division of Regulatory Applications (Post 870413).
This journal includes all formal reports in the NUREG senes HAGEMEYER,D Science Applications International Corp. (for-prepared by the NRC staff and contractors, proceedings of con-merly Science Apphcations, Inc ).
January 1993. 294pp.
ferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access This report summanzes the occupational radiation exposure by title and abstract, secondary report number, personal author, information that has been reported to the NRC s Radiation Ex-subject, NRC organization for staff and intemational agree-posure information Reporting System (REIRF) by nuclear power ments, contractor, international organization, and hcensed facili-facihties and certain other categones of NRC hcensees during ty' the years 1969 through 1990. The bulk of the data presented in NUREG-0325 R16: U.S. NUCLEAR REGULATORi COMMISSION the report was obtained from annual radiation exposure reports FUNCTIONAL ORGANIZATION CHARTS. March 15, 1993.
- submitted in accordance with the requirements of 10 CFR Ofc of Personnel (Post 870413). March 1993. 66pp.
20.407 and the technical specifications of nuclear power plants.
9304060302. 74467:001.
Data on workers terminating their employment at certain NRC Functional organization charts for the U.S. Nuclear Regulatory hcensed facihties were obtained from reports submitted pursu-Commission offices divisions, and branches are presented.
ant to 10 CFR 20.408. The 1990 annual reports submitted by about 443 heensees indicated that approximately 214,568 inde NUREG-0386 D06 R05: UNITED STATES NUCLEAR REGULA-viduals were monitored. 110.204 of whom were monitored by TORY COMMISSION STAFF PRACTICE AND PROCEDURE nuclear power facihties. They incurred an average individual DIGEST. Commission, Appeal Board And Licensing Board dose of 0.19 rem (cSv) and an average measurable dose of Decisions. July 1972 - March 1992.
- Office of the General about 0.36 (cSv). Termination radiation exposure reports were Counsel (Post 860701) February 1993. 602pp. 9303110316.
analy7ed to reveal that about 113,361 individuals completed 74215 001.
their employment with one or more of the 443 covered bcens-1
2 Main Citations and Abstracts ees dunng 1990 Some 77.633 of these individuals terminated of NRC licensed facilities throughout the country for the fourth from power reactor facilities, and about 11,083 of them were quarter 1992.
Considered to be transient workers who received an average dose of 0.67 rem (cSv).
NUREG-0936 V11 N04: NRC REGULATORY AGENDAQuarterly NUREG-0750 V36 N01: NUCLEAR REGULATORY COMMISSION mation & Publica' ions Services (Post 890205). February 1993.
ISSUANCES FOR JULY 1992.Pages 1-45
- Division of Free-147pp. 9303110325, 74212.297.
dom of information & Publ cations Services (Post 890205). Jan-The NRC Regulatory Agenda is a compilation of all rules on uary 1993. 45pp. 9302230178. 64977;308' Atomic Safety and L.
which the NRC has recently completed action, or has proposed Legal issuances of the Commission, the i-action, or is considenng action, and all petitions for rulemaking censing Board Panel, the Administrative Law Judges, and NRC Program Offica are presented.
disposition by the Commission. The Regulatory Agenda is up-NUREG-0750 V36 NO2: NUCLEAR REGULATORY COMMISSION dated and issued each quarter.
ISSUANCES FOR AUGUST 1992. Pages 47148
- Drvision of Freedom of Information & Publications Services (Post 890205),
NUREG-0940 V11 N04: ENFORCEMENT ACTIONS: SIGNIFi-February 1993.110pp. 9302230128. 64978:220.
CANT ACTIONS RESOLVED Quarterly Progress See NUREG-0750,V36.N01 abstract.
Report October-December 1992.
- Ofc of Enforcement (Post 870413). March 1993. 300pp. 9303300180. 74407:001, NUREG-0750 V36 NO3: NUCLEAR REGULATORY COMMISSION This compilation summanzes significant enforcement actions ISSUANCES FOR SEPTEMBER 1992. Pages 149 220.
- Divi, that have been resolved dunng one quarterly period (October -
sion of Freedom of Information & Pubhcations Services (Post December 1992) and includes copies of letters, Notices, and 890205). February 1993. 77pp. 9303090074. 74138.142.
Orders sent by the Nuclear Regulatory Commission to licensees See NUREG-0750.V36,N01 abstract.
with respect to these enforcement actions. It is anticipated that NUREG 0750 V36 N04: NUCLEAH HEGULATORY COMMISSION the information in this publication will be widely disseminated to ISSUANCES FOR OCTOBER 1992. Pages 221-249.
- Division managers and employees engaged in activities licensed by the of Freedom of information & Publications Services (Post NRC, so that actions can be taken to improve safety by avoid-890205). February 1993. 34pp. 9303120069. 74214:298-ing future violations similar to those described in this publica-See NUREG-0750,V36.N01 abstract.
tion.
NUREG-0750 V36 N05: NUCLEAR REGULATORY COMMtSSION NUREG-1021 R07: OPERATOR LICENSING EXAMINER STAND-ISSUANCES FOR NOVEMBER 1992. Pages 251-350.
- Division ARDS.
- Division of Reactor Controls & Human Factors (Post of Freedom of information & Publications Services (Post 921004). Janua'Y 1993. 352pp. 9302230189. 64962:001.
890205). March 1993.107pp. 9303300160. 74408:001.
See NUREG-0750,V36,N01 abstract.
The Operator Licensing Examiner Standards provide pohey and guidance to NRC examiners and establish the procedures NUREG-0750 V36 N06: NUCLEAR REGULATORY COMMISSION and practices for examining licensees and applicants for reactor ISSUANCES FOR DECEMBER 1992. Pages 351-396.
- Division operator and senior reactor operator licenses at power reactor of Freedom of In%rmatton & Publications Services (Post facihtees pursuant to Part 55 of Title 10 of the Code of Federal 890205). March 1993. 53pp. 9304060309. 74467:069 Regulations (10 CFR 55). The Examiner Standards are intendeo See NUREG-0750.V36,N01 abstract-to assist NRC examiners and facihty heensees to better under.
NUREG-0750 V37 N01: NUCLEAR REGULATORY COMMISSION stand the initial and requahfication examination processes and ISSUANCES FOR JANUARY 1993. Pages 1-54.
- Division of to ensure the equitable and consistent administration of examF Freedom of Information & Pubications Services (Post 890205) nations to all apphcants. These standards are not a substitute March 1993. 62pp. 9304080072. 74499:001.
for the operator heensing regulations and are subject to revision See NUREG-0750,V36 N01 abstract.
or other internal operator keensing policy changes. This revision will officially become effective 90 days after its pubication is no-NUREG-0797 S26: SAFETY EVALUATION REPORT RELATED ticed in the Federal Register. The revised dynamic simulator re-TO THE OPERATION OF COMANCHE PEAK STEAM ELEC-quahfication examination procedure (ES-604) may be used im-TRIC STATION. UNIT 2. Docket No. 50-446.(Texas Utilities Elec-mediately, if requested by the facihty bcensee. The corporate tric Company.et al.)
- Division of Reactor Projects - til,lV,V (Post notification letters issued after the effective date will provide fa-901216). February 1993. 230pp. 9303110338. 74214:068-cihty licensees with at least 90 days notice that the examina-Supplement 26 to the Safety Evaluation Report related to the tions will be administered in accordance with the revised proce-operation of the Comanche Peak Steam Electne Station dures.
(CPSES), Unit 2, has been prepared by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission NUREG 1214 R11: HtSTORICAL DATA
SUMMARY
OF THE SYS-(NRC). The facibty is located in Somervell County, Texas, ap-TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE.
proximately 40 miles southwest of Fort Worth, Texas. This sup-ALLENSPACH,F. Division of Reactor inspection & Licensee plement reports the status of certain issues that had not been Performance (Post 921004). February 1993.
132pp.
resolved when the Safety Evaluation Report and Supplements 9303250054. 74363:155.
1, 2, 3, 4, 6,12, 21, 22, 23, 24 and 25 to that report were pub.
The Histoncal Data Summary of the Systematic Assessment hshed. This supplement deals pnmarily with Unit 2 issues; how-of Licensee Performance (SALP) is produced penodically by the ever, it also references evaluations for several licensing issues U.S. Nuclear Regulatory Commission. This summary provides that relate to Unit 1, which have been resolved since Supple-the results of the assessment for each facility by NRC region ment 25 was issued.
and is further divided into the following sections: Section i pre-NUREG-0837 V12 N04: NRC TLD DIRECT RADIATION MON 1-sents the most recent SALP report ratings for facihties in oper-TORING NETWORK. Progress Report. October-December 1992.
ation and under construction; Section 2 presents a chronologi.
STRUCKMEYER.R.; MCNAMARA,N. Region 1 (Post 820201).
cal hsting of all SALP report ratings for each operating facihty; March 1993. 326pp. 9304060314. 74466 001, Section 3 presents a chronological hsting of all SALP report rat-This report provides the status and results of the NRC Ther-ings for each facihty under construction. For histoncal purposes, moluminescent Dosimeter (TLD) Direct Radiation Monitonng past construction ratings for facihties that recently have been h-Network. It presents the radiation levels measured in the vicinity censed also are listed in Section 3.
Main Citations and Abstracts 3
NUREG-1220 R01: TRAINING REVIEW CRITERIA AND PROCE-Regulatory Commisson's (NRC's) Electrical Distnbution System DURES.
- Division of Licensee Performance & Quahty Evalua.
Functional Inspections (EDSFis) The program enables the user tion (870411 921003) January 1993. 104pp. 9303150141.
to search and sort findings, ascertain trends, and obtain pnnted 74242:188.
reports of the findings The findings include observations, unre-This document provides direction to NRC personnel for re-solved issues, or possible deficiencies in the design and imple-viewing training programs at nuclear power plants to verify com-mentation of electncal distobution systems in nuclear plants pliance with the requirements of 10 CFR 50.120 and 10 CFR 55 This database will assist those prepanng for electncal inspec-as applicable. It desenbes the process for evaluating the eff9C-tions, searching for deficiencies in a plant, and determining the teveness of training programs, provides aids for collecten of in-corrective actions previously taken for similar deficiencies This formation dunng interviews and observations, and provides en-database will be updated as new EDSFis are completed
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tena for evaluating the implementation of a systems approach to training This document is not intended to have the effect of NUREG 1476: DRAFT ENVIRONMENTAL IMPACT STATEMENT a regulation, it establishes no binding requirements or interpre-TO CONSTRUCT AND OPERATE A FACILITY.TO RECEIVE, tations of NRC regulations 11 is intended as guidance only.
STORE, AND DISPOSE OF 11E (2) BYPRODUCT MATERIAL NUREG-127S V09: OPERATING EXPERIENCE FEEDBACK NEAR CLIVE, UTAH. Docket No. 40-8989. Envirocare 01 Utah, REPORT - PRESSURE LOCKING AND THERMAL BINDING OF Inc. BRUMMETT.E.: ABU EID,R.; MULUNS.A; et al Division of GATE VALVES. Commercial Power Reactors. HSU.C. Division of Low-Level Waste Management & Decommissioning (Post Safety Programs (Post 870413) March 1993. 30pp.
870413). February 1993. 224pp. 9303120020 74238'001.
9304020327. AEOD/S92-07. 74435:275.
A Draft Environmental Statement (DEIS) related to the licens.
The potential for vane inoperability caused by pressure lock-ing of Envirocare of Utah, Inc.'s proposed disposal facility in ing and thermal binding has been known for many years in the Tooele County, Utah, (Docket No. 40-8989) for byproduct mate-nuclear enoustry. In spite of numerous generic communications nal as defined in Section 11e(2) of the Atomic Energy Act, as issued in the past by the Nuclear Regulatory Commission (NRC) amended, has bson prepared by the Office of Nuclear Matenal and industry, pressure locking and thermal binding continues to Safety and Safeguards This statement desenbes and evaluates occur to gate valves installed in safety-related systems of both (1) the purpose of and need for the proposed acton, (2) the al-boiling water reactors (BWRs) and pressunzed wotor reactors ternatives considered, i.nd (3) the environmental consequences (PWRs). The genenc communications to date have not led to of the proposed action. The NRC has concluded that the pro-effective industry action to fully identify, evaluate, and correct Posed acton evaluated under the Nat onal Environmental Pol.cy the problem. This report identifies: (1) conditons when the fail-ure mechanisms have occurred. (2) the spectrum of safety sys-Act of 1969 (NEPA) and 10 CFR Part 51, is to permit the apple, terr.s that have been subjected to the failure mechanisms; and cant to proceed with the project as described in this Statement (3) conditons that may introduce the failure mechanisms under NUREG-1480: LOSS OF AN IRIDIUM-192 SOURCE AND THER-both normal and accident conditions. On the basis of the eval-APY MISADMINISTRATION AT INDIANA REGIONAL CANCER uation of the operating events, the Office for Analysis and Eval-uation of Operational Data (AEOD) of the NRC concludes that CENTER. INDIANA. PENNSYLVANIA,0N NOVEMBER 16, 1992.
the binding problems with gate valves are an important safety
- NRC - No Detailed Affiliation Given. February 1993. 223pp.
issue that needs pnority NRC and industry attention. This report 9303120040. 74263.047.
also provides AEOD's recommendation for actions to effectively On December 1,1992, the Indiana Regional Cancer Center prevent the occurrence of va!ve binding failures.
reported to the U S. Nuclear Regulatory Commission's (NRC)
Region f that they believed a 1.37 E + 11 becquerel (3.7-cune)
NUREG-1366: IMPROVEMENTS TO TECHNICAL SPECIFICA.
indium-192 source from their Omnitron 2000 high dose rate TIONS SURVEIL. LANCE REOUlPEMENTS LOBEL R,
rem te brachytherapy afterloader had been found at a bioha-TJADER,T.R. Division of Operational Events Assessment (870411-921003). December 1992. 93pp.
9301220193.
zard waste transfer station in Carnegie, Pennsylvania. After notr 64652.313.
fying the NRC. this cancer center, one of several operated by in August 1983 an NRC task group was formed to investigate the hcensee Oncology Services Corporation, retneved the problems with surveillance testing required by Technical Specifs source, and Region i dispatched an inspector and a supervisor cations. and to recommend approaches to effect improvements.
to investigate the event. The source was first detected when it NUREG-1024
(" Technical Specifications Enhancing Safety toggered radiation alarms at a waste inemerator facility in impact") resulted, and it contained recommendations to review Warren. Ohio. The licensee informed the NRC that the source the basis for test frequencies: to ensure that the tests promote wire had apparently broken dunng treatment of a patier1 on No-safety and do not degrade equipment, and to review surveil.
vember 16, 1992, leaving the source to the patient. On the lance tests so that they do not unnecessarily burden personnel, basis of the senousness of the incident, the NRC elevated its The Technical Specifications improvement Program (TSIP) was response to an incident investigation. The incident investigation established in December 1984 to provide the framework for re-Team initiated its investigation on December 3,1992. The in-wnting and improving the Technical Specifications. As an ele-vestigation team concluded that the patient received a senous ment of the TSiP, all Technical Specifications surveillance re-misadministration and died on November 21, 1992, and that quirements were comprehensively examined as recommended over 90 individuals were exposed to radiation from November in NUREG-1024. The results of that effort are presented in this 16 to December 1,1992. In a press release dated January 26, report. The study found that while some testing at power is es-1993, the, Indiana County Coroner stated that the cause of sentia!, safety can be improved, equipment degradation de-death listed in the official autopsy report was ' Acute Radiational creased. and unnecessary personnel burden relaxed by reduc-Exposure and Consequences Thereoff An almost identical ing the amount of testing at power.
source-wire failure occurred with an afterloader in Pittsburgh, NUREG-1473: ELECTRICAL DISTRIBUTION SYSTEM FUNC-Pennsylvania, on December 7,1992, but with minimal radiologi-TIONAL INSPECTION (EDSFI) DATA BASE PROGRAM.
cal consequences. This incident was included in the investiga-GAUTAM.A S. Division of Reactor inspection & Licensee Per.
tion This report discusses the Omnitron 2000 high dose rate af-formance (Post 921004). January 1993. 45pp. 9303120055.
terloader source-wire failure, the reasons why the fylure was 74237:224.
not detected by Indiana Regional Cancer Center, the potential This document desenbes the organtzation, installation proce-consequences to the patient, the estimated radiological doses dures, and operating instructions for the database computer to workers and the public, and regulatory aspects associated program containing inspection findings from the U S. Nuclear with th:s incident.
4 Main Citations and Abstracts NUREG/CP-0128: PROCEEDINGS OF THE INTERNATIONAL NUREG/CR-4551 V7 RIP 1: EVALUATION OF SEVERE ACCl-WORKSHOP ON THE CONDUCT OF INSPECTIONS AND 1N-DENT RISKS. ZION UNIT
- 1. Main Report P AR K,C.K.;
SPECTOR OUALIFICATION AND TRAINING. GRIMES.B.K.
CAZZOLI,E.; GRIMSHAW,C.; et al. Brookhaven National Labo-Office of Nuclear Reactor Regulation, Director (Post 870411).
ratory. March 1993. 200pp. 9304080019. BNL/NUREG-52029.
February 1993. 240pp. 9303160283. NEA/CNRA/R(92)3.
'74498.023.
74254:069 In support of the Nuclear Regulatory Commission's (NRC's)
The resutts of an international workshop on nuclear reactor assessment of the risk from severe accidents at commercial nu-enspection are presented Topics include types of inspection clear power plants in the U S. reported in NUREG-1150, revised programs (resident, teams, centralized), methods of inspection, calculation of the nsk to the general public from severe acci-invesbgation of incidenM/ accidents, achieving correction of defi-dents at the Zion Power Station, Unit 1 has been completed.
ciencies iwnd dunny inspections, training and qualifications of This power plant, located on the western sho e of Lake Michi-inspectors, and inspections of shutdown activities and low gan on the outskirts of Zion, is operated by the Commonwealth power operations Represented at the conference were Bel-Edison Company. The emphasis in this risk analysis was not on grum, Bulgana. Canaca, CFSM, France, Finland, Getmany, Hun.
determining a "so called" point estimate of nsk. Rather, it was gary, IAEA, The Netherlands, Norway, OECD, Russia, Spain.
. to determme the distribution of risk, and to discover the uncer.
Sweden, Switzerland, U.K., U.S, and the Ukraine.
tainties that account for the breadth of tNs distnbution. Off-site risk instration by events, both internal to the power station and NUREG/CR-2850 V11: DOSE COMMITMENTS DUE TO RADIO-external to the power station, was assessed ACTIVE RELEASES FPOM NUCLEAR POWER PLANT SITES NUREG/CR-4551V7R1P2A: EVALUATION OF SEVERE ACCl-IN 1989 BAKER,D A. Battelle Memorial Institute, Pacific North-DENT RISKS: ZION UNIT
- 1. Appendix A.
PARK,C.K.;
west Laboratory. February 1993.192pp. 9303120086, PNL-CAZZOLI,Ea GRIMSHAW,C.; et al. Brookhaven National Labo-4221. 74239 001.
ratory. March 1993. 600pp. 9304080029. BNL/NUREG.52029.
Population and indivicua! rad = ton dow commitments have 74495.00i.
been estimated from reported radionuchde releases from com-See NUREG/CR-4551,V07,R01,PT1 abstract.
mercial power reactors operating during 1989. Fifty-year dose commitments for a one-year exposure from both liquid and at-NUREG/CR-4551V7R1P28: EVALUATION OF SEVERE ACCl-mosphenc releases were calculated for four population groups DENT RISKS: ZION UNIT 1. Appendices B, C, D. And E.
6nfant, child, teen-ager and adult) residing between 2 and 80 PARK C.K.; CAZZOLI,E.; GRIMSHAW,C.; et al. Brookhaven Na-km from each of 72 reactor sites. This report tabulates the re-tional Laboratory. March 1993. 300pp. 9304080012. BNL/
sults of these calculations, showing the dose commitments for NUREG-52029. 74497:001, both water and airborne pathways for each age group and See NUREG/CR-4551,vo7,R01,PT1 abstract.
organ. Also included for each of the sites is an estimate of indi-NUREG/CR-5229 V05: FIELD LYSIMETER INVESTIGATIONS:
l vidual doses which are compared with 10 CFR Part 50, Appen.
LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM dix I desegn objectives. The total collective dose comm tments FOR FISCAL YEAR 1992. Annual Report. MCCONNELL J.W.;
(from both hquid and airbome pathways) for each site ranged ROGERS.R.D.; JASTROW,J.D.: et al. EG&G Idaho, Inc. Febru-from a high of 14 person-rem to a low of 0.005 person-rem for ary 1993. 68pp. 9303120065. EGG-2577. 74235.255.
the sites with plants in operation and producing power dunng The Field Lysimeter Investigations: Low-Level Waste Data the year. The anthmetic mean was 1.2 person-rem. The total Base Development Program, funded by the U.S. Nuclear Regu-population dose for all sites was estimated at 84 person-rem for latory Commission, is: (a) studying the degradation effects in the 140 milkon people considered at risk. The individual dose EPICOR-il organic ion-exchange resins caused by radiation; (b) commitments estimated for all sites were below the Appendix I examining the adequacy of test procedures recommended in design objectives the Branch Technical Position on Waste Form to meet the re-a quirements of 10 CFR 61 using sohdified EPICOR-Il resins; (c)
WUREG/CR-4273: CRACK PROPAGATION IN HIGH STRAIN RE.
obtaining performance information on sohdified EPICOR-ll ion-GIONS OF SEQUOYAH CONTAINMENT. GREIMANN,L FANOUS.F.; BLUHM,D lowa State Univ., Ames, lA. Marc {
ange resins in a espsal enhW aM @ Meg the condition of EPICOR-il hners. Results of the seventh year of 1993. 48pp. 9304080044.15-4878. 74494.243.
data acquisition from the field testing are presented and dis-The rate of release of radioactive materials from a contain-cussed. During the continuing field testing, both Portland type l-ment dunng a severe accident has a significant impact on the ll cement and Dow vinyl ester-styrene waste forms are being consequences of the accident One hypothesis for a contain-tested in lysimeter arrays located at Argonne National Laborato-ment leakage model states that the containment will develop a ry-East in Illinois and at Oak Ridge National Laboratory. The controlled. relatively small leak before the pressure reaches the study is designed to provide mntinuous d3t3 on nuchde release point where a general rupture of the shell occurs. Another and movement, as well as environmental conditions, over a 20-states that overall failure will occur with total release of the year period.
vessel contents almost instantaneously. The Sequoyah ice con-denser containment vessel has been studied for some time to NUREG/CR-5247 V01 R1: RASCAL VERSION 2.0 USER'S predict the possible location and extent of leakage which could GUIDE. ATHEY,G.F. Phoenix Associates, Inc. SJOREEN.A.L occur during a severe accident. In this work, three critical high Oak Ridge National Laboratory. RAMSDELL.J.V.; et al. Battelle strain locations were studied to predict crack propagation from Memonal institute, Pacific Northwest Laboratory. February 1993.
l an initially small defect. The 1/2anch plate near the Sequoyah 187pp. 9303150148. PNL-8454. 74242:001.
spnnghne was selected for further study. A detailed finite ele-The Radiological Assessment System for Consequence i
ment model of the region was prepared and a virtual crack ex-Analysis; Version 2.0 (RASCAL 2.0) has been -developed for tension method for calculating the J integral was devetooed for use by the NRC personnel who report to the site of a nuclear I
use with the general purpose finite element program. The pres-accident at the time of radiological emergencies. It supplements sure in the model was increased to 78 psi which produced a assessments based on plant conditions and quick estimates maximum membrane strain of 6.5 percent. At this point the sur-based on paper methods and provid9s rough comparisons to face crack was assumed to propagate through the plate and EPA Protective Action Guidance and thresholds for acute health leakage began. Using the virtual crack extension method, two effects. The system, which can be run on any DOS system, was through cracks with different lengths were found to be unstable developed to allow consideration of the dominant aspects of at this pressure which would allow almost instantaneous release source term, transport, dose, and consequences. The model of the vessel contents.
that was previously the whole of RASCAL has been renamed
l l
Main Citations and Abstracts 5
ST-DOSE: Two new models have been added to RASCAL 2.0.
nuclear industry CRDM maintenance experts. Nearly 23% of the The first FM-DOSE, computes doses from environmental con-NPRDS CRD system component failure reports were attnbeted centrations. The second DECAY, computes radiologic decay to the CRDM. The CRDM components most often requinng re.
and ingrowth over a selected time penod. This volume includes placement due to normal wear and aging are the Graphitar complete instructions for system use.
seals. The predominant causes of aging for these seals are me-chanical wear and thermally induced embnttlement. More than NUREG/CR-5488: RISK-BASED INSPECTION GU!DE FOR 59 f the NPRDS CRD system failure reports were attnbuted THREE MILE ISLAND NUCLEAR STATION UNIT 1.
to components that compnse the hydraulic control unit (HCU).
HARRISON.D.G; GORE.B F.; VO.T.V.; et al. Battelle Memonal The prodominant HCU components experiencing the effects of Institute, Pacific Northwest Laboratory. February 1993 132pp 1
service wear and aging are valve seals, discs, seats, stems, 9303120073. PNL-7187. 74239:193.
packing. and diaphragms.
The level one probabilistic risk assessment (PRA) for Three Mile Island Nuclear Stabon Unit 1 (TMI,1) has been analyzed to NUREG/CR-5755: STIFFNESS OF LOW. ASPECT RATIO, REIN-identify plant systems and components important to minimizing FORCED CONCRETE SHEAR WALLS. FARR AR,C.R. Los public nsk, as measured by system contnbutions to the as iual Alamos National Laboratory. BAKER.W E. New Mexico, Univ. of, probability of core damage, and to identify the pnmary failure Albuquerque, NM. January 1993. 149pp. 9302020466. LA-modes of these components. This report presents a senes of 12181-MS. 64729:054.
tables, organized by system and pnontized by nsk importance-This report summarizes the information relating to statiness of 6
which identify components associated with over 95% of the in-low-aspect-ratio, reinforced concrete shear walls that has been spectable nsk due to plant operation The systems addressed-obtained from static and dynamic tests of scale-model Seismic in descending order of importance, are: the Decay Heat Remov-Category 1 structures (exclusive of containment) and structural al, High Pressure injection, Decay Heat Cooling Water, AC elements. Although numerous static and dynamic tests of shear Power, Nuclear Services Cooling Water, Main Steam, Emergen-wall elements are reported in the technical hterature, most of cy Feedwater, Ream C :ter.t System Pressure Conid ioter.
these were ultimate strength tests. When these tests are exam-med: ate Closed Cooling Water Instrument Air, DC Power, and ined to determine stiffness values. there is a considerable range Engrneered Safeguards Actuation Systems. This ranking is in the results obtained. The types of structures and structural based on the Fussel-Vesely importance Measure of nsk impor-elements tested the test procedures, the methods used to tance, i.e., the fraction of the total annual probability of core measure stiffness (both directly and indirectly), and a summary damage which involves failures of the system of interest.
of the results are discussed. This report concludes by showing Though not involved in the prevention of core damage and thus the changes in stiffness of shear walls as a function of the peak not ranked, containment protection systems are of fundamental nominal base shear stress that the structure experiences dunng I
importance in preventing and minimizing public nsk due to a re-a seismic event lease of radionuclides, should core damage occur. Therefore, containment protection systems are included in this report, con-NUREG/CR-5766: AUXILIARY FEEDWATER SYSTEM RISK-sisting of: the Reactor Building isolation, Reactor Building BASED INSPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 Spray, and Reactor Building Emergency Cooling Systems.
NUCLEAR POWER PLANT. PUGH,R.; GORE,B.F.; VO,T.V.; et WUREG/CR-5672 V03: CHARACTERISTICS OF LOW LEVEL RA-al. Battelle Memorial Institute, Pacific Northwest Laboratory.
DIOACTIVE DECONTAMINATION WASTE. Annual Report For February 1993. 36pp 9302230239. PNL-7609 64963 001.
Fiscal Year 1992.
AKERS,D.W.;
MCCONNELL,J.W.;
in a study sponsored by the U S. Nuclear Regulatory Com.
MORCOS N EG&G Idaho, Inc. February 1993. 68pp.
mission (NRC), Pacific Northwest Laboratory has developed and 9303120059. EGG-2635, 7424 t:207.
applied a methodology for denving plant-specific nsk-based in.
This document addresses the work performed dunng fiscal spection guidance for the auxiliary feedwater (AFW) system at year 1992 at the Idaho National Engineenng Laboratory by the pressunzed water reactors that have not undergone probabilistic Low-Level Radioactrve Waste Decontamination Waste Program risk assessment (PRA). This methodology uses existing PRA re-(FIN A6359), which is funded by the U.S. Nuclear Regulatory su!!s and plant operating expenence information Existing PRA-Commission. The program evaluates the physical stability and based inspection guidance information recently developed for leachability of solidrfied waste streams generated in the decon.
the NRC for vanous plants was used to identify generic compo-nent failure modes. This information was then combined with tamination. process of pomary coolant systems in operating nu.
clear power stations. The data in this document include the plant-specific and industry wide component information and fail-chemical composition and charactenration of waste streams ure data to identify failure modes and tailure mechanisms for frorn Peach Bottom Atomic Power Station Unit 3 and from Nine the AFW system at the selected plants. San Onofro 2 was se-Mile Point Nuclear Plant Unit 1 The results of compressive lected as one of a senes of plants for study. The product of this strength testing on immersed and unimmersed solidified waste-effort is a pnontized listing of AFW f ailures which have occurred form specimens from Peach Bottom, and the results of leachate at the plant and at other PWRs. This listing is intended for use analysis are addressed Cumulative fractional release rates and by NRC inspectors in the preparation of insoection plans ad-leachability indexes of those specimens were calculated and dressing AFW risk-important components at the San Onofre-2 are included in this report.
plant.
NUREG/CR-5699 V01: AGING AND SERVICE WEAR OF CON-NUREG/CR-5783: AGING ASSESSMENT OF THE COMBUS-TROL ROD DRIVE MECHANISMS FOR BWR NUCLEAR TION ENGINEERING AND BABCOCK & WILCOX CONTROL PLANTS. GREENE,R.H. Oak Ridge National Laboratory. No-ROD DRIVES. GROVE.E.; GUNTHER.W. Brookhaven National vember 1992.149pp. 9303110370. ORNL-6666. 74212:090.
Laboratory. January 1993. 219pp. 9302230172. BNL NUREG-This Phase i Nuclear Plant Aging Research (NPAR) study ex-52299. 64978:001.
amines the aging phenomena associated with BWR control rod The effects of aging upon the Babcock & Wilcox (B&W) and dnve mechanisms (CRDMs) and assesses the ments of various Combustion Engineenng (CE) control rod drive systems have methods of " managing" this aging. Information for this study been evaluated. For this study, the CRD system boundary in-l was acquired from. (1) the resutts of a special CRDM aging ciuded the control rod assemblies, guide tubes, control rod dnve l
questionnaire distributed to each U.S. BWR utility; (2) a first-of-mechanism, control system components, rod position indication its-kind workshop held to discuss CRDM aging and mainte-components, and cooling system. Detailed operation experience nance concerns; (3) an analysis of the Nuclear Plant Reliability data for 1980 to 1990 was evaluated to identify the predominant Data System (NPRDS) failure cases attributed to the control rod failure modes, causes, and effects. The results of this evalua-dnve (CRD) system; and (4) personal information exchange with tion, along with an assessment of component material and op-
~
=
6 Main Citations and Abstracts erating environment, lead to the conclusion that both the B&W seal injection or othei ;ources continuously flows into the reac-and CE CRD systems are susceptible to age degradation. Fail-tor coolant system and dilution takes place first in the pump ures of the CRD system have resulted in signibcant plant et-suction line and then in the reactor vessel The thermal mixing fects including power reductions. plant shutdowns, scrams, and and boron dilution under these conditions were analyzed. For j
ESF actuations. Information on cunent plant system inspection the analysis of thermal mixing, water at room temperature (re-j and maintenance practices were obtainect from two B&W terred to as cold water) was fed into the cold leg of the reactor plants, and four CE plants through an industry survey. The re-system at various flow rates. For the analysis of boron dilution, j
suits of this survey indicate that some plants have modified the cold and hot unborated water was fed into the cold leg at a
]
system, replaced components and estabhshed preventive main' high flow rate The subsequent transient thermal mixing and 1
tenance programs, some of whech effectively address the aging boron dilution that would occur in the reactor system were simu-issue, while others do not. The potential apphcation of some ad' lated for 12 h depending on the flow rate. A third analysis was vanced monitonng inspection techniques are discussed' performed for the boron dilution after the start of the reactor NUREG/CR-5791: RISK EVALUATION FOR A GENERAL ELEC-coolant pump, which forces a slug of cold unborated water from TRIC BWR, EFFECTS OF FIRE PROTECTION SYSTEM AC10-the pump suction line into the reactor vessel. This transient was ATION ON SAFETY-RELATED EQUIPMENT. Evaluation Of Ge-simulated for 20 sec, by which time the slug has been pushed nenc issue 57. LAMBRIGHT,J.; ROSS,S Sandia National Lab-out of the reactor core. The rates of reactivity insertion were oratones KLAMERUS.E.; et at Science & Engineenng Associ-evaluated for these analyses.
ates, fnc. December 1992. 312pp 9301220181. SAND 911536.
64652.001.
NUREG/CR-5834: AUXILIARY FEEDWATER SYSTEM RISK.
Nuclear power plants have expenenced actuations of fire pro-BASED INSPECTION GUIDE FOR THE FORT CALHOUN NU-tection systems (FPS) under conditions for which these systems CLEAR POWER PLANT.
MOFFITT,N E,;
GORE,B.F.;
were not intended to actuate, and also have expenenced actu-VEHEC.T.A.; et al. Battelle Memorial Institute, Pacific Northwect i
ations with the presence of a fire. These actuations have often Laboratory. February 1993. 34pp. 9303120001. PNL-7906.
damaged nearby plant equipment. A review of past occurrences 74235:324.
t of both types of such events on nuclear power plant safety, and in a study sponsored by the U.S. Nuclear Regulatory Com-a cost-benefit analysis of potential corrective measures has mission (NRC), Pacific Northwest Laboratory has developed and j
been performed. Thirteen different scenanos leading to actu-applied a methodology for deriving plant-specific risk based in-ation of fire protection systems due to a vanety of causes were s ection 9uidance for the auxihary feedwater (AFW) system at adentrfied. A quantification of these thirteen scenarios, where ap-t plicable, was periormed on a BWR4/MKl. This report estimates pressurized water reactors that have not undergone probabilistic nsk assessment (PRA). This methodology uses existing PRA re-the contnbution of FPS actuations to core damage frequency, proposes physical modifications to reduce the nsk from the sults and plant operating experiance information. Existing PRA-dominant contributors, and estimates the values and impacts of based inspection guidance information recently developed for the proposed modifications.
the NRC for various plants was used to identify generic compo.
NUREG/CR-5818: UNCERTAINTY ANALYSIS OF MINIMUM anbspecific and industry-wide component information and fail-VESSEL U QUID INVENTORY DURING A SMALL-BREAK ure data to identify failure modes and failure mechanisms for LOCA IN A B&W PLANT AN APPLICATION OF THE CSAU the AFW system at the selected plants. Fort Calhoun was se-METHODOLOGY USING THE RELAPS/ MOD 3 COMPUTER lected as the sixth plant for study. The product of this effort is a CODE. ORTIZ,M.G.; GHAN.L.S. EG&G Idaho, Inc. December priontized listing of AFW failures which have occurred at the 1992. 89pp. 9302230168. EGG-2665. 64979 001.
P ant and at other PWRs. This listing is intended for use by l
The Nuclear Regulatory Commission (NRC) revised the emer.
gency core coohng system heensing rule to allow the use of NRC inspectors in the preparation of inspection plans address-best estirrate computer codes, provided the uncertainty of the ing AFW risk-important components at the Fort Calhoun plant.
calculations are quantified and used in the licensing and regula-NUREG/CR-5835: AUXILIARY FEEDWATER SYSTEM RISK-tion process The NRC developed a genenc methodology called Code Scahng, Applicability, and Uncertainty (CSAU) to evaluate BASED INSPECTION GUIDE FOR THE BEAVER best estimate code uncertainties. The objective of this work was VALLEY, UNITS 1 AND 2 NUCLEAR POWER PLANTS.
to adapt and demonstrate the CSAU methodology for a small-LLOYD,R.C.; VEHEC,T.A,; MOFFITT,N E.; et al. Battelle Memo-break loss-of coolant accident (SBLOCA) in a Pressurized rial institute. Pacific Northwest Laboratory. February 1993.40pp.
Water Reactor of Babcock & Wilcox Company lowered loop 9303120101. PNL-7925. 74236:271.
design using RELAPS/ MOD 3 as the simulation tool The CSAU in a study sponsored by the U.S. Nuclear Regulatory Com-methodology was successfully demonstrated for the new set of mission (NRC), Pacific Northwest Laboratory has developed and vanants defined in this project (scenario, plant design, code).
applied a methodology for denving plant specific risk based in-However, the robustness of the reactor design to this SBLOCA spection guidance for the auxihary feedwater (AFW) system at j
scenano limits the applicability of the specific results to other pressurized water reactors that have not undergone probabilistic plants or scenanos. Several aspects of the code were not exer-nsk assessment (PRA). This methodology uses existing PRA re-cised because the conditions of the transient never reached sults and plant operating experience information. Existing PRA-enough seventy. The plant operator proved to be a determinin l based inspecton guidance information recently developed for a
factor in the course of the transient scenario, and steps were the NRC for various plants was used to identify genenc compo-taken to include the operator in the model, simulation, and anal-nent failure modes. This information was then combined with 1
yses.
plant-specific and industry-wide component information and fail-NUREG/CR 5822: ANALYSIS OF THERMAL MIXING AND ure data to identify failure modes and failure mechanisms for BORON DILUTION IN A PWR. SUN.J.G.; SHA,W.T. Argonne the AFW system at the selected plants. Beaver Valley Units 1 l
National Laboratory. February 1993. 92pp. 9303250056. ANL-and 2 were selected as two of a series of plants for study. The 1
91/43. 74358.154.
product of this effort is a prioritized hsting of AFW failures which
)
Thermal mixing and boron dilution in a pressurized water re-have occurred at the plant and at other PWRs. This listing is actor were analyzed with COMMIX codes. The reactor system intended for use by NRC inspectors in the preparation of in-was a four-toop Zion reactor that was initially filled with hot spection plans addressing AFW risk important components at boron-nch water. It was assumed that the reactor coolant Beaver Valley Units 1 and 2.
pumps are inpped. Following the trip, cold unborated water from l
Main Citations and Abstracts 7
WUREG/CR 5836: AUXILIARY FEEDWATER SYSTEM RISK-System (NPRDS) databases for failures of pressure sensing BASED INSPECTION guide FOR THE PALO VERDE NUCLE-systems in nuclear power plants.
AR POWER PLANT. BUMGARDNER,J.Da MOFFITT,N Ec NUREG/CR-5863: RISK ASSESSMENT OF ISOLATION DEVICES GORE,B.F.: et al Battelle Memonal Institute, Pacific Northwest IN SAFETY SYSTEMS. CRAMOND,W R; MITCHELL D B.
Laboratory. February 1993 34pp. 9302230328. PNL-7908.
Sandia National Laboratories MILLER,S P-; et al Science Appli-64384.128.
cations Intemational Corp. (formerly Science Applications, Inc )
In a study sponsored by the U.S. Nuclear Regulatory Com.
January 1993.196pp. 9302230219. SAND 92 0538 64963.037.
mission (NRC) Pacific Northwest Laboratory has developed and Electronic isolaivrs are uni to maintain electncat separation applied a methodology for deriving plant-specific nsk-based in-between safety and non-safety systems in nuclear power plants.
spection guidance for the auxihary feedwater (AFW) system at The concern is that these deviws may fail allowing unwanted i
pressunzed water reactors that have not undergone probabilistic signals or energy to act upon se ety systems, or prevenung de-fisk assessment (PRA) This methodology uses existing PRA re.
stred signals from performing heir intended function. While 6
suits and plant operating expenence information Existing PRA.
operabonal hsstory shows many isolation device problems re-based inspection guidance information recently developed for quiring adjustments and maintenance, we could not find ince-I the NRC for vanous plants was used to identify generic compo.
dents where there was a safety implication Even hypotnesiring nent failure modes. This information was then combined with multiple simultaneous failures did not lead to significant contn-plant-specific and industry-wide component information and fail.
butions to core damage frequency Although the analyses per-7 ure data to dentify failure modes and failure mechanisms for formed in this study were not extensive or detailed, there seems the AFW system at the seiected plants. Palo Verde was select.
to be no evidence to suspect that isolation device failure is an ed as one of a senes of plants for study. The product of this issue which should be studted further effort is a pnoritized listing of AFW failures which have occurred at the plant and at other PWRs. This hsting is intended for use NUREG/CR-5883: HEALTH RISK ASSESSMENT OF IRRADIAT-by NRC inspectors in the preparation of inspection plans ad-ED TOPAZ. NELSON.K.; BAUM.J.W. Brookhaven National Lab-d essing AFW nsk important components at the r,aiu /erde oratory. January - 1993 156pp. 9302220410. BNL-NUREG-52330 64901:001.
NUREG/CR-5844: AGING ASSESSMENT OF BISTABLES AND inaatated topaz gemstones are currently processed for color SWITCHES IN NUCLEAR POWER PLANTS. LE E.B.S.;
improvement by subjecting clear stones to neutron or high-VILLARAN.M.; SUBUDHINI Brookhaven National Laboratory.
energy e!ectron irradiations, which leads to activation of trace January 19E3. 213pp. 9302230104. BNL-NUREG-523 t 8.
elements in the stones. Assessment of the nsk to consumers 64979.119 required the identification and quantification of the resultant ra-Bestables and process switches play vital roles in the instru-dionuclides and the attendant exposure. Representative stones mentation and control log.c of a nuclear power station. To un-from Brazil, India, Nigeria, and Sn Lanka were irradiated and derstand the aging charactenstics of these components, more analyzed for gamma ray and beta particle emissions, using than 5.000 NPRDS events and more than 1200 LERs were re-sodium iodide and germaniura spectrometers; and Geiger.
viewed and analyzed. Telephone surveys were conducted and Muller, plastic and liquid scintillation, autoradiography; and ther-nuclear plant site visits were made to collect information on op-moluminescent-dosimetry measurement techniques. Based on erating exponence and the current status of these devices-these studies and other information denved from published liter-Interaction with the equipment manufacturers provided further ature, dose and related nsk estimates were made for typical details on the designs of bistables and switches. The aging user conditions New cnteria and methods for routine assays for characteristics studied included the effects of aging on failure acceptable release, based on gross beta and gross photon frequency, failure mode, and f ailure cause This study found that emissions from the stones, were also developed.
two groups of bistables are in operation. The first group which consists of older bistables, needs attention in the near future NUREG/CR-5898: AUXILIARY FEEDWATER SYSTEM RISK-concerning the decisron on replacement or refurbishment; how-BASED INSPECTION GUIDE FOR THE POINT BEACH NUCLE.
AR POWER PLANT. LLOYD,R C.; MOFFIT1,N E.; GORE,B F.;
ever, the second group, which is newer. still has time to manage aging concerns. Most of the onginal switches employed et al. Battelle Memonal Institute, Pacific Northwest Laboratory.
in reactor protection systems have been replaced with transmit.
February 1993. 32pp. 9303120004. PNL-8105. 74240:225.
ters and bistables, and the trerid shows that the remaining ones in a study sponsored by the U S. Nuclear Regulatory Com-will be replaced in the near future. Based on the results of the mission (NRC). Pacific Northwest Laboratory has developed and analyses, recommendations for better aging management are applied a methodology for denving plant specific risk-based in-made, and the areas for future studies are identified.
spection guidance for the auxiliary ftedwater (AFW) system at NUREG/CR-5851: LONG TERM PERFORMANCE AND AGING 9# #
CHARACTERISTICS OF NUCLEAR PLANT PRESSURE sults and plant operating expenence information. Existing PRA-TRANSMITTERS.
HASHEM!AN.H.M '-
MITCHELL,D W
- FAIN.R.E.; et al. Analysis & Measurement Services Corp. March the NRC for vanous plants was used to identify genenc compo-1993. 375pp. 9304020285. 74450 001 This report presents the results of a comprehensive research plant specific and industry-wide component information and fail-and development project conducted for the NRC to study the ure data to identify failure modes and failure mechanisms for effects of normal aging on cahbration and response time of nu-the AFW system at the selected plants. Point Beach was se-clear plant pressure, level, and flow transmitters and to develop lected as one of a senes of plants for study. The product of this and validate new methods for testing the performance of the effort is a priontized listing of AFW lailures which have occurred transmitters as installed in nuclear power plants The project in-at the plant and at other PWRs. This listing is intended for use volved research in seven areas as follows: 1) Aging tests of by NRC inspectors in the preparation of inspection plans ad-complete transmitter assemblies; 2) Aging tests of cntical com-dressing AFW nsk-important components at the Point Beach ponents of transmitters; 3) Testing the effects of sensing line plant' length, blockages, and voids on the response time of pressure sensing systems; 4) Oil loss phenomenon in Rosemount and NUREG/CR-5903: VALIDATION OF SMART SENSOR TECHNOL-other transmitters; 5) Validation of new methods for on-hne test.
OGIES FOR INSTRUMENT CAllBRATION REDUCTION IN NU-ing of response times of pressure transmitters; 6) On-line detec.
CLEAR POWER PLANTS. HASHEMIAN H.M ; MITCHELLD.W.;
tion of oil loss in Rosemount transmitters, and 7) Analysis of Li-PETERSEN.K M.; et al. Analysis & Measurement Services Corp censee Event Report (LER) and Nuclear Plant Reliability Data January 1993.168pp. 9302230183. 64964'004.
a s
a l
1 8
Main Citations and Abstracts This report presents the preliminary results of a research and This report documents the denvation and venfication of the f
development project on the validation of new techniques for on-closed form analytical solutions of the one-dimensional nondis-hne testing of calibration dnft of process instrumentation chan-persive and isothermal transport of a radionuclide in a layered nels in nuclear power plants. These techniques generally in-system of saturated planar fractures coupled with diffusion into volve a computer based data acquisition and data analysis the adjacent saturated rock matnx. The analytical solutions are system to trend the output of a large number of instrument based on the Laplace transform method where the domains of channels and identrfy the channels that have dnfted out of toler.
radionuchde migration in both fractures and rock layers are one-ance. This helps limit the calibration effort to those channels dimensional and of the semi-infinite type, implying in this in-which need the calibration. as opposed to the current nuclear stance that radionuclide diffusion from the fractures wall to the industry practice of calibrating essentially all the safety-related rock matnx may extend to infinity. The sorption phenomena in instrument channels at every refueling outage.
both fracture and rock matnx layers are descnbed by a linear equilibnum sorption isotherm. Two types of radionuclide release NUREG/CR-5911: SOURCE TERM EVALUATION FOR RADIO-modes are considered. the en1tinuously decaying, and the peri-ACTIVE LOW-LEVEL WASTE DISPOSAL PERFORMANCE AS-odically fluctuating decaying sorce, which may, in turn, be sub-SESSMENT. COWGILL,M G.; SULLIVAN,T.M. Brookhaven Na' ject to step and band releas( nodes. The initial concentrations l
tional Laboratory. January 1993. 97pp. 9302230094. BNL-in the fracture and rock matrix layws may be assigned spatially NUREG.52334. 64968.001.
varying values in the Case of the first, wheres uniform ones information compded on the low-level radioactive waste dis-may be implemented in both cases.
posed at the three currently operating commercial disposal sites during the period 1987 - 1989 have been reviewed and proc-NUREG/CR-5917 V02: SENSITIVnY AND UNCERTAINTY ANAL-essed in order to determine the total activity distnbution in YSES APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE terms of waste stream, waste classification and waste form. The TRANSPORT IN A LAYERED FRACTURED ROCK. Evaluation review identified deficiencies in the information currentfy being Of The Limit State Approach. WU,Y.-T.; GUREGHIAN,A.S; i
i recorded on shipping manifests and the development of a uni-SAGAR.B.; et af. Center for Nuclear Waste Regulatory Analy-form mees' 4 racommended. The data from waste disposed ses. December 1992. 71pp. 9301220115. CNWRA91-010.
dunng 1989 at one of the s6tes (Richland, WA.) were more de-64650.021.
tailed than the data available dunng other years and at other The Limit State approach is based on partitioning the parame-sites, and thus were amenable to a more in depth treatment.
ter space into two parts: one in which the performarice measure This included determination of the distnbution of activity for is smaller than a chosen value (called the limit state), and the each radionuclide by waste form, and thus enabled these data other in which it is larger. Through a Taylor expansion at a suit-to be evaluated in terms of the specific needs for improved able point, the partitioning surface (called the limit state surface) modeling of releases from waste packages. From the results, is approximated as either a linear or quadratic function The preliminary lists have been prepared of, the isotopes which success and efficiency of the limit state method depends upon might be the most significant from the aspect of the develop-chooseng an optsmum point for the Taylor expansion. The point rnent of a source term model.
in the parameter space that has the highest probability of pro-ducing the value chosen as the limit state is optimal for expan-NUREG/CR 5914: CHEMICAL COMPOSITION AND RT(NDT) DE-sion. When the parameter space is transformed into a standard TERMINATIONS FOR MIDLAND WELD WF 70.
Gaussian space, the optimal expansson point, known as the NANSTAD.R.K-; MCCABE.D.E.; SWAIN.R.La et al. Oak Ridge Most Probable Point (MPP), has the property that its location on Nationat Laboratory. December 1992. 379pp. 9302010102.
the Limit State surface is closest to the origin. Additionally, the ORNL-6740. 64728 001.
projections onto the parameter axes of the vector from the The Heavy-Section Steel irradiation Program Tenth Irradiation origin to the MPP are the sensitivity coefficients Once the MPP l
Senes has the objective to investigate the effects of radiation is determined and the Limit State surface approximated, formu-l on the fracture toughness of the low-upper shelf submerged-are las (se Equations 4-7 and 4 8) are available for determining welds (B&W designation WF-70) in the reactor pressues vessel the probability of the performance measure being less than the l
of the canceled Midland Unit i nuclear plant. This report dis-limit state. By choosing a succession of limit states, the entire cusses determination of variations in chemical composition and cumulative distribution of the performance measure can be de-reference temperature (RT(NDT)) throughout the welds. Speci-termined. Methods for determining the MPP and also for im-mens were machined from different sections and through thick-proving the estimat9 of the probability are discussed in this ness locations in both the beltline and nozzle course welds. The report.
i l
nil-ductility transition temperatures ranged from -40 to -60 de-grees C (-40 and 76 degrees F) while the RT(NDT)s, controlled NUREG/CR-5922: MODULAR HIGH-TEMPERATURE GAS-by the Charpy behavior, vaned from -20 to 37 degrees C (-4 to COOLED REACTOR SHORT-TERM THERMAL RESPONSE TO 99 degrees F) The upper shelf energies varied from 77 to 108 FLOW AND REACTIVITY TRANSIENTS. CLEVELAND J.C. Oak J (57 to 80 ft-lb). The combined data revealed a mean 41 J (30 Ridge National Laboratory. February 1993. 55pp. 9303110375.
ft-lb) temperature of -8 degrees C (17 degrees F) with a mean ORNL/TM-12179. 74212:239.
upper shelf energy of B8 J (65 ft-Ib). The copper contents range The research reported here has been conducted at the Oak from 021 to 0 34 wt % in the beltline weld and from 0.37 to Ridge National Laboratory for the Nuclear Regulatory Commis-0 46 wt % in the nozzle course weld. Atom probe field ion mi.
sion's Division of Regulatory Applications of the Office of Nucle-croscope analyses indicated substantial depletion of copper in ar Regulatory Research. The short-term thermal response of the matrix but no evidence of copper clustenng Statistical anal-the Modular High Temperature Gas-Cooled Reactor (MHTGR) yses of the Charpy and chemical composition results as well as is analyzed for a tange of flow and reactivity transients. These interpretation of the ASME procedures for RT(NDT) determina.
transients include loss of forced circulation without scram, spuri-tion are discussed.
ous withdrawal of a control rod group, moisture ingress, control rod and control rod group ejections, and a rapid core cooling NUREG/CR-5917 V01: SENSITIVITY AND UNCERTAINTY ANAL-event. For each event analyzed, an event descnption, a discus-YSES APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE sion of the analysis approach and assumptions, and results are TRANSPORT IN A LAYERED FRACTURED ROCK.MULTFRAC presented. When possible, results of these analyses are com.
Analytic Solutsons And Local Sensitivities. GUREGHIAN.A.B.;
pared with those presented by the designers in the MHTGR WU,Y.-T.; SAGAR.B.; et al. Center for Nuclear Waste Regula-Probabilistic Risk Assessment. The importance of inherent tory Analyses. December 1992.
139pp. 9302230456.
safety features is illustrated, and conclusions are presented re-CNWRA91010 64959:001.
garding the safety performance of the MHTGR. Recommenda-l l
=
1 4
]
Main Citations and Abstracts 9
1 tions are made for a more in-depth examinaten of MHTGR re-NUREG/CR-5936: ENHANCEMENTS TO THE ACCIDENT PRE-sponse for some of the analyzed transients. The coupled heat CURSOR METHODOLOGY. BOHNHOFF,W.J.; DINGMAN.S E.;
i n
transfer-neutron kinetics model is desenbed in detal in Appen-CAMP.A L. bandia National Laboratones. February 1993,138pp.
i dix A-9303120072. SAND 92-2109. 74241:001.
A feasibility study for developing an improved tool and kn-NUREG/CR 5926: SANS INVESTIGATION OF LOW ALLOY proved rnodels for performing event assessments is desenbed.
STEELS IN NEUTRON IRRADIATED, ANNEALED, AND REIR-The study indicates that the IRRAS code should become the RADIATED CONDITIONS.
KAMPMANN,R :
FRISIUS,F.;
base tool for perfocming event assessments, but thu modifsca-j HACKBARTH,H.; et al Institute for Materials Research. Febru-tioru would be needed to make it more suitable for routine use.
}
ary 1993. 44pp. 9303120100. MEA-2490. 74240.262.
Alternative system modeling approaches are explored and an Small Angle Neutron Scattenng (SANS) expenments were approach is recommended that is based on improved train-level made on seve a! tow alloy stects and submerged-arc welds pro-models. These models are demonstrated for Grand Gulf and 4^
totypic of nuclear reactor vessel construction. The ob ect>ve was Sequoyah The insights that can be gained from importance l
I the characterization of radiation-enhanced and/or radiation-in-measures are also demonstrated. The feasibihty of using Individ-duced precipitation coninbuting to mechanical property changes ual Plant Examinaten (IPE) submittals as the basis for train-observed in tensile and notch ductility tests of the matenals.
level models for precursor studies was also examined. The level 4
The matenals were irradiated in the UBR Test Reactor under of reported detail was found to vary widely, but in general, the closely controlled condihons. A portion of the samples were ex-submittals would not provide sufficient information to fully define amined in the 288 degrees C irradiated (1) condition; others the model The feas;bihty of developing an industry risk profile I
were examined in the postirradiation annealed (IA) condition from Accident Sequence Precursor results and of trending pre-and in the 288 degrees C reirradiated (IAR) condition Expen-cursor results for individual plants is considered but not recom-mental vanables included matena! composition (pnmarily %Cu, mended because of data sparsity.
%P, %Ni content), postirradiation anneahng temperature (454 I
+
degrees C and 399 degrees C) rc:rradct:en fluence level, and NUREG/CR-5938: NATIONAL PROFILE ON COMMERCIALLY neutron-fluence rate (~0.08,0.7, and 9 x 10(12) n/cm(2)-s(-1)-
GENERATED LOW-LEVEL RADIOACTIVE MIXED WASTE.
E > 1 MeV). The apparent influence of the desenbod vanables KLEIN.J.A; MROCHEK,J E.; JOLLEY,R,L.; et al. Oak R<go Na-on the sae, number density, and composition of copper och tional Laboratory. December 1992. 468pp. 9301220128. ORNL.
precipitates was the primary focus of the SANS analyses. SANS 673t 64650.094.
observations are related to measured notch ductility and tensile This report details the findings and conctwons drawn from a 3
property changes, with a view toward mechanist c explanation surve, undertaken as part of a joint RS Nuclear Regulatory of the observed mechanicat property trends for 1, IA. and IAR Commc.tsion ar.d U.S. Environmentat notection Agency-spon-conditions' sored protect entitled " National Profile on Commercially Gener-NUREG/CR-5933; HIGH PRESSURE COOLANT INJECTION ated Low-Level Radioactive Mixed Waste." The overall objec-(HPCI) SYSTEM RISK BASED INSPECTION GUIDE FOP tive of the work was to compile a national profile on the vol-DRESDEN NUCLEArt POWER STATION UNITS 2 AND 3.
umes, chwacteristics, and treatabihty of commeremli/ generaMd SHIER,W; VILLARAht.L; GUNTHER.W. Brookhaven National low-lovel mixe1 waste for 1990 by five major facility categories.
Laboratory, February %3. 48pp. 9303120079. BNL-NUREG.
academic, industnal, medical, and NRC/ Agreement State li-52343. 74241:280.
censed government facihtes and nuclear utihties included in A review of the operating expenence for the High Pressure the,eport are descriptions of the methodology used to coldt Coolant injection (HPCI). system at the Dresden Nuclear Power and collate the data, the procedures used tc estimate the mixed Station Urds 2 and 3 is descnbed in this repo% The information waste generation rate or commercial facilities in the United for this review was obtained from Dresden Licenseo Event Re.
States in 1990, and the identihcation of available treatment I
ports (LERs) that were generated between 1980 and 1989.
technolog es to meet apphcable EPA treatment standards (40 These LERs have been categonzed into 23 failure modes that CFR Part 268) and, if possible, to render the hazardous compo-have been pnoritized based on probabihstic ask assessment nont of specific mixed waste streams nonhazardous. The report considerations. In addition, the results of the Dresden operating also contains information on existing and potential commercial expenence review have been compared with the results of a waste treatment facilities that may provide treatment for specific similar, industry wide operating expenence review. This compan-waste streams identified in the national survey.
son provides an Indicaten of areas in the Dresoen HPCI system that should be given increased attention in the priontization of NUREG/CR-5951: THE MANAGEMENT OF ATWS BY BORON inspection resources.
INJECTION. DIAS,M.P. Meatuwa, Univ, of, Sri Lanka. YAN,H.;
i THEOFANOUS,T.G Cahic nia, Univ. of, Sar ta Barbara, CA.
NUREG/CR-5934: HIGH PRESSURE COOLANT INJECTION March 1993. 58pp. 93",.f020304. 74451:037, (HPCI) SYSTEM RISK-DASED INSPECTION GUIDE FOR Experimental simulations of the muttidimensional mixing /strat-l OUAD-CITIES STATION, UNITS 1 AND 2 VILLARAN,M.;
itication phenomena in the lower plenum of a Boihng Water Re-TRAVIS R.; GUNTHER,W. Brookhaven National Laboratory.
actor dunng operation of the Standby Liquid Control System January 1993 55pp. 9303190108. BNL NUREG.52344-(SLCS) are reported. The simulations both at full and 1/2-scale j
74314:001.
allow the demarcation of the fully entraining regime, which is The High Pressure Coolant Injection (HPCI) system has been also interpreted in terms of an approximate corisideration of examined from a risk perspective. A System Risk-Based inspec-flow stabihty cnteria, based on the local Froude number. These tion Guide (S-RIG) has been developed as an aid to HPCI results are combined with analyses of the subsequent disper-system inspections at Quad Cities. Included in this S-RIG is a sion (of entrained boron) throughout the pnmary bystem and in discussion of the role of HPCI in mitegating accidents and a combination with neutron diffusicn and natural convection presentation of PRA-based failure modes which could prevent (power flow-void coupling) predictens of reactor kinetic behav proper operation of the systern The S-RIG uses industry oper-
,or are made. On this basis the performance of SLCS dunng ating experience, including plant specific illustrative examples to ATWS is assessed and a discussion on current Errergency Op-augment the basic PRA failure modes. It is designed to be used erating fiocudures is offered as a reference for both routine inspections and the evaluation j
of the significance of componerH failures.
l e-.
.,n
+.
10 Main Citations and Abstracts NUREG/CR-5952: EVALUATION OF CP.ACK POP-INS AND THE A family of seH-similar fields provides the two parameters re-DEiERMINATION OF THEIR RELEVANCE TO DESIGN CON-quired to charactente the full range of high-and low triaxiality SIDERATIONS. MCCABE.D E. Oak Ridge National Laboratory.
crack tip states. The two parameters, J and O, have distinct February 1993.
30pp.
9303110379. ORNL/TM-12247.
roles: J sets the size scale of the process zone over which 74212-057.
large stresses and strains develop, while O scales the near tip The issue with regard to crack pop-ins is to determine if such stress distribution felative to a high triaxiality reference stress events are signdicant to design considerations. The hterature state. Ao immediate consequence of the theory is this: it is the contains ample evidence of pop-in occurrences, but scant infor-toughness values over a range of crack tip constraint that fully mation is offered on how pop-ins should be handled as an issue characterize the material s fracture resistance. It is shown that fnr design problems. Because there are two types of cleavage O provides a common scale for interpreting cleavage fracture c!ack ongins, the problem was subdivided into two classes of and ductile teanng data thus allowing both tailure modes to be matenals, monohthic.and weldments with brittle zones. The incorporated in a single toughness locus. The evolution of O, as wtidment situation can be analyzed as a crack-arrest toughness plasticity progresses frorn small scale yielding to fully yielded capability problem, following the recommendations of Sumpter conditions, has been quantified for several crack geometries et al. For monolthic matenals, pop-ins are more dangerous, and for a wide range of material strain hardening properties. An since they appear to be a part of the more commonly encoun-indicator of the robustness of the J-O fields is introduced; O as tered full-cleavage K(Jc) instability distributions. A recommenda-a field parameter and as a pointwise measure of stress level is tion is made on how to determine if pop-in events lie outside of discussed.
the larger body of K(Jc) instabilibes, The evaluation procedure recommended by the Amencan Society for Testing and Maten_
NUREG/CR-5959: HIGH PRESSURE COOLANT INJECTION als for pop-ins seems to dismiss the possibility that small crack (HPC0 SYSTEM RISK BASED INSPECTION GUIDE FOR jumps can be a safety-related issue. The present work suggests ENRICO FERMI ATOMIC POWER PLANT, UNIT 2.
that nearly all pop-in events, regardless of the magnitude of VILLARAN.M.; TRAVIS.R4 GUNTHER.W. Brookhaven National crack jump, are relevant to safety issues.
Laboratory. tanuary 1993. 55pp. 9303190116. BNL-NUREG-52352. 74314.059.
NUREG/CR-5953: STUDIES OF HUMAN PERFORMANCE The High Pressure Coolant injection (HDCl) system has been DURING OPERATING EVENTS.1990-1992. MEYER.O R.;
examined from a risk perspective. A System Risk-Based Inspec-HILL,S G; STEINKE.W.F. EG&G Idaho, Inc. January 1993.
tion Guide (S-RIG) has been developed as an aid to HPCI 86pp. 9302010090. EGG 2690. 64727:001.
system inspections at the Enrico Fermi Unit 2 Nuclear Power in order to better evaluete the human factors influencing op' Plant. Included in this S RIG ts a discussion of the role of HPCI erator performance during operating events at nuclear power n rnitigating accidents and a presentation of PRA-based failure stations, the Office for Analysis and Evaluation of Operational modes which could prevent proper operation of the system. The Data (AEOD) of the U S. Nuclear Regulatory Commission (NRC)
S-RIG uses industry operating expenence, including plant spe-initiated a proj.ect to perform onsite analyses of selected events.
cific illustrative examples to augment the basic PRA failuro An intenm report on the results of the analysis of the first six modes It is designed to be used as a reference for both routine selected events was pubbshed in May 1991. Causal factors for inspections and the evaluation of the significance of component operator performance were identified and categonzed in the in' failures tenm report. Subsequently,10 more onsite analyses have been conducted. This is a report on the analysis of the 16 events.
NUREG/CR-5961: POSTTEST DESTsiUCTIVE EXAMINATION OF Summanes of the 16 operating events analyrad can be found in THE STEEL LINER IN A 1:6. SCALE REACTOR CONTAIN-Appende: A MENT MODEL. LAMBERT L D. Sandia National Laboratories.
NUREG/CR-5956: CONSIDERATION OF UNCERTAINTIES IN February 1993. 40pp. 9302220439. SAND 92-1721. 64899:228.
SOIL-STRUCTURE INTERACTION COMPUTATIONS.
A 1.6 scale model of a nuclear reactor containment model COSTANTINO,Ch MILLER.C.A. City College of New York, was built and tested at Sandia National Laboratories as part of New York, NY. ' Viking Systems International December 1992.
a research program sponsored by the Nuclear Regulatory Com-140pp. 930122t'172. CEERC-91 105. 64680:046.
mission to investigate containment integnty. The overpressure This report presents a summary of the results obtained in a test was terminated due to leakage from a large tear in the study conducted to evaluate and quantify somo important ef.
steel liner. A limited destructive examination of the liner and an-fects of soil-structure interaction (SSI) on the seismic response chorage system was conducted to gain information about the of Category I facilities. The current procedures utilized in SSI failure mechanism and is described. Sections of liner were re-evaluations typically use complex computer analyses to treat moved in areas where liner distress was evident or where large the vanous important aspects of the problem. The purpose of strains were indicated by instrumentation dunng the test. The i
this study has been to provide input to the Staff for developing condition of the liner, anchorage system, and concrete for each consistent guidelines for assessing adequacy of these SSI com-of the regions that were investigated are described. The proba-putations as well as clanfication of some portions of the SRP ble cause of the observed posttest condition of the liner is dis-relating to SSI calculations. The specific areas addressed in this cussed.
study are: (a) summanzing the entena needed when using the NUREG/CR-5962: HEALTH AND SAFETY IMPACTS FROM DIS-targe computer codes used in SSI studies, (b) providing recom.
CRETE SOURCES OF NATURALLY-OCCURRING AND AC-mendations for specification of control point location for soil CELERATOR-PRODUCED RADIOACTIVE MATERIALS sites; (c) providing specific enteria to allow the Staff to judge the (NARM). NUSSBAUMER D.; WIBLIN,C.: WELCH.L, Advanced adequacy of fixed base structural analyses. (d) the development of expanded guidehnes for inclusion of vanabihty in soil proper-Systems Technology, Inc. February 1993. 54pp. 9303120051.
ties in the SSI calculations, and (e) the development of esti-T NWhhemmdeMWp mates of radiation damping inherent in the detailed numencal ring and accelerator-produced radioactive material (NARM) and ays s performed or SSI evaluations of typical Category I estimates nsks posed by the possession, use and disposal of them. A distinction between discrete and diffuse NARM sources NUREG/CR-5958: TWO-PARAMETER FRACTURE MECHANICS:
is made with discrete sources being high activity, low volume THEORY AND APPLICATIONS. O'DOWD,N.P. Imperial College, and diffuse sources being low activity, high volume. Two nanc-l London, UK. SHIH,C.F. Brown Univ., Providence, RL
- Navy, cunes per gram is used as a separation guide between high and Dept.
of.
February 1993.
45pp.
9303120046.
tow activity, although use of this value does not impact the re-CDNSWCSMECR t 692. 74238:225.
port's conclusions. Most NARM is under regulatory control of
.. ~. - -
Main Citations and Abstracts 11 States that either itCense of register users but reporting require.
report was obtained from interviews conducted with each state ments t'e not uniform. Use in consumer products has declined regulatory agency that administers an incentive program and with vi'tually no production today; however, lack of information each utility that owns at least 10% of an affected nuclear power
(
available concerning radiation exposures resulting form posses.
plant The agreements, orders, and settlements that form the sion of ageing radium sources precludes a quant!tative risk as-basis for each incentive program were reviewed as required.
sessment in this report. The report identifies the type of infor.
The interviews and supporting documentation form the basis for mation needed to permit such an assessment. Regarding accel.
the individual state reports desenbing the structure and financial erator produced radioactive matenal (ARM), use of this matenal impact of each incentive program in nuclear medicine programs has recently increased. Available radiation exposure data regarding ARM handling and use indi.
NUREG/CR-5977: A PERFORMANCE INDICATOR OF THE EF.
cates that the nsk to workers and the public is low at this time.
FECTIVENESS OF HUMAN ~ MACHINE INTERFACES FOR NU.
CLEAR POWER PLANTS.
MORAY.N; JONES,B.J.;
NUREG/CR 5964:
SAPHfRE TECHNICAL REFERENCE RASMUSSEN J.; et at Illinois, Univ. of Urbana, IL. January MANUAL:lRRAS/ SARA VERSION 4.0.
RUSSELLED.;
1993.68pp.9302010095 VILU-ENG92-4007. 64727:091.
ATWOOD.C.L.; SATTISON M B.: et al. EG8G Idaho, Inc Janu-ary 1993 75pp 93022303GG. EGG-2692. 64998199.
Effective interfaces must call up operators' deep understand-This report provides information on the pnnciples used in the ing of plant operation if operators are to deal effectively with normal operation and diagnosis of transients. The present re-construction and operation of Version 4.0 of the Integrated Rel'-
search examines the ability of a memory recall task to indicate ability and Risk Analysis System (IRRAS) and the System Anal-the ability of an interface to couple plant state to operator ysis and Risk Assessment (SARA) system. It summanzes the knowledge. Novices, people with intermediate experience, and fundamental mathematical concepts of sets and logic. fault expenenced nuclear power plant operators viewed three kinds trees. and probability The report then desenbes the ajonthms of displays. They watched nine simulated transients and tried to that these programs use to construct a fault tree and to obtain the mmema: cut sats. !! gives the formulas used to obtain the recall the values of variables, or the states through which the peabe; of the top event from the minimal cut sets, and the plant passed, and to detect and diagnose the nature of the tran-formulas for probabilities that are appropriate under various as-sients The displays were simulated analog instruments, simulat-ed analog with pressure-temperature graphics, and an ansmated eq%s conceming repairability and mission time. It defines representation of the Rankine cycle. The recall tasks did not the measures of basic event importance that these programs can calculate The report gives an overview of uncertainty anal-show promise as indirect performance indicators of the quahty ysis using simple Monte Carlo samphng or Latin Hypercube of the interfaces, but the diagnosis test detected differences in sampling. and states the algorithms used by these programs to the quality of the displays and the levels of expertsse.
generate random basic event probabilities from vanous distnbu-NUREG/CR-5980: THREE DIMENSIONAL REDISTRIBUTION OF tions. Further references are given, and a detailed example of TRITIUM FROM A POINT OF RELEASE INTO A UNIFORM the reduction and quantification of a simple fault tree is provid-UNSATURATED SOILA Deterministic Model For Tntium Migra-ed in an appendix.
tion in An Arid Disposal Site. SMILES,D E.: GARDNER,W.R.;
NUREG/CR 5973: CODES AND STANDARDS AND OTHER SCHULZ,R.K. California. Univ. of, Berkeley, CA. January 1993.
GUIDANCE CITED IN REGULATORY DOCUMENTS.
30pp. 9302020469. 64729:020.
NICKOLAUSJR, VINTHER,R.W.; MAGUIRE-MOFFITT; et al.
This report presents a three-dimensional model for tritium mi-Battelle Memonal Institute, Pacific Northwest Laboratory. Janu.
gration in an and waste disposal site. When tntiated water is re-ary 1993. 73pp. 9302230373. PNL-8462. 64960:001.
leased at a point in a uniform and relatively dry soil it redistnb-As part of the U.S. Nuclear Regulatory Commission (NRC) utes in both the liquid and vapor phases. The flux density of tnt-Standard Reww Plan Update and Development Program, Pa_
ium in each phase is of the same order of magnitude however cific Northwest Laboratory developed a listing of industry con-so tntium redistribution is modeled as if transfer occurs "in par-sensus codes and standards and other govemment and indus_
allel" in the liquid and vapor phases. The approach we desenbe try guidance referred to in regulatory documents _ This hsting uses the diffusion equation cast in radial (sphencal) coordinates j
identifies the version of the code or standard cited in the regula-and takes into account radioactive decay. It permits calculation j
tory document, the regulatory document, and the current ver-of radial profiles of tntium concentration, within and external to sion of the code or standard, it also provides a summary char-a sphere of released solution. We assume the concentration acterization of the nature of the citation. This listing was devel-within this sphere initially to be uniform. The solution also pre-
)
oped from electronic searches of the Code of Federal Regula-dicts attenuation and rate of advance of the maximum of tntium j
tions and NRC's Bulletins, information Notices, Circulars, Ge_
concentration as it advances in the soil. With deep disposal in a neric Letters. Pohey Statements. Regulatory Guides, and Stand.
desert soil, the model predicts that intium migraton will be very j
ard Review Plan (NUREG-0800)_
short range, with a maximum of a few meters.
i NUREG/CR-5975: INCENTIVE REGULATION OF INVESTOR-NUREG/CR-5987: MICROBIAL-INFLUENCED CEMENT DEGRA.
OWNED NUCLEAR POWER PLANTS BY PUBLIC UTILITY DATION LITERATURE REVIEW.
ROGERS.R D.:
REGULATORS. MCKINNEY,M.D.; ELLIOTT,0.B. Battelle Memo-HAMILTON.M.Aa MCCONNELL,J.W. EG8G Idaho, Inc. March rial Institute, Pacific Northwest Laboratory. January 1993.80pp.
1993. 34pp. 9303300171. EGG-2695. 74407:322.
9302220421. PNL 8466. 64899.001.
The Nuclear Regulatory Commission stipulates that disposed The U.S. Nuclear Regutatory Commission (NRC) periodically low-level radioactive waste (LLW) be stabilized. Because of ap-surveys the Federal Energy Regulatory Commission (FERC) and parent ease of use and normal structural integnty, cement has state regulatory commissions that regulate utility owners of nu-been widoty used as a binder to solidify LLW. However, the re-clear power plants. The NRC is interested in identifying states sulting waste forms are sometimes susceptible to failure due to that have established economic or performance incentive pro-the actions of waste constituents, stress, and environment. This grams applicable to nuclear power plants, including states with report reviews literature which addresses the effects of micro-new programs, how the programs are being implemented, and biologically influenced chemical attack on cement-solidified in determining the financial impact of the programs on the utili-LLW. Groups of microorganisms are identified, which are capa-ties. The NRC interest stems frorn the fact that such programs ble of metabolically converting organic and inorganic substrates have the potential to adversely affect.the safety of nuclear into organic and mineral acids. Such acids aggressively react power plants. The current report is an update of NUREG/CR-with concrete and can ultimately lead to structural failure. Mech-4911, incentive Regulation of Nuclear Power Plants by State anisms inherent in microbial-influenced degradation of cement.
Regulators, published in February 1991. The information in this based matenal are the focus of this report. This report provides
e 12 Main Citations and Abstracts sufficient evidence of the potential for microbial-influenced dete-the sediments and core data collected at the end of the expen-noration of cement.sohdified LLW to justify the enumeration of ment The unique features of this expenment were the accu-the conditions necessary to support the microbiological growth monted control of the inputs. the three-dimensionaf nature of and population expansion, as well as the development of appro-the experiment, the measurement of radioactive tracers in situ, pnate tests necessary to de'armine the resistance of cement-and the use of multiple injections. Tha in situ monitonng meth-solidified LLW to microbiological-induced degradation that could ods were neutron moderation for water content and gamma impact the stability of the waste form.
energy analysis for tracor concentration. The data are provided n 3 5-in. diskettes. The data include observation and injection NUREG/CR-5988: SOIL CHARACTERIZATION METHODS FOR wd consMion detads, inWn sown concenkabons, rah UNSATURATED LOW LEVEL WASTE SITES. WlERENGA P.J.,
active tracer and water content distributions in space and time.
YOUNG.M,H, Anzona, Univ. of, Tucson, AZ. GEE,G.W.; et al.
neutron probe calibration information, and sediment properties Battelle Memonal Inst:tute, Pacific Northwest Laboratory. Febru-determined in both the laboratory and field.
ary 1993.150pp. 9303120106. PNL-8480. 74236:120.
To support a license application for the disposal of low-level NUREG/CR-5998: SIMULATION OF UNSATURATED FLOW AND radioactive waste (LLW), applicants must charactenze the un-NONREACTIVE SOLUTE TRANSPORT IN A HETEROGENE-saturated zone. This requires an integrated plan to be devel-OUS SOIL AT THE FIELD SCALE, ROCKHOLD.M.L. Battelle oped for samphng and analyzing the soil horizons for physical Memorial Institute, Pac:fic Northwest Laboratory. February 1993.
and hydraulic properties. This document provides a strategy for 65pp. 9303120158. PNL-8496. 7424 t:139 developing this characterization plan. It describes pnnciples of A field-scale, unsaturated flow and solute transport experi-contaminant flow and transport, site characterization and moni-ment at the Las Cruces trench site in New Mexico was simulat-tonng strategies, and data management. It also discusses meth-ed as part of a " blind" modeling exercise to demonstrate the ods and practices that are currently used to monitor properties ability or inability of uncalibrated models to predict unsaturated and conditions in the soil profile, how these properties influence flow and solute transport in spatially vanable porous media.
water and waste migration, and why they are importet to the Simulations were conducted using a recently developed multi-heense application The methods part of the document is dwid-phase flow and transport simulator. Uniform and heterogeneous ed into sections on laboratory and field-based properties, then soil models were tested, and data from a previous expentnent further subdivided into the desenptcn of methods for determin-at the site were used with an inverse procedure to estimate ing 18 physical, flow, and transport properties. Because of the water retention parameters. A spatial moment analysis was availability of detailed procedures in many texts and journal arti' used to provide a quantitative basis for companng the mean ob-cles, the reader is often directed for details to the available hier-served and simulated flow and transport behavior. The results ature. References are rnade to expenments performed at the of this study suggest that defensible predictions of waste migra-Las Cruces Trench site, New Mexico, that support LLW site tion and fate at low-level waste sites will ultimately require site-characten2ation activities A major contnbution from the Las specific data for model calibration.
Cruces study is the expenence gained in handhng data sets for site charactenzation and the subsequent use of ;hese data sets NUREG/CR-6007: STRESS ANALYSIS OF CLOSURE BOLTS in modehng studies.
FOR SHIPPING CASKS. MOK.G C.; FISCHER,LE, Lawrence Livermore National Laboratory. HSU S.T. Kaiser Engineenng NUREG/CR-5991: PORFLOW. A MULTIFLUID MULTIPHASE MODEL FOR SIMULATING FLOW, HEAT TRANSFER, AND (formerly Kaiser Engineers). January 1993.139pp.9302010084.
UCRL-iO-110637, 64 726:111.
MASS TRANSPORT IN FRACTURED POROUS MEDIA. User's This report specifies the requirements and cnteria for stress Manual - Version 2.41. RUNCHAL A.K. Analytic & Computional Research, Inc SAGAR.B. Center for Nuclear Waste Regulatory analysis of closure bolts for shipping casks containing nuclear Analyses. February 1993. 221pp 9303120062. CNWRA 92-003.
spent fuels or h#gh level radioactwe materials. The specification b based on existing information conceming the structural be-74240:004.
The PORFLOW software package is designed to simulate havior, analysis, and design of bolted joints. The approach l
taken was to extend the ASME Boiler and Pressure Vessel flow, heat transfer, and mass transport in three-dimensional het.
Code requirements and enteria for bolting analysis of nuclear i
erogenous porous and fractured media. Phase change and gas phase flow is included. Radionuchde decay chains of up to four piping and pressure vessels to include the appropriate design and load characteristics of the shipping cask. The charactens-members can be included in transport analyses. The mathemati.
tics considered are large, flat, closure tids with metal-to-metal cat basis of the model is described in Chapters 2 and 3 the code structure is discussed in Chapters 4 and 5, detailed in, contact within the botted joint; significant temperature and impact loads; and possible prying and bending effects. Specific structions for the user are in Chapter 6, and a few test prob _
formulas and procedures developed apply to the bolt stress lems are in Chapter 7. The PORFLOW is a general purpose software that can be adapted to many d;fferent problems. Ana, analysis of a circular, flat, bolted closure. The report also in-cludes enticalload cases and desirable design practices for the lytic and Computational Research, incorporated of Los Angeles, bolted closure an in-depth review of the structural behavior of CA owns the copynght to the software, however, the U S. Gov.
botted joints, and a comprehensive bibhography of current ir lor.
emment has retained hmited nghts on its use.
mation on bolted joints.
NUREG/CR 5996: SUBSURFACE INJECTION OF RADIOACTIVE TRACERS. Field Expenment For Model Vahdation Testing NUREG/CR-6011: REVIEW OF STRUCTURE DAMPING VALUES FAYER,M.J ; SISSON,J.B.: JORDAN,W A : et al. Battelle Memo-FOR ELASTIC SEISMIC ANALYSIS OF NUCLEAR POWER rial Institute, Pacific Northwest Laboratory. February 1993.50pp.
PLANTS. HASHIMOTO,P.S.; STEELE.L K.; JOHNSON J.J.; et al.
9303120155. PNL-8499. 74234.302.
EOE Engineenng Consultants (formerly EOE Engineenng. inc)
Accurate predictions of the movement of radioactive contami-March 1993. 650pp. 9303300197. 74405:001.
nants from disposal facilities are required to evaluate effects, Current U.S. Nuclear Regulatory Commission guidance on optimize data collection, design remediation strategies, and pre-structure damping values for, elastic seismic design analysis of dict the longterri results of such strategies. A field experiment nuclear power plants a e contained in Regulatory Guide 1.61 was undertaken in 1980 and 1981 to provide data to test the (R.G.161) The obhettves of the study described in this report limits of model predictions. The purpose of this report is to pro-are to investigate the adequacy of R.G.1.61 structure damping vide a complete record of data generated during that field ex-values based on currently availacle data, and to recommend re-penment for use as a model validation test case. The report visions to R G 1.61 as approp4 ate. Measured structure damp-combines the information in Sisson and Lu (1984) with unpub-ing values, and honciated stutture, foundation, excitation, and lished laboratory and field data on the hydrauhc properties of input / response parameteis, were collected and compiled.
i I
Main Citations and Abstracts 13 l
l These data were analyzed to rdentify the parameters that signifs An investigation into the structural properties and seismic re-cantly influence structure damping and to quantify structure sponses of a low aspect ratio shear wall building, which has damping in terms of these parameters. Based on this study, cur.
construction similanty to typical nucioar plant structures, has rent R G.161 damping values for structure design are either been performed using actual recorded earthquake tr,otions. This adequate or require only minor revtsion, depending on the effort used a combination of modal identification to obtain strue.
structure matenal. More explicit guidance on structure damping ture modal parameters directly from the recorded motions, and values for seismic analysis to determine input to equipment has elastic structural analysis using methods and enteria frequently been prepared, along with other recommendations to improve employed by the nuclear industry. Modal parameters determined the applicability of R G.1.61.
by modal identification provide excellent fits to the building mo-tions recorded during the 1984 Morgan Hill earthquake. Modal NUREG/CR A012: ST!FFNESS AND DAMPING PROPERTIES OF parameters identified for the 1989 Loma Prieta earthquake are A LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON more uncertain. Investigation of building stiffnesses generally RECORDED EARTHOUAKE RESPONSES. HASHIMOTO.P S.;
confirms the adequacy of bounding estriates currently recom-TIONG.L.W.; STEELE LK.; et al. ECE Engineenng Consultants mended for nuclear plant structure seismic analysis. Damping va ues identified for this building supplement the database being (formerly EOE Fngineenng, Inc4 March 1991 250pp 9304020300. 74449.001.
c mpiled to investigate current nuclear plant structure damping
- critena,
. ~,.
l i
t 1
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.
l l
SECONDARY REPORT NUMBER REPORT NUMBER SECONDARY REPORT NUMBER REPORT NUMBER AEOD/S92-07 NUREG-1275 V09 LA-12181-MS NUREG/CR-5755 ANL-91/43 NUREG/CR-5822 ME A-2490 NUREG/CR-5926 hAhC
/R(92)3 NL {
-02 BNL NUREG-52299 NUREG/CR-5783 BNL-NUREG-52318 NUREG/CR-5844 ORNL-6731 NUREG/CR-5938 BNL-NUREG-52330 NUREG/CR-5883 ORNL 6740 NUREG/CR-5914 BNL-NUREG-52334 NUREG/CR-5911 ORNL/TM-12179 NUREGICA 5922 BNL NUREG-52343 NUREG/CR-5933 ORNL/TM-12247 NUREG/CR-5952 BNL-NUREG 52344 NUREG/CR-5934 PNL-4221 NUREG/CR-2850 Vi t BNL-NUREG-52352 NUREG/CR-5959 PNL 7187 NURE G/CR-5468 BNL/NUREG-52029 NUREG/CR-4551V7AIP2B PNL 7609 NUREG/CR-5766 h#
BNLINUREG-52029 NUREG/CR-4551 V7 RIP 1 f
BNL/NUREG-52029 NUREG/CR-4551V7 RIP 2A PNL-7925 NUREG/CR-5835 CDNSWCSMECR1692 NUREG/CR 5958 PNL-8105 NUREG/CR-5898 CEERC-91-105 NUREG/CR-5956 PNL-8454 NUREG/CR-5247 V01 R1 CNWRA 92-003 NUREG/CR-5991 PNL-8462 NURE GICR-5973 CNWRA91410 NUREG/CR-5917 V02 PNL-8466 NUREG/CR-5975 CNWRA91-010 NUREG/CR-5917 V01 PNL 8480 NURE G/CR-5988 EGG-2577 NUREG/CR-5229 VOS PNL-8496 NUREG/CR-5998
$9 EGG-2635 NUREG/CR-5672 V03 1536 EGG-2665 NUREG/CR-5818 SAND 92-0538 NUREG/CR-5863 EGG-2690 NUREG/CR 5953 SAND 92-1721 NUREG/CR-5961 EGG-2692 NUREG/CR-5964 SAND 92-2109 NUREG /CR-5936 EGG-2695 NUREG/CR-5987 UCRL-ID 110637 NUREG/CR-6007 IS 4878 NUREG/CR-4273 UILU ENG92-4007 NUREG/CR-5977 15
1 f
I
_m.
1 1
(
t i
i Personal Author Index This index lists the personal authors of NRC staff, contractor, and international agreement reports in alphabetical order. Each name is followed by the NUREG number and the title of the report (s) prepared by the author. If further information is needed, refer to the main cita-
]-
tion by the NUREG number.
]
ADO EID.R.
CADY.R.E.
NUREG-1476 DR AFT ENVIRONMENTAL IMPACT STATEMENT TO NUREG/CR $988 SOIL CHAR ACTERt2ATION METHODS FOR UN-i.
CONSTRUCT AND OPERATE A F ACILITY TO RECEIVE. STORE.
SATURATED LOW-LEVEL WASTE SITES AND D!SPOSE OF 11E C) BYPRODUCT MATERIAL NEAR CLIVE.
UTAH. Docket No 40-8989. Enwocare Of Utan. Inc C AMP,A.L.
NUREG/CR 5936-ENHANCEMENTS TO THE ACCIDENT PRECURSOR A K E R S,0.W.
METHODOLOGY.
NUREG/CR 5672 V03 CHARACTERiST.CS OF LOW-LEVEL RADIOAC.
i TlVF MFQ'%iTAM! NATION WASTE Annual Report for Fiscal Year CAZZOLI.E.
1932 NUREG/CR-4551 V7AIP1 EVALUATION OF SEVERF ACCIDE NT RISKS. ZION UNIT 1. Main Report ALLENSPACH,F.
NUREG/CR4551V7 RIP 2A. EVAL UATION OF SEVERE ACCIDENT NUREG-1214 R11 HISTORfCAL DATA
SUMMARY
OF THE SYSTEMAT-RISKS ZION UN;T 1.Appenda A.
lC ASSESSMENT OF LICENSEE PERFORMANCE NUREG/CR-45t ;V7R1P2B EVALUATION OF SEVERE ACCIDENT ATH E Y.G.F.
NUREG/CR-5247 V01 R1 RASCAL VERSION 2.0 USER'S GUIDE CLEVELAND,J.C, NUREG/CR 5922 MODULAR HiGH-TEMPERATURE GAS-COOLED RE-ATWOOD,C.L ACTOR SHORT-TERM THERMAL RESPONSE TO FLOW AND REAC-NUREG/CR-5964 SAPH;RE TECHNICAL REFERENCE MANUAL 1ARAS/ SARA VERSION 4 0 TIVITY TRANSIENTS 4
B AKE R.D. A.
CODELL,R.B.
NUREG/CR-2850 VII. DOSE COMMITMENTS DUE TO RADIOACTIVE NUREG/CR 5917 VOI: SENSITIVITY AND UNCERTAINTY ANALYSES RELEASES FROM NUCLEAR POWER PLANT SITES IN 1989 APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A LAYERED FRACTURED ROCK.MULTFRAC - Analytic Solutions And BAKER.W.E.
Local Sensibvitres NUREG!CR-5755 STIFFNESS OF LOW-ASPECT RATIO REINFORCED NUREG/CR-5917 V02. SENSITIVITY AND UNCERTAINTY ANALYSES CONCRETE SHEAR WALLS APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A LAYERED FRACTURED ROCK Evaluabon Of The Lmt State Ap-BAUM J.W.
proach NUREG /CR-5883 HEALTH RISK ASSESSMENT OF IRRAD4ATED TOPA2 COSTANTINO.C.J.
NUREG/CR-5956. CONSIDERATION OF UNCERTAINTIES IN SOll-BEAVEN.P.A ONANNS NUREG/CR 5926 SANS INVESTIGATION OF LOW ALLOY STEELS IN NEUTRON IRRADIATED. ANNEALED. AND REIRRADIATED CONDI-COWGILL M.G.
TIONS NUREG/CR-5911: SOURCE TERM EVALUATION FOR RADIOACTIVE LOW-LEVEL WASTE DISPOSAL PERFORMANCE ASSESSMENT.
BECK,J L NUREG/CR-6012 STIFFNESS AND DAMPING PROPERTIES OF A CRAMOND,W.R LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD' NUREG/CR-5863. RISK ASSESSMENT OF ISOLATION DEVICES IN ED EARTHOUAkE RESPONSES SAFETY SYSTEMS.
BLUHM.D.
N G/GR-5791 RISK EVALUATION FOR A GENERAL ELECTRIC OF SE U HC AIN T
BWR. EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON BOHNHOFF,W.J.
SAFETY-RELATED EOUIPMENT, Evaluation Of Genenc issue 57 NUREG/CR-5936 ENHANCEMENTS TO THE ACCIDENT PRECURSOR METHODOLOGY.
DI AS,M.P.
NUREG/CR 5951. THE MANAGEMENT OF ATWS BY BORON INJEC-BROCK,R.
TION NUREG/CR 5977. A PERFORMANCE INDICATOR OF THE EFFECTIVE.
NESS OF HUMAN-MACHINE INTERFACES FOR NUCLEAR POWER DINGMAN,S.E.
PLANTS NUREG/CR 5936 ENHANCEMENTS TO THE ACCIDENT PRECURSOR METHODOLOGY.
BRUMMETT.E.
NUREG.1476 DRAFT ENVIRONMENTAL IMPACT STATEMENT TO DJEMIL,T.
CONSTRUCT AND OPERATE A FACILITY TO RECEIVE. STORE.
NUREG/CR-5977; A PERFORMANCE INDICATOR OF THE EFFECTIVE-AND DISPOSE OF 11E (2) BYPRODUCT MATERIAL NEAR CLIVE, NESS OF HUMAN MACHINE INTERFACES FOR NUCLEAR POWER UTAH Docket No 40-8969 Envnocare Of Utah. Inc.
PLANTS BUMG ARDNE R.J.D.
ELLIOTT,D B.
tVUREG/CR 5766. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-NUREG/CR-5975 INCENTIVE REGULATION OF INVESTOR-OWNED SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULATORS POWER PLANT NUREG/CR-5836 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN.
F AIN,R.E.
SPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWER NUREG/CR-5851 LONG TERM PERFORMANCE AND AGING CHAR-PLANT ACTERfSTICS OF NUCLEAR PLANT PRESSURE TRANSMITTERS.
17
I l
I l
l l
18 Personal Author index l
FANOUS,F.
GROVE.E.
NUREG/CR 4273 CRACK PROPAGATION IN HIGH STRAIN REGIONS NUREG/CR 5783 AGING ASSESSMENT OF THE COMDUSTION ENGI-OF SEQUOY AH CONT AINMENT, NEERING AND BABCOCK & WILCOX CONTROL ROD DRIVES FARR AR C.R.
GUNTHER.W.
NUREG/CR.5755 STlFFNESS OF LOW. ASPECT RATIO, REINFORCED NUREG/CR 5783. AGING ASSESSMENT OF THE COMBUSTION ENGb CONCRETE SHEAR WALLS NEERING AND BABCOCK & WILCOx CONTROL ROD DRIVES NUREG/CR 5933 HIGH PRESSURE COOLANT INJECTION (HPCI) b[R P NUR G/CR-5996 SUBSURFACE INJECTION OF RADIOACTIVE W RS TO U 2 ND TRACERS Field Expenment For Model Valedation Testing NUREG/CR-5934. HIGH PRESSURE COOLANT INJECTION (HPCI)
FISCHER LE.
SYSTEM RISK-BASED INSPECTION GUIDE FOR OUAD-CITIES NUREGICR 7 STRESS ANALYSIS OF CLOSURE BOLTS FOR NURE /CRS 9 HG PRESSURE COOLANT INJECTION (HPCI)
SYSTEM RISK BASED INSPECTION GUIDE FOR ENRICO FERMI FRANCIS,A.A.
ATOMIC POWER PLANT. UNIT 2.
NUREG/CR-5938 NATIONAL PROFILE ON COMMERCIALLY GENER-ATED LOW-LEVEL RADIOACTIVE M!xED WASTE GUREGHIAN,A.B.
NUREG/CR-5917 V01: SENSITIVITY AND UNCERTAINTY ANALYSES FRlSIUS,F, APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A NUREG/CR-5926 SANS INVESTIGATION OF LOW ALLOY STEELS IN LAYERED FRACTURED ROCK:MULTFRAC - Analytic Solutions And NEUTRON IRRADIATED ANNEALED, AND REIRRADIATED CONDI-Local Sensitmties TIONS NUREG/CR-5917 V02: SENS!TIVITY AND UNCERTA!NTY ANALYSES APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A
[
GARDNER W.R.
LAYERED FRACTURED ROCK. Evaluation Of The Limst State Ap-NUREG/CR-5980. THREE D!MENSf0NAL REDISTRIBUTION OF TRITI-proach.
UM FROM A POINT OF RELEASE INTO A UNIFORM UNSATURATED SOIL.A Deterministec Model For Tntium Migration in An Ard Disposal HACKBARTH.H.
Sde-NUREG/CR 5926. SANS INVESTIGATION OF LOW ALLOY STEELS IN NEUTRON IRRADIATED. ANNEALED. AND REIRRADIATED CONDI-G AUT A M,A.S.
TIONS.
NUREG-1473 ELECTRICAL DISTRIBUTION SYSTEM FUNCTIONAL tN-SPECTION (EDSF1) DATA BASE PROGRAM HAGEMEYER,0.
GEE G.W NUREG-0713 V12; OCCUPATIONAL RADIATION EXPOSURE AT COM-NbREG/CR 5988. SOIL CHARACTERtZATION METHODS FOR UN-
^ " " " * ' #
SATURATED LO4 LEVEL WASTE SITES GHAN.LS.
HAMDAN,L NUREG/CR-5818 UNCERTAINTY ANALYSIS OF MINIMUM VESSEL NUREG-1476 DRAFT ENVIRONMENTAL IMPACT STATEMENT 1")
LIQUlO INVENTORY DURING A SMALL-BREAK LOCA IN A B&W CONSTRUCT AND OPERATE A FACfLITY TO RECEtVE, STORE, PLANT AN APPLICATION OF THE CSAU METHODOLOGY USING AND DISPOSE OF 11E.(2) BYPRODUCT MATERIAL NEAR CLIVE, THE RELAP5/ MOD 3 COMPUTER CODE UTAH Docliet No 40-8989 Enwocare Of Utah. Inc.
GOR E,B.F.
HAMILTON,M.A.
NUREG/CR-5488 RISK-BASED INSPECTION GUIDE FOR THREE MILE NUREG/CR-5987 MICROBIAL-INFLUENCED CEMENT DEGRADATION ISLAND NUCLEAR STATION UNIT 1
- LITERATURE REVIEW NUREG/CR-5766 AUXILIARY FEEDWATER SYSTEM RISK. BASED IN-SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR HAMM ER.J.A.
POWER PLANT NUREG/CR 5973 CODES AND STANDARDS AND OTHER GUIDANCE NUREG/CR 5834 AUxlLIARY FEEDWATER SYSTEM RISK-BASED IN.
CITED IN REGULATORY DOCUMENTS SPECTION GUIDE FOR THE FORT CALHOUN NUCLEAR POWER PLANT.
HARRISON.D.G.
NUREG/CR 5835 aux!LIARY FEEDW ATER SYSTEM ntSK-BASED IN-NUREG/CR 5488: RISK-BASED INSPECTION GUIDE FOR THREE MILE SPECTION GUIDE FOR THE BEAVER VALLEY. UNITS 1 AND 2 NU-ISLAND NUCLEAR STATION UNIT 1.
CLEAR POWER PLANTS NUREG/CR 5836 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-HARTFIELD,R.A.
SPECTION GUIDE FOR THE PALO VERDE HUCLEAR POWER NUREG-0020 V17: LICENSED OPERATING REACTORS STATUS SUM PLANT.
MARY REPORT. Data As Of December 31,1992 (Gray Book l}
NUREG/CR 5898 AUXILIARY FEEDWATER SYSTEM RISK. BASED IN-l SPECTION GUIDE FOR THE POINT BEACH NUCLEAR POWER H ASHE MIAN.H.M.
PLANT.
NUREG/CR-5851: LONG TERM PERFORMANCE AND AGING CHAR-ACTERISTICS OF NUCLEAR PLANT PRESSURE TRANSMITTERS R
R VE EC IS S OR BWR NU EA P NS E P TS GREIMANN,L.
HASHIMOTO P.S NUREG/
273 C K R PAGATION IN HIGH STRAIN REGIONS NUREG/CR-6011: REVIEW OF STRUCTURE DAMPING VALUES FOR i
ELASTIC SEISMIC ANALYSIS OF NUCLEAR POWER PLANTS GRIMES.B.K.
NUREG/CR-6012: STlFFNESS AND DAMPING PROPERTIES OF A NUREG/CP-0128 PROCEEDINGS OF THE INTERNATIONAL WORK-LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD-SHOP ON THE CONDUCT OF INSPECTIONS AND INSPECTOR ED EARTHOUAKE RESPONSES.
QUALIFICATION AND TRAINING HAWTHORNE,J.R.
GRIMSHAW.C.
NUREG/CR-5926 SANS INVESilGATION OF LOW ALLOY STEELS IN NUREG/CR-4551 V7RtP1: EVALUATION OF SEVERE ACCIDENT NEUTRON IRRADIATED. ANNEALED, AND REIRRADIATED CONDL RISKS ZION UNIT 1 Main Report TIONS.
NUREGICR-4551V7R1P2A EVALUATION OF SEVERE ACCIDENT RISKS ZION UNIT 1. Appendix A.
HELLER.P.R.
NUREG/CR 4551V7 RIP 28-EVALUATION OF SEVERE ACCIDENT NUREG/CR-5996: SUBSURFACE INJECTION OF RADIOACTIVE RISKS ZION UNIT 1 Appendices B. C, D, And E.
TRACERS Field Expenment For Model Vahdation Testing
Personal Author index 19 HERNAN.R.W.
LE E,M.
NUREG/CR 5488 RISK-BASED INSPECTION GUIDE FOR THREE MILE NUREG /CR-4551 V7 RIP 1 EVALUATION OF SEVERE ACCIDENT ISLAN" NUCLE AR STATION UNIT 1 RISKS ZION UN11 1 Main Report.
HILL,S.G.
NUREG/CR-4551V7R1P2A-EVALUATION OF SEVERE ACCIDENT NUREGICR 5953. STUD!ES OF HUMAN PERFORMANCE DURING OP-RISKS ZION UNIT 1. Appendix A NUREG/CR 4551V7 RIP 2B EVALUATION OF SEVERE ACCIDENT ERATING EVENTS.1990-1992 RISKS. ZION UNIT 1 Appendices B. C. D. And E.
HILLS.R.G.
^
NURh CR-5835-AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SATU ATE LOW VEL S ES SPECTION GUIDE FOR THE BEAVER VALLEv UNITS 1 AND 2 NU-4 HSU.C.
CLEAR POWER PLANTS i
NUREG-12 V09 OPERATING EXPERIENCE FEEDBACK REPORT.
NUREG/CR-5898. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-PRESS'. nE LOCKING AND THERMAL BINDING OF GATE SPECTION GUIDE FOR THE POINT BEACH NUCLEAR POWER VALVES Commercial Power Reactors PLANT.
HSU.S.T.
LOBEL,R.
NUREG/CR.6007. STRESS ANALYSIS OF CLOSURE BOLTS FOR NUREG-1366. IMPROVEMENTS TO TECHNICAL SPECIFICATIONS SHIPPING CASKS SURVEILLANCE REOUiREMENTS.
f JASTROWAD-LU.A.H.
l NUREG/CR-5229 VOS FIELD LYSIMETER INVESTIGATIONS. LOW-NUREG/CR 5996 $UBSURFACE INJECTION OF RADIOACTIVE l
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR FISCAL YEAR 1992 Annual Report TRACERS Field Expenment For Model Vahdation Testing i
I MAGUIRE-MOFFITT tUAEG/
-6011: REVIEW OF STRUCTURE DAMPlNG VALUES FOR NUREG/CR-5973 CODES AND STANDARDS AND OTHER GUIDANCE l
ELASTIC SEISMIC ANALYSIS OF NUCLEAR POWER PLANTS CITED IN REGULATORY DOCUMENTS.
NUREG/CR-6012. STlFFNESS AND DAMPING PROPERTIES OF A l
LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD, MCCABE.D.E.
f ED EARTHOUAKE RESPONSES NUREG/CR-5914 CHEMICAL COMPOSITION AND RT(NDT) DETERMI-NATIONS FOR MIDLAND WELD WF-70.
JOHNSON.T.
NUREG/CR 5952: EVALUATION OF CRACK POP. INS AND THE DE.
NUREG-1476 DRAFT ENVIRONMENTAL lMPACT STATEMENT TO TERMINATION OF THEIR RELEVANCE TO DESIGN CONSIDER.
CONSTRUCT AND OPERATE A FAClllTY TO RECEIVE STORE, ATIONS AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL NEAR CLIVE, UTAH Docket No 40 8989,Envirocare Of Utah. Inc.
MCCONNE LL,J.W.
NUREG/CR-5229 VOS FIELD LYSIMETER INVESTIGATIONS: LOW-JOLLEY,R.L LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR l
NUREG/CR 5930: NATIONAL PROFILE ON COMMERCIALLY GENER-FISCAL YEAR 1992 Annual Report.
i ATED LOW-LEVEL RADIOACTIVE M!XED WASTE NUREG/CR-5672 V03. CHARACTERISTICS OF LOW-LEVEL RADIOAC.
JONES.B.J.
nual W 6 Beal War 97 NUREG/CR-5977 A PERFORMANCE INDICATOR OF THE EFFECTIVE-NUREG/CR-5987: MICROBIAL INFLUENCED CEMENT DEGRADATION NESS OF HUMAN, MACHINE INTERFACES FOR NUCLEAR POWER PLANTS
- LITERATURE REVIEW JORDAN W.A MCKENNA.T.J.
NUREd/CRl5996 SUBSURFACE INJECTION OF RADIOACTIVE NUREG/CR 5247 V01 R1 RASCAL VERSION 2.0 USER'S GUIDE.
TRACERS.Feeld Expenment For Model Va!idation Testing MCKINNEY,M.D.
RAMPM ANN R.
NUREG/CR-5975 INCENTIVE REGULATION OF INVESTOR. OWNED NUREG/CR-5926 SANS INVESTIGATION OF LOW ALLOY STEELS IN NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULATORS.
NEUTRON IRRADIATED. ANNEALED, AND REIRRADIATED CONDI-y g
NUREG-0837 V12 N04 NRC TLD DIRECT RADIATION MONITORING MINCAID.C.T.
NETWORK Progress Report October December 1992 NUREG/CR-59BB SOIL CHARACTER 12ATION METHODS FOR UN-SATURATED LOW-LEVEL WASTE SITES MENSING R.W.
l NUREG/CR-6011: REVIEW OF STRUCTURE DAMPING VALUES FOR i
MLAMERUS.E-ELASTIC SEISMIC ANALYSIS OF NUCLEAR POWER PLANTS.
[
NUREG/CR-5791 RISK EVALUATION FOR A GENERAL ELECTRIC BWR. EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON MEYER,O A SAFETY.RELATED EQUIPMENT Evaluation Of Genenc issue 57.
NUREG/CR-5953 STUDIES OF HUMAN PERFORMANCE DURING OP.
ERATING EVENTS.1990-1992.
NUREG/CR-5938 NATIONAL PROFILE ON COMMERCIALLY GENER-MILLER.C.A.
ATED LOW-LEVEL RADIOACTIVE MlXED WASTE-NUREG/CR-5956: CONSIDERATION OF UNCERTAINTIES IN SOIL-LAMBE RT.L.D.
STRUCTURE INTERACTION COMPUTATIONS I
NUREG/CR 5961 POSTTJST DESTRUCTIVE EXAMINATION OF THE MILLER.M.K.
STEEL LINER IN A 16-SCALE RE ACTOR CONTAINMENT MODEL.
NUREG/CR-5914. CHEMICAL COMPOSITION AND RT(NDT) DETERMi-LAMBRIGHT.J.
NATIONS FOR MIDLAND WELD WF.70 NUREG/CR-5791. RISK EVALUATION FOR A GENERAL ELECTRIC BWR, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON MILLER.S.P.
SAFETY-RELATED EOU!PMENT. Evaluation Of Genenc issue 57.
NUREG/CR.5863 RISK ASSESSMENT OF ISOLATION DEVICES IN SAFETY SYSTEMS LEE,B.S.
NURE G /CR-5844 AGING ASSESSMENT OF BIST ABLE$ AND MITCHELL,D.B.
SWITCHES IN NUCLEAR POWER PLANTS NUREG/CR 5863 AISK ASSESSMENT OF ISOLATION DEVICES IN SAFETY SYSTEMS.
LEEA D.
NUREG/CR-5977-A PERFORMANCE INDICATOR OF THE EFFECTIVE.
MITCHELL.D.W.
NESS OF HUMAN-MACHINE INTERFACES FOR NUCLEAR POWER NUREG/CR 5851. LONG TERM PERIORMANCE AND ACONG CHAR.
PLANTS ACTERISTICS OF NUCLEAR PLANT hvSCORE TRANSM.TTERS
20 Personal Author Index NUREGICR 5903. VAUDATION OF SMART SENSOR TECHNOLOGIES NUREG/CR-4551V7 RIP 2A: EVALUATION OF SEVERE ACCIDENT FOR INSTRUMENT CAllBRATION FIEDUCTION IN NUCLEAR RISKS. ZION UNIT 1. Appendix A.
POWER PLANTS.
NUREG/ CR-4551V7R 1 P28. EVALUATION OF SEVERE ACCIDENT AlSKS: ZION UNIT 1. Appendices B, C, D, And E.
MOFFITT,N.E.
NUREG/CR 5488 RISK-BASED INSPECTION GUIDE FOR THREE MILE PETERSEN K.M.
ISLAND NUCLE AR STATION UNIT 1.
NUREG/CR-5851: LONG TERM PERFORMANCE AND AGING CHAR.
NUREG/CR-5766 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-ACTERISTICS OF NUCLEAR PLANT PRESSURE TRANSMITTERS SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR NUREG/CR-5903 VALIDATION OF SMART SENSOR TECHNOLOGIES POWER PLANT.
FOR INSTRUMENT CALIBRATION REDUCTION IN NUCLEAR NUREG/CR 5834. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-POWER PLANTS SPECTION GUIDE FOR THE FORT CALHOUN NUCLEAR POWER PLANT.
PR ATT,W,T.
NUREG/CR-5835 AUXILIARY FEEDWATER SYSTEM RISK BASED IN.
NUREG/CR-4551 V7R1P1. EVALUATION OF SEVERE ACCIDENT SPECTION GUIDE FOR THE BEAVER VALLEY. UNITS 1 AND 2 NU-RISKS ZION UNIT 1 Main Report.
CLEAR POWER PLANTS NUREG/CR 4551V7R1P2A. EVALUATION OF SEVERE ACCIDENT NUREG/CR-5836. AUxlLIARY FEEDWATER SYSTEM RISK BASED IN-RISKS. ZION UNIT 1. Appendix A.
SPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWER NUREG/CR 4551V7 RIP 28. EVALUATION OF SEVERE ACCIDENT PLANT.
RISKS-ZION UNIT 1. Appendices B, C, D. And E NUREG/CR-5898 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SPECTION GUIDE FOR THE POINT BEACH NUCLEAR POWER PUGH.R.
PLANT-NUREG/CR-5766: AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR NUR G'/CR-6007: STRESS ANALYSIS OF CLOSURE BOLTS FOR SHIPPING CASKS RADDATZ,C.T.
NUREG-0713 Vt2; OCCUPATIONAL RADIATION EXPOSURE AT COM-URE'G CR-5977. A PERFORMANCE INDICATOR OF THE EFFECTIVE-MERCIAL NUCLEAR POWER REACTORS AND OTHER FACILITIES.1990. Twenty-Third Annual Report NESS OF HUMAN-MACHINE INTERFACES FOR NUCLEAR POWER RAMSDELL J.V.
NUREG/CR 5247 V01 R1: RASCAL VERSION 2.0 USER'S GUIDE.
MORCOS.N.
NUREG/CR-5672 V03: CHARACTERISTICS OF LOW-LEVEL RADIOAC-TiVE DECONTAMINATION WASTE Annual Report For Fiscal Year NUREG C" 5964 SAPHIRE TECHNICAL REFERENCE R
MANUAL:lRRAS/ SARA VERSION 4.0.
MROCHEK,J E.
NUREG/CR-5938 NATIONAL PROFILE ON COMMERCIALLY GENER.
RASMUSSEN.J.
NUREG/CR-5977: A PERFORMANCE INDICATOR OF THE EFFECTIVE-ATED LOW-LEVEL RADIOACTIVE MIXED WASTE.
NESS OF HUMAN MACHINE INTERFACES FOR NUCLEAR POWER MULLINSA PLANTS NUREG-1476 DRAFT ENVIRONMENTAL IMPACT STATEMENT TO CONSTRUCT AND OPERATE A FACILITY TO RECEIVE, STORE, ROCKHOLD.ML AND DISPOSE OF 11E(2) BYPRODUCT MATERIAL NEAR CLIVE, NUREG/CR-5998. SIMULATION OF UNSATURATED FLOW AND NON-UTAH Drrket No 40-8989 Envirocare Of Utah, Inc.
REACTIVE SOLUTE TRANSPORT IN A HETEROGENEOUS SOIL AT l
THE FIELD SCALE.
NANSTAD,R.K.
NUREG/CR-5914 CHEMICAL COMPOSITION AND RT(NDT) DETERMi-ROGFRS.R D, NATIONS FOR MIDLAND WELD WF 70.
NUREG/CR-5229 V05 FIELD LYSIMETER INVESTIGATIONS LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NELSON.K.
FISCAL YEAR 1992. Annual Report.
NUREG/CR 5883 HEALTH RISK ASSESSMENT OF IRRADIATED NUREG/CR-5987. MICROBIAL-INFLUENCED CEMENT DEGRADATION TOPAZ.
LITERATURE REVIEW.
NICHOLSON.T.J.
ROSS S.
NUREG/CR 5988-SOIL CHARACTERIZATION METHODS FOR UN~
NUREG/CR 5791: RISK EVALUATION FOR A GENERAL ELECTRIC SATURATED LOW-LEVEL YvASTE SITES BWR, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON NICKOLAUS.J.R.
NUREG/CR-5973: CODES AND STANDARDS AND OTHER GUIDANCE kOS$ BACH.LW, CITED IN REGULATORY DOCUMENTS.
NUREG/CR-5835: AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SPECTION GUIDE FOR THE BEAVER VALLEY, UNITS 1 AND 2 NU.
NUSSBAUMER.D.
CLEAR POWER PLANTS.
NUREG/CR-5962: HEALTH AND SAFETY IMPACTS FROM DISCRETE SOURCES OF NATURALLY OCCURRING AND ACCELERATOR PRO-DUCED RADIOACTIVE MATERIALS (NARM)
UR C 991: PORFLOW: A MULTIFLUID MULTIPHASE MODEL O'DOWD,N.P.
FOR SIMULATING FLOW, HEAT TRANSFER, AND MASS TRANS-NUREG/CR-5958 TWO-PARAMETER FRACTURE MECHANICS:
PORT IN FRACTURED POROUS MEDIA. User's Manual Version THEORY AND APPLICATIONS.
2.41.
ORTIZ,M.G.
RUSSELL,K.D.
NUREG/CR-5818. UNCERTAINTY ANALYSIS OF MINIMUM VESSEL NUREG/CR-5964.
SAPHIRE TECHNICAL REFERENCE LIOUlO INVENTORY DURING A SMALL-BREAK LOCA IN A B&W MANUAL:lRRAS/ SARA VERSION 4 0.
PLANT-AN APPLICATION OF THE CSAU METHODOLOGY USING 8 AGAR, THE RELAPS/ MOD 3 COMPUTER CODE.
NU OSBORNE LEEJ.
APPLIED TO ONE DIMENSIONAL RADIONUCLlDE TRANSPORT IN A NUREG/CR-5938: NATIONAL PROFILE ON COMMERCIALLY GENER.
LAYERED FRACTURED ROCK.MULTFRAC Analytic Solutions And ATED LOW-LEVEL RADIOACTIVE MIXED WASTE.
Local Sensitivities NUREG/CR 5917 V02: SENSITIVITY AND UNCERTAINTY ANALYSES P ARK.C.K.
APPLIED TO ONE-DIMENSf0NAL RADIONUCLIDE TRANSPORT IN A NUREG/CR-4551 V7R1P1: EVALUATION OF SEVERE ACCIDENT LAYERED FRACTURED ROCK Evaluation Of The Limit State Ap-RISKS: ZION UNIT 1. Main Report.
proach
N l
Personal Author index 21 NUREG/CR 5991 PORFLOW. A MULTIFLUID MULTIPHASE MODEL SURMElER.J.
FOR SIMULATING FLOW. HEAT TRANSFER. AND MASS TRANS-NUREG-1476 DRAFT ENVIRONMENTAL IMPACT STATEMENT TO PORT IN FRACTURED POROUS MEDIA User's Mawl - Versson CONSTRUCT AND OPERATE A F ACILITY TO RECEIVE. STORE, 24L AND DISPOSE OF ItE (2) BYPRODUCT MA1ERIAL NEAR CLIVE, UTAH Docket No 40 8969. Enwocare Of Utah,Inc NUREG/CR-5964 SAPHIRE TECHNICAL REF ERENCE SWAIN,R L MANUAL 1RRAS/ SARA VERSION 4.0-NUREG/CR-5914 CHEMICAL COMPOSITION AND RT(NDT) DETERML SCHULZ.R.K.
NUREG/CR-5980 THREE DIMENSIONAL REDISTRIBUTION OF TRIT!*
THEOFANOUS.T.G.
UM FROM A POINT OF RELEASE iNTO A UNIFORM Ut' SATURATED NUREG/CR 5951 THE MANAGEMENT OF ATWS BY BORON INJEC-SOIL A Deterministic Model For Tntium Mgation in An And Disposal TION Site.
TINGLE A.
N RE /CR-5835 AUXtLIARY FEEDWATER SYSTEM RISK-BASED IN-R SKS Z O N1 1 r5 Re 1 SPECTION GUIDE FOR THE BEAVER VALLEY UNITS 1 AND 2 NU-NURE G/CR4551V7R1P2A: EVALUATION OF SEVERE ACCfDENT CLEAR POWER PLANTS giggs. ZION UNIT 1.Appenda A.
NUREG /CR455 t V7 RIP 2B EVALUATION OF SEVERE ACCIDENT NU EGrCR-5822-ANALYSIS OF THERMAL M!XING AND BORON Dl-LUTION IN A PWR TIONG LW.
NUREG/CR-6012 STIFFNESS AND DAMPING PROPERTIES OF A LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD-NUREG R-5903-VALIDATION OF SMART SENSOR TECHNOLOGIES ED E ARTHOUAKE RESPONSES FOR INSTRUMENT CAllBRATION REDUCTION IN NUCLEAR POWER PLANTS TJ ADER,T.R.
NUREG-1366. IMPROVEMENTS TO TECHNICAL SPECtFICATIONS SHERFEY,LL SURVEl' LANCE REQUIREMENTS NUREG/CR-5973 CODES AND STANDARDS AND OTHER GUIDANCE CITED IN REGUL ATORY DOCUMENTS TRAVIS.R.
SHIER.W.
NUREG/CR 5934: HIGH PRESSURE COOLANT INJECTION (HPCI)
SYSTEM RISK-BASED INSPECTION GUIDE FOR OU AD-CITIES NUREG1CR 5933 HIGH PRESSURE COOLANT INJECTION (HPCI)
SYSTEM RISK-BASED INSPECTION GUIDE FOR DRESDEN NUCLE.
STATION.UNtTS 1 AND 2 AR POWER STATION UNITS 2 AND 3.
NUREG/CR 5959 HIGH PRESSURE COOLANT INJECTION (HPCl)
SYSTEM RISK-BASED INSPECTION GUIDE FOR ENRICO FERMI SHlH.C.F.
ATOMIC POWER PLANT. UNIT 2 NUREG/CR-5958 TWO-PARAMETER FRACTURE MECHANICS-THEORY AND APPLICAllONS.
VEMEC.T.A.
NUREG/CR-5834. AUXlLIARY FEEDWATER SYSTEM RISK-BASED IN-SISSON.J.B.
SPECTION GUIDE FOR THE FORT CALHOUN NUCLEAR POWER NUREG/OR-5996. SUBSURFACE INJECTION OF RADIOACTIVE PLANT.
TRACERS Field Expenment For Model Validation Testing NUREG/CR-5835: AUXILIARY FEEDWATER SYSTEM RISK. BASED IN-SPECTION GUIDE FOR THE BEAVER VALLEY, UNITS 1 AND 2 NU-SJOREEN.A.L CLEAR POWER PLANTS NUREG/CR 5247 VC1 R1; RASCAL VERSION 2.0 USER S GUIDE.
NUREG/CR-5899 AUXILIARY FEEDWATER SYSTEM RISK BASED IN-SLOAN.J.A.
NUREG/CR4B36 AUXILIARY FEEDWATER SYSTEM RISK BASED IN-SPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWER VICENTE,K.J.
PLANT.
NUREG/CR-5977. A PERFORMANCE INDICATOR OF THE EFF ECTIVE-NESS OF HUMAN MACHINE INTERCACES FOR NUCLEAR POWER SMILESM l
NUREG/CR-5960 THREE DrMENSIONAL REDISTRIBUTION OF TRITI-UM FROM A POINT OF RELEASE !NTO A UNIFORM UNSATURATED VILLARAN,M.
SOIL A Deterministic Model For Tntium Migration in An Arid Disposal NUREG/CR 5644. AGING ASSESSMENT OF BISTABLES AND Site SWITCHES IN NUCLEAR POWER PLANTS NUREG/CR-5933 HIGH PRESSURE COOLANT INJECTION (HPCI)
[R
^
NUR CR-6011 REVIEW OF STRUCTURE DAMPING VALUES FOR EA STAT O UN TS 2 D3 ELASTIC SEISMIC ANALYSIS OF NUCLEAR POWER PLANTS NUREG/CR-5934 HIGH PRESSURE COOLANT INJECTION (HPCI)
NUREG/CR-6012: STIFFNESS AND DAMPING PROPERTIES OF A SYSTEM RISK-BASED INSPECTION GUIDE FOR QUAD-CITIES LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD-STATION UNITS 1 AND 2 ED EARTHOUAKE RESPONSES I
NUREG/CR 5959 HIGH PRESSURE COOLANT INJECTION (HPCI)
STEINKE,W.F.
SYSTEM RISK-BASED INSPECTION GUIDE FOR ENRICO FERMI NUREG/CR-5953 STUDIES OF HUMAN PERFORMANCE DURING OP-ATOMIC POWER PLANT. UNIT 2.
ERATING EVENTS 19901992.
VINTHER.R.W.
STRUCKME YER,R.
NUREG/CR-5973 CODES AND STANDARDS AND OTHER GUIDANCE NUREG-0B37 V12 N04 NRC TLD DIRECT RADIATION MONITORING CITED IN REGULATORY DOCUMENTS NETWORK Progress Report. October-December 1992 VRTX SUBUDHl.M.
NUREG/CR-5488: RISK-BASED INSPECTION GUIDE FOR THREE MILE NUREG/CR-5644: AGING ASSESSMENT OF BISTABLES AND ISLAND NUCLEAR ST ATION UNIT 1.
SWITCHES IN NUCLEAR POWER PLANTS NUREG/CR-5766: AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR SULLIVAN,T.M.
POWER PLANT.
NUREG/CR 5911 SOURCE TERM EVALUATION FOR RADIOACTIVE NUREG /CR-5834 AUXILIARY FEEDWATER SYSTEM RISK BASED IN-LOW LEVEL WASTE DISPOSAL PERFORMANCE ASSESSMENT.
SPECTION GUIDE FOR THE FORT CAlHOUN NUCLEAR POWER PLANT.
SUN.J.G.
NUREG/CR 5835: AUXlLIARY FEEDWATER SYSTEM RtSK-BASED N-NUREG/CR-5822. ANALYSIS OF THERMAL MixlNG AND BORON DI-SPECTION GUIDE FOR THE BEAVER VALLEY UNITS 1 AND 2 NU-LUTION IN A PWR.
CLEAR POWER PLANTS
22 Personal Author index NUREG'CR-5836 AUML!ARY FEEDWATER SYSTEM RISK-BASED IN.
WICKLIFF.D.S.
SPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWE R NUREG/CR 5229 VOS FIELD LYS(ME TER INVE STIGATIONS LOW-PLANT LEVEL W ASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR 58it8 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-F ISCAL YE AR 1992. Annual Report SPECTION GUIDE FOR THE POINT BEACH NUCLEAR POWER PLANT.
WlE R E NGA.P.J.
NUREG/CR 5988 SOlt CHARACTERl2ATION METHODS FOR UN, W A GNE R.R.
SATURATED LOW-LEVEL WASTE SITES.
NUREG/CR-5926 SANS INVESTIGATION OF LOW ALLOY STEELS IN NEUTRON IRRADIATED. ANNEALED. AND REIRRADIATED CONDI.
WRIGHT.T.
TIONS NUREG/CR-5938 NATIONAL PROFILE ON COMMERCIALLY GENER-ATED LOW-LEVEL RADIOACTIVE MIXED WASTE W ARNER.R D.
N'U GrCR 5917 VOI: SENSITIVITY AND UNCERT AINTY ANALYSES C TED N E JLA OR CU NS APPLIED TO ONE DIMENSIONAL RADIONUCLIDE TRANSPORT IN A W ASTLE R,S.
LAYERED FRACTURED ROCK MULTFRAC Anatytec Solutions And NUREG 1476 DRAFT ENVIRONMENTAL IMPACT STATEMENT TO Local Sensitivities NURE G/CR-5911 V02: SENSITIVITY AND UNCER TAINTY ANALYSES CONSTRUCT AND OPERATE A FACILITY TO RECEIVE, STORE APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A AND DISPOSE OF 11E (2) BYPRODUCT MATER!AL NEAR CLIVE' LAYERED FRACTURED ROCK Evaluation Of The Lmt State Ap-UTAH Docket No 40 8989 Enwocare Of Utah. Inc.
proach.
EBER,R Y AKLE,JL NUREG 1476 DRAFT ENVIAONMENTAL !MPACT STATEMENT TO NUREG/CR-5863. RISK ASSESSMENT OF ISOLATION DEVICES IN CONSTRUCT AND OPERATE A FACILITY TO RECEIVE. STORE, SAFETY SYSTEMS' AND DISPOSE OF itE (2) BYPRODUCT MATERIAL NEAR CLtVE.
UTAH. Docket No 40 8989. Envwocare Of Utah, Inc YAN,H.
NUREG/CR-5951. THE MANAGEMENT OF ATWS BY BORON INJEC-WELCH.L TION.
NUREG/CR-5962 HE ALTH AND SAFETY IMPACTS FROM DISCRETE a
SOURCES OF NATURALLY-OCCURRING AND ACCELERATOR PRO-YOUNG.F.L DUCED RAD:OACTIVE MATERIALS (NARM)
NUREG/CR-5488 RISK-BASED INSPECTION GUIDE FOR THREE MILE ISLAND NUCLEAR STATION UNIT 1.
WIBLIN.C.
NUREG/CR-5962 HEALTH AND SAFETY IMPACTS FROM DISCRETE Y OU N G.M.H.
SOURCES OF NATURALLYOCCURRlNG AND ACCELERATOR-PRO-NUREG/CR-5988. SOfL CHARACTER 12ATION METHODS FOR UN-DUCED R ADICACTIVE MATERIALS (NARM)
SATURATED LOW-LEVEL WASTE SITES L_________
1 i
l 1
I i
Subject Index This index was developed from keywords and word strings in titles and abstracts. During this development period, there will be some redundancy, which will be removed later when a rea-i sonable thesaurus has been developed through experience. Suggestions for improvements are welcome.
1 NUREGICR-5791. RISK EVALUATION FOR A GENERAL ELECTRIC ATWS NUREG/CR 5951 THE MANAGEMENT OF ATWS BY BORON INJEC-BWR EFF ECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT. Evaluation Of Genenc issue 57.
TION NUREG/CR 5951. THE MANAGEMENT OF ATWS BY BORON INJEC-Accelerator-Produced TION NUREG/CR-5962: HEALTH AND SAFETY IMPACTS FROM DISCRETE SOURCES OF NATURALLY-OCCURR!NG AND ACCELERATOR-PRO-Boron Dilution DUCED RADIOACTIVE MATERIALS (NARM).
NUREG/CR-5822. ANALYSIS OF THERMAL Mfx(NG AND BORON 01-LUTION IN A PWR Accident Sequence Precursor NUREG/CR 5936: ENHANCEMENTS TO THE ACCIDENT PRECURSOR Boron inject 6on METHODOLOGY.
NUREG/CR-5951 THE MANAGEMENT OF ATWS BY BORON INJEC-TION Aging NUREG/CR-5699 V01. AGING AND SERVICE WEAR OF CONTROL Byproduct Material ROD DRIVE MECHANtSMS FOR BWR NUCLEAR PLANTS NUREG 1476 DRAFT ENVIRONMENTAL IMPACT ST ATEMENT TO NUREGICR-5851. I.ONG TERM PERFORMANCE AND AGING CHAR.
CONSTRUCT AND OPERATE A F ACILITY TO RECEIVE, STORE.
ACTERISTICS OF NUCLEAR PLAN 1 PRESSURE TRANSMITTERS AND DISPOSE OF 11E (2) BYPRODUCT MATERIAL NEAR CLIVE, UT AH Docket No. 40-8989. Envuocare Of Utah, Inc l
Aging Assessment NUREG/CR-5783-AGING ASSESSMENT OF THE COMBUSTION ENGI-Calibratlon NUREG C 4
A E SM T F
TA S AND FOR INSTRUMENT CAllBRATION REDUCTION IN NUCLEAR SWITCHES IN NUCLEAR POWER PLANTS POWER PLANTS Arid Disposal Site Cement Degradation NUREGrCR-5980 THREE DIMENSIONAL REDISTRIBUTION OF TRlTI.
NUREG/CR-5987. MICROBIAL-INFLUENCED CEMENT DEGRADATION UM FROM A POINT OF RELEASE INTO A UNIFORM UNSATURATED
- LITERATURE REVIEW SOlt A Deterministic Model For Tntium Migration in An And Disposal Charpy V-Notch Impact NUREG/CR-5914 CHEMICAL COMPOSITION AND RT(NOT) DETERMI-Auxiliary Feedwater System NATIONS FOR MIDLAND WELD WF-70 NUREG!CR-5766. AUxlLIARY FEEDWATER SYSTEM RISK-BASED IN.
SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR Chem 6 cal Composition POWER PLANT NUREG/CR-5914. CHEMICAL COMPOSITION AND RT(NOT) DETERMI-NUREG/CR-5834. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN.
NATIONS FOR MIDLAND WELD WF-70 SPECTION GUIDE FOR THE FORT CALHOUN NUCLEAR POWEp PLANT Closure Bolt NUREG/CR 5835 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-NUREG/CR-6007. STRESS ANALYSIS OF CLOSURE BOLTS FOR SPECTION GUIDE FOR THE BEAVER VALLEY. UNITS 1 AND 2 NU.
SHIPPtNG CASKS.
CLEAR POWER PLANTS NUREGICR-5836. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-Concrete SPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWER NUREG/CR-5987. MICROBIAL-INFLUENCED CEMENT DEGRADATION PLANT.
. LITERATURE REVIEW.
NUREG/CR-5898. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN, S CTION GUIDE FOR THE POINT BEACH NUCLEAR POWER Containment NUREG/CR-4273 CRACK PROPAGATION IN HIGH STRAIN REGIONS OF SEQUOYAH CONTAINMENT.
Average Dose NUREG-07t3 V12-OCCUPATIONAL RADIATION EXPOSURE AT COM-Control Rod Drive MERCIAL NUCLEAR POWER REACTORS AND OTHER NUREG/CR-5699 V01: AGING AND SERVICE WEAR OF CONTROL FACILITIES,1990 Twenty-Third Annual Reg ROD DRIVE MECHANISMS FOR BWR NUCLEAR PLANTS NUREG/CR-5783 AGING ASSESSMENT OF THE COMBUSTION ENGl.
BWR NEERING AND BABCOCK & WILCOX CONTROL ROD DRIVES NUREG/CR 5699 V01: AGING AND SERVICE WEAR OF CONTROL ROD DRIVE MECHANISMS FOR BWR NUCLEAR PLANTS NUREG/CR-5791: RISK EVALUATION FOR A GENERAL ELECTRIC Crack Pop-In NUREG/CR-5952 EVALUATION OF CRACK POP INS AND THE DE-BWR. EFFECTS OF FfRE PROTECTION SYSTEM ACTUATION ON TERMINATION OF THEIR RELEVANCE TO DESIGN CONSIDER-SAFETY RELATED EOU!PMENT. Evaluation Of Genenc issue $7 NUREG/CR-5951. THE MANAGEMENT OF ATWS BY BORON INJEC-ATIONS TION.
Crack Propagation NUREG/CR 4273 CRACK PROPAGATION IN HIGH STRAIN REGIONS Bistable NUREG/CR-5644 AGING ASSESSMENT OF BlSTABLES AND OF SEQUOYAH CONTAINMENT.
SWITCHES IN NUCLEAR POWER PLANTS Crack-Arrest Bomng Water Reactor NUREG/CR-5952: EVALUATION OF CRACK POP-INS AND THE DE.
NUREG/CR-5699 V01: AGING AND SERVICE WEAR OF CONTROL TERMINATION OF THEIR RELEVANCE TO DESIGN CONSIDER-ROD DRIVE MECHANISMS FOR BWR NUCLEAR PLANTS ATIONS.
23
24 Sub ctIndex Decontamination Waste Program fracture Toughness NdREG/CR-5672 V03 CHAC
.4 TICS OF LOW-LEVEL RADIOAC-NUREGICR-5914-CHEMICAL, COMPOSfTION AND RT(NDT) DETERMt.
TIVE DECONTAMINATION WASTE Annual Report For Faal war NATIONS FOR MIDLAND WELD WF-70 1992.
TWO-PARAMET ER FRACTURE MECHANICS THEORY AND APPLICATIONS.
Design Consideration NUREG/CR-5952 EVALUATION OF CRACK POP-INS AND THE DE-Fractured Porous Media TERMINATtON OF THEIR RELEVANCE TO DESIGN CONSIDER-NUREG/CR 5991 PORFLOW: A MULTIFLUID MULTIPHASE MODEL ATIONS FOR SIMULATING FLOW. HEAT TRANSFER AND MASS TRANS.
Destructive Examination R D MWS 6A Ns Mamal Wsu NUREG/CR-5961: POSTTEST DESTRUCTIVE EXAMINATION OF THE
~ ^
STEEL LINER IN A 16-SCALE REACTOR CONTAINMENT MODEL Fractured Rock Dose Assessment NUREGICR-5917 V01. SENSITIVITY AND UNCERTAINTY ANALYSES NUREG/CR-5247 V01 R1. RASCAL VERSION 2 0 USER S GUIDE.
APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A LAYERED FRACTURED ROCK MULTFRAC Analytic Solubons And Dose Comnutment Local Sensitivities.
NUREG/CR-2850 V11: DOSE COMMITMENTS DUE TO RADIOACTIVE NUREG/CR-5917 V02. SENSITIVITY AND UNCERTAINTY ANALYSES RELEASES FROM NUCLEAR POWER PLANT SITES IN 1989.
APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A LAYEilED FRACTURED ROCK Evaluation Of The Limit State Ap-Draft Environmental impact Statement proach.
NUREG-1476 DRAFT ENVIRONMENTAL IMPACT STATEMENT TO CONSTRUCT AND OPERATE A FACILfTY TO RECEIVE STORE.
Functional inspection AND DISPOSE OF 11E.(2) BYPRODUCT MATERIAL NEAR CL!VE.
NUREG-1473. ELECTRICAL D:STRIBUTION SYSTEM FUNCTIONAL IN-UT AH. Docket No 40-8989 Eavrocare Of Utah. Inc.
SPECTION (EDSFI) DATA BASE PROGRAM.
Duct 61e-Brittle I
Gate Valve i
NUREGICR 5952 EVALUATION OF CRACK POP-lNS AND THE DE-NUREG-1275 V09 OPERATING EXPERIENCE FEEDBACK REPORT -
t TERMINATION OF THEIR RELEVANCE TO DESIGN CONSIDER-PRESSURE LOCKING AND THERMAL BINDING OF GATE ATIONS VALVES. Commercial Power Reactors ECCS Heanh Risk NUREG/CR 5818 UNCERTAINTY ANALYSIS OF MINIMUM VESSEL NUREG/CR-58B3: HEALTH RISK ASSESSMENT OF IRR ADIAT ED LIOUID INVENTORY DURING A SMALL-BREAK LOCA IN A B&W TOPAZ' PLANT-AN APPLICATION OF YHE CSAU METHODOLOGY USING THE RELAP5/ MOD 3 COMPUTER CODE-Heat Transfer EDSFI NUREG/CR 5991: PORFLOW. A MULTIFLUID MULTIPHASE MODEL NUREG 1473 ELECTRICAL DISTRIBUTION SYSTEM FUNCTIONAL IN.
FOR S!MULATING FLOW. HEAT TRANSFER, AND MASS TRANS-SPECTION (EDSFI) DATA BASE PROGRAM.
PORT IN FRACTURED POROUS MEDIA. User's Manual - Version 2.41.
EPICOR-li NUREG/CR-5229 VDS FIELD LYSIMETER INVESTIGATIONS LOW, Heterogeneous Soil LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NUREG/CR-5998: SIMULATION OF UNSATURATED FLOW AND NON-FISCAL YEAR 1932. Annual Report REACTIVE SOLUTE TRANSPORT IN A HETEROGENEOUS SOIL AT THE FIELD SCALE.
Earthquake Response NUREG/CR-6012: STIFFNESS AND DAMPING PROPERTIES OF A H6gh Pressure Coolant injection LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD.
NUREG/CR 5933: HIGH PRESSURE COOLANT INJECTION (HPCI)
ED EARTHOUAKE RESPONSES.
SYSTEM RISK BASED INSPECTION GUIDE FOR DRESDEN NUCLE-AR POWER STATION UNITS 2 AND 3 i
Economic Regulation NUREG/CR 5934 HIGH PRESSURE COOLANT INJECTION (HPCI)
NUREG!CR-5975: INCENT'VE REGULATION OF INVESTOR-OWNED SYSTEM RISK-BASED INSPECTION GUIDE FOR QUAD-CITIES r
NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULATORS.
ST ATION. UNITS 1 AND 2.
NUREG/CR-5959. HIGH PRESSURE COOLANT INJECTION (HPCI)
Electrical Distribution System NUREG-1473. ELECTRICAL DISTRIBUTION SYSTEM FUNCTIONAL IN-SYSTEM RISK-BASED INSPECTION GUIDE FOR ENRICO FERMI SPECTION (EDSFI) DATA BASE PROGRAM.
ATOM!C POWER PLANT, UNIT 2' Human Performance UA 11 N04 ENFORCEMENT ACTIONS SIGNIFICANT AC.
,5 STUD OF HUMAN PERFORMANCE DURING OP-g
^
TIONS RESOLVED Ouarterly Progress Report October-December l
1992 Human-Machine interf ace Envirocare NUREG/CR-5977; A PERFORMANCE INDICATOR OF THE EFFECTIVE-i NUREG 1476 DRAFT ENVIRONMENTAL IMPACT STATEMENT TO NESS OF HUMAN-MACHINE INTERFACES FOR NUCLEAR POWER l
CONSTRUCT AND OPERATE A FACILITY TO RECEIVE. STORE.
^*S' l
AND DISPOSE OF 11EJ2) BYPRODUCT MATERIAL NEAR CLIVE.
IRRAS l
UTAH Docket No 40-8989. Envvocare Of Utah. Inc NUREG/CR-5964.
SAPHiRE TECHNICAL REFERENCE Event Tree Analysis MANUAL:lRRAS/ SARA VERSION 4 0.
SAPHIRE TECHNICAL REFERENCE MANUAllRRAS/ SARA VERSION 4.0.
NU 7
12 OCCUPATIONAL RADIATION EXPOSURE AT COM-Esaminer Standards MERCIAL NUCLEAR POWER REACTCRS AND OTHER NUREG-1021 R07. OPERATOR LICENSING EXAMINER STANDARDS FACILITIES.1990 Twenty-Thnd Annual Report Fire Protection System inspection r
NUREG/CR-5791-RISK EVA: UAllON FOR A GENE *lAL ELECTRIC NUREG/CP-0128 PROCEEDINGS OF THE INTERNATIONAL WORK-BWR EFFECTS OF FN PROTECTION SYSTEM ACTUATION ON SHOP ON THE CONDUCT OF INSPECTIONS AND INSPECTOR SAFETY RELATED ECWMENT, Evaluahon Of Genenc issue 57.
QUALIFICATION AND TRAINING.
Fracture Mechan 6cs inspection Gulde NUREG/CR-595B. TWO-PARAMETER FRACTURE MECHANICS-NUREG/CR-5488. RISK BASED INSPECTION GUIDE FOR THREE MILE THEORY AND APPLICATIONS ISLAND NUCLEAR STATION UNIT 1.
l 4
l
Subject index 25 NUREG/CR-5766 AUMLIARY FEEDW ATER SYSTEM RISK-BASED IN-Low Level Radioactive Waste SPECTION 'iUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR NUREG/CR-5672 V03 CHARACTERISTICS OF LOW ~ LEVEL RADICAC.
TIVE DECONTAMINATION WASTE Annual Aeport For Fiscal Year POWER PLANT NUREG/ CR-5834 AUXILIARY FEEDW ATER SYSlEM RISOBASED IN-1992 SPECTION GUIDE FOR THE FORT CALHOUN NUCLEAR POWER NUREG/CR-5938. NATIONAL PROFILE ON COMMERCIALLY GENER-ATED LOW-LEVEL RADIOACTIVE mixed WASTE.
PLANT.
NUREG/CR 5835. AUXILIARY FEEDWATER SYSTEM RISK BASED IN-NUREG/GR 5987. MICROBtAL-INFLUENCED CEMENT DEGRADATION SPECTION GUIDE FOR THE BEAVER VALLEY UNITS 1 AND 2 NU-LITERATURE REVIEW CLEAR POWER PLANTS NUREGICR 5836 AUXILLARY FEEDWATER SYSTEM RISK-BASED IN-Low-Level Weste SPECTON GUIDE FOR THE PALO VERDE NUCLEAR POWER NUREG/CR-5988 SOIL CHARACTER 12ATION METHODS FOR UN-SATURATED LOW tEVEL WASTE SITES PLANT NUREG/CR-5898. AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SPECTON GUIDE FOR THE POINT BEACH NUCLEAR POWER Low Level Waste Data Base PLANT NUREG/CR 5229 V05 FIELD LYSIMETER INVESTIGATIONS. LOW-NUREG/CR 5933 HIGH PRESSURE COOLANT INJECTION (HPCI)
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR SYSTEM RISK-BASED INSPECTON GUIDE FOR DRESDEN NUCLE-FISCAL YEAR 1992 Annual Report.
AR POWER ST ATION UNITS 2 AND 3.
NUREGICR 5934 HIGH PRESSURE COOLANT INJECTION (HPCI)
Low-Level Waste Disposal SYSTEM RISK-BASED INSPECTION GUIDE FOR OUAD. CITIES NUREG/CR-59tl. SOURCE TERM EVALUATION FOR RADIOACTIVE LOW-tEVEL WASTE DISPOSAL PERFORMANCE ASSESSMENT.
NtRE C 9 H GH PRESSURE COOLANT INJECTION (HPCI)
SYSTEM RISK-BASED INSPECTION GUIDE FOR ENRICO FERMI Lysimeter ATOMIC POWER PLANT. UNIT 2' NUREG/CR.5229 V05. FIELD LYSIMETER INVESTIGATONS LOW-LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR Inspector Qualification And Traming FISCAL YEAR 1992 Annual Report.
NUREG/CP-0128 PROCEEDINGS OF THE INTERNATIONAL WORK.
SHOP ON THE CONDUCT OF INSPECTIONS AND INSPECTOR U
OUALIFICATION AND TRAINING NUREG/CR-5922; MODULAR HIGH TEMPERATURE GASCOOLED RE-
- ACTOR SHORT, TERM THERMAL RESPONSE TO FLOW AND REAC-Instrumentation Channel NUREGICR-5903 VAllDATION OF SMART SENSOR TECHNOLOGIES TIVITY TRANSIENTS.
FOR INSTRUMENT CAUBRATION REDUCTION IN NUCLEAR Minimum Vessel Liquid POWER PLANTS NUREG/CR-5818-. UNCERTAINTY ANALYSIS OF MIN 1 MUM VESSEL LIOUID INVENTORY DURING A SMALL-BREAK LOCA IN A B&W Iridium-192 NUREG 1480 LOSS OF AN IRlDIUM-192 SOURCE AND THERAPY MIS-PLANT-AN APPUCATION OF THE CSAU METHODOLOGY USING ADMIN!ST RATION AT INDIANA REGIONAL CANCER THE RELAPS/ MOD 3 COMPUTER CODE CENTER)NDIANA. PENNSYLVANIA.ON NOVEMBER 16.1992.
Multiphase Transport irradiated Topaz NUREG/CR 5991: PORFLOW: A MULTIFLUlO MULTIPHASE MODEL NUREG/CR-5883 HEALTH RISK ASSESSMENT OF IRRADIATED FOR SIMULATING FLOW. HEAT TRANSFER, AND MASS TRANS-TOPAZ PORT IN FRACTURED POROUS MEDIA. User's Manual Version 24 isolation Device NUREG/CR 5863. RISK ASSESSMENT OF ISOLATION DEVICES IN Naturally Occurring b#
b#Ub NUREG/CR-5962: HEALTH AND SAFETY IMPACTS FROM DISCRETE SOURCES OF NATURALLY-OCCURRING AND ACCELERATOR-PRO-LOCA DUCED RADIOACTIVE MATERIALS (NARM)
NUREGICR-58t B UNCERTAINTY ANALYSIS OF MlN! MUM VESSEL UQUtD INVENTORY DURING A SMALL-BREAK LOCA IN A B8W Neutron Klnetic PLANT AN APPLICATON OF THE CSAU METHODOLOGY USINq NUREG/CR 5922: MODULAR HIGH-TEMPERATURE GASCOOLED RE-THE RELAPS/ MOD 3 COMPUTER CODE ACTOR SHORT-TERM THERMAL RESPONSE TO FLOW AND REAC-TIVITY TRANSIENTS Legal lasuances NUREG-0750 V36 N01: NUCLEAR REGULATORY COMM!SSION IS Operating Events t
SUANCES FOR JULY 1992.Pages 145 NUREG/CR-5953 STUDIES OF HUMAN PERFORMANCE DURING OP-NUREG-0750 V36 NO2. NUCLEAR REGULATORY COMM!SSION IS SUANCES FOR AUGUST 1992 Pages47-148 ERATING EVENTS 19901992.
NUREG-0750 V36 NO3 NUCLEAR REGULATORY COMM!SSION IS-SU NCES FOR SEPTEMBER 1992 Pages 149 220 Operating Esperience Feedback Report NUREG-0750 V75 N04 NUCLEAR REGULATORY COMMISSION IS-NUREG 1275 V09. OPERATING EXPERIENCE FEEDBACK REPORT -
SUANCES FOR OCTOBER 1992 Pages 221-249 PRESSURE LOCKING AND THERMAL BINDING OF GATE NUREG-0750 V36 N05. NUCLEAR MEGULATORY COMMISSON IS-VALVES Commercial Power Reactors.
SUANCES FOR NOVEMBER 1992 Pages 251350 NUREG-0750 V36 N06 NUCLEAR REGULATORY COMMISSION IS Operational Event i RNJL Y COMMISSION IS-ME HO O Y" NU E -
7 J LE SUANCES FOR JANUARY 1993 Pages 1-54.
Operator Licensing Licensed Operating Reactor NUREG 1021 R07. OPERATOR UCENSING EXAMINER ST ANDARDS NUREG4020 V17: UCENSED OPERATING REACTORS STATUS SUM-MARY REPORT. Data As Of December 31,1992 (Gray Book I)
Organiotion Chart NUREG-0325 R16 U.S NUCLE AR REGULATORY COMMISSION F UNC-Liquid Control Systerr.
TIONAL ORGANIZATION CHARTS March 15.1993 NUREG/CA-5951. THE MANAGEMENT OF ATWS BY BORON INJEC-PORFLOW NUREG/CR-5991 PORF LOW: A MULTIFLUID MULTIPHASE MODEL Long Term Ferformance FOR SIMULATING FLOW. HEAT TRANSFER, AND MASS TRANS NUREG/CR-5851, LONG TERM PERFORMANCE AND AGING CHAR-ACTERISTICS OF NUCLEAR PLANT PRESSURE TRANSMITTERS.
PORT IN FRACTURED POROUS MEDIA User's Manual Version 241.
Low Alloy Steet NUREG/CR-5926 SANS INVESTIGATION OF LOW ALLOV STEELS IN PRA NEUTRON IRRADIATED, ANNEALED, AND REIRRADIATED CONDI.
NUREG/CR 5488: RISK-BASED INSPECTION GUIDE FOR THREE MILE (SLAND NUCLE AR STATON UN!T 1.
TIONS
l 26 SubkCt index NUREG/CR 5766 AUXIUARY FEEDWATER SYSTEM RISK-BASED IN-Radiation Embrittlement SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR POWER PLANT.
NUREG/CR-5926. SANS INVESTIGATION OF LOW ALLOY STEELS IN NUREGJCR-5834 AUXILIARY FEEDW ATER SYSTEM R:SA 6ASED IN-NEUTRON IRRADIATED. ANNEALED, AND REIRRADIATED CONDI-SPECTION guide FOR THE FORT CALHOUN NUCLEAR POWER TIONS.
PLANT NUREG/CR-5835 AUXlLIARY FEEDWATER SYSTEM RISK-BASED IN-Radiation Exposure SPECTION GUIDE FOR THE BEAVER VALLEY. UNITS 1 AND 2 NU-NUREG-0713 V12-OCCUPATIONAL RADIATION EXPOSURE AT COM-CLE AR POWER PLANTS MERCIAL NUCLEAR POWER REACTORS AND OTHER NUREG/CR 5836. AUXILIARY FEEDWATER SYSTEM RISK BASED IN-FACILITIES.1990 Twenty-Thnd Annual Report SPECTION GUIDr FOR THE PALO VERDE NUCLEAR POWER NUREG-1480: LOSS OF AN IRIDIUM 192 SOURCE AND THERAPY MIS.
PLANT ADMINISTRATION AT INDIANA REGIONAL CANCER NUREG'CR-5898 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-CENTER,1NDIANA. PENNSYLVANIA,0N NOVEMBER 16,1992.
SPECTION GUIDE FOR THE POINT BEACH NUCLEAR POWER PLANT.
Rs11ation Hazard NUREG/CR-5964.
SAPH:RE TECHNICAL REFERENCE NUREG/CR-5883 HEALTH RISK ASSESSMENT OF IRRADIATED MANUAL IRRAS/ SARA VERSION 4 0 TOPAZ.
PWR F<adiation Transport NUREG/CR-5822. ANALYSIS OF THERMAL MIXING AND BORON Di-NUREG/CR 5247 V01 R1: RASCAL VERSION 2 0 USER'S GUIDE.
LUTION IN A PWR Radioactive Material Performance History NUREG/CR-5962: HEALTH AND SAFETY IMPACTS FROM DISCRETE NUREG4214 R11 HISTORICAL DATA
SUMMARY
OF THE SYSTEMAT.
SOURCES OF NATURALLY OCCURRING AND ACCELERATOR-PRO-IC ASSESSMENT OF LICENSEE PERFORMANCE.
DUCEO RADIOACTIVE MATERIALS (NARM).
Performance incentive Radioactive Release NUREG/CR-5975 INCENTIVE REGULATION OF INVESTOR-OWNED NUREG/CH-2850 V11: DOSE COMMITMENTS DUE TO RADIOACTIVE NUCLE AR POWER PLANTS BY PUBLIC UTILITY REGULATORS RELEASES FROM NUCLEAR POWER PLANT SITES IN 1989.
Performance Indicator Radioactive Tracer NUREG/CR 5977. A PERFORMANCE INDICATOR OF THE EFFECTIVE.NUREG/CR-5996. SUBSURFACE INJECTION OF RADIOACTIVE NESS OF HUMAN-MACHINE INTERFACES FOR NUCLEAR POWER TRACERS Field Expenment Fct Model Vahdation Testing PLANTS Petitions For Rulemaking Radionuclide Transport NUREG/CR-5917 V01: SENSITIVITY AND UNCERTAINTY ANALYSES NUREG-0936 V11 N04 NRC REGULATORY AGENDA Quarterly APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A Report. October-December 1992 LAYERED FRACTURED ROCK.MULTFRAC - Analytic Solutions And Practice And Procedure Digest Local Sensitetees.
NUREG-0386 D06 ROS. UNITED STATES NUCLEAR REGULATORY NUREG/CR-5917 V02. SENSITIVITY AND UNCERTAINTY ANALYSES APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A COMMISSION STAFF PRACTICE AND PROCEDURE DIGEST Comm> won. Appeal Bord And Licensing Board Decisons. July L AYERED FRACTURED ROCK Evaluation Of The bmit State Ap-1972 March 1992 proach Pressure Transmitte' ReactMty Transient NUREG/CR-5851' LONG TERM PERFORMANCE AND AGING CHAR-NUREG/CR-5922 MODULAR HIGH TEMPERATURE GAS-COOLED RE-ACTERISTICS OF NUCLEAR PLANT PRESSURE TRANSMITTERS ACTOR SHORT TERM THERMAL RESPONSE TO FLOW AND REAC.
TiVITY TRANSIENTS Pressure Vessel NUREG/CR 5926 SANS INVESTIGATION OF LOW ALLOY STEELS IN Reactor Accident NEUTRON IRRADIATED. ANNEALED, AND RElRRADIATED CONDI-NUREG/CR-5933-HIGH PRESSURE COOLANT INJECTION (HPCI)
TIONS SYSTEM RISK-BASED INSPECTION GUIDE FOR DRESDEN NUCLE-AR POWER ST ATION UNITS 2 AND 3 Pressurized Water Reactor NUREG/CR 5934, HIGH PRESSURE COOLANT INJECTION (HPCI)
NUREG/CA-5822 ANALYSIS OF THERMAL MIXfNG AND BORON DI-0
. UTION IN A PWR' STATION. UNITS 1 AND 2.
NUREG/CR 5959. HIGH PRESSURE COOLANT INJECTION (HPCI)
Probabilistic Risk Assessment SYSTEM RISK-BASED INSPECTION GUIDE FOR ENRICO FERMI NUREG/CR-4551 V7R1P1. EVALUATION OF SEVERE ACCIDENTATOMIC POWER PLANT, UNIT 2.
RISKS-ZION UNIT 1. Main Report NUREG/CR-455 t V7 RIP 2A: EVALUATION OF SEVERE ACCIDENT Reador Containment RISKS: ZION UNIT 1 Appenda A NUREG/CR-5961: POSTTEST DESTRUCTIVE EXAMINATION OF THE NUREG/CR-4551V7R tP2B EVALUATION OF SEVERE ACCIDE NT STEEL LINER IN A 1.6 SCALE REACTOR CONTAINMENT MODEL RISKS ZION UNIT 1. Appendices B. C. D, And E NUREG/CA-5791 RISK EVALUATION FOR A GENERAL ELECTRIC Reactor Control System BWR. EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON NUREG/CR-5783. AGING A$SESSMENT OF THE COMBUSTION ENGi-SAFETY-RELATED EQUIPMENT. Evaluation Of Genene issue 57 NEERING AND BABCOCK & WILCOX CONTROL ROD DRIVES NUREG/CR-5863 RISK ASSESSMENT OF ISOLATION DEVICES IN NUREG/CR-5844-AGING ASSESSMENT OF BISTABLES AND SAFETY SfSTEMS NUREG/CR 5936 ENHANCEMENTS TO THE ACCIDENT PRECURSOR SWITCHES IN NUCLEAR POWER PLANTS.
METHODOLOGY.
Reactor Cooling System Public Utility Regulator NUREG/CR-5933. HIGH PRESSURE COOLANT INJECTION (HPCI)
SYSTEM RISK-BASED INSPECTION GU!DE FOR DRESDEN NUCLE-NUREG/CR-5975 INCENTIVE REGULAT60N OF INVESTOR OWNED AR POWER STATION UNITS 2 AND 3.
NUCLEAR POWER PLANTS BY PUBLIC UTILITY REGULATORS.NUREG/CR-5934. HIGH PRESSURE COOLANT INJECTION (HPCI)
RASCAL Version 2 SYSTEM RISK-BASED INSPECTION GUIDE FOR OUAD-CITIES NUREG/CR-5247 VC1 R1; RASCAL VERS!ON 2 0 USER'S GUIDE STATION. UNITS 1 AND 2 NUREG/CR-5959. HIGH PRESSURE COOLANT INJECTION (HPCI)
RELAPS/ MOD 3 SYSTEM RISK BASED INSPECTION GUIDE FOR ENRtCO FERML NUREG/CR-5818. UNCERTAINTY ANALYSIS OF MINIMUM VESSEL ATOMIC POWER PLANT.UN!T 2.
LtOU1D INVENTORY DURING A SMALL-BREAK LOCA IN A B&W Reactor Maintenance PLANT AN APPLICATION OF THE CSAU METHODOLOGY USING THE RELAPS/ MOD 3 COMPUTER CODE.
NUREG/CR-5783: AGING ASSESSMENT OF THE COMBUSTION ENGi-NEERING AND BABCOCK & WILCOX CONTROL ROD DRIVES.
i 1
(
4 Subject index 27 i
?
3 Reactor Safety Seismic Design i
I NUREG/CR-4551 V7R1PI: EVALUATION OF SEVERE ACCIDE NT NUREG!CR 6011 REVIEW OF STRUCTURE DAMPING VALUES FOR 1
RISKS ZION UNIT 1 Mair, Report.
ELASilC SEISMIC ANALYSIS OF NUCLEAR POWER PL ANTS j
NURE G/CR-4551V7R1P2 A.
EVALUATION OF SEVERE ACCIDENT i
j RISKS ZION UNIT 1 Appenda A Severe Accident l
NURE G /CR-4551V7R1P2B EV ALUATION OF SEVERE ACCIDENT NUREG/CR-4273 CRACK PROPAGATION IN HIGH STRAIN REGIONS
(
RISKS ZION UNIT 1 Appendices B. C. D. And E OF SEQUOYAH CONTAINMENT.
NUREG/CR-4551 V7R1Pt-EVALUATION OF SEVERE ACCIDENT j
Recall Technique blSKS ZION UNIT 1 Main Report r
NUREGICR-5977 A PERFORMANCE INDICATOR OF THE EFFECTIVE-NUREG/CR 4551V7R1P2A. EVAL UATION OF SEVERE ACCIDENT NESS OF HUMAN-MACHINE INTERFACES FOR NUCLEAR POWER RISKS ZION UNIT 1 Appendu A l
PLANTS NUREG/CR-4551V7R1P28. EVALUATION OF SEVERE ACCIDENT RISKS ZION UNIT 1 Appendices B. C, D. And E.
1 Regulatory Agenda 1
NUREG-0936 V11 N04 NRC REGULATORY AGENDA Quarterly Shear Wall j
Report. October-December 1992 NUREG/CR 5755 STIFFN2SS OF LOW. ASPECT RATIO, REINFORCED l
CONCRETE SHEAR WALLS.
Regulatory And Technical Report i
NOREG-0304 V17 NO4 REGULATORY AND TECHNICAL REPORTS Shear Wall Bulldmg l
l (ABSTRACT INDEX JOURNAL) Annual Compilation F or 1992.
NUREG/CR-6012 STIFFNESS AND DAMPlNG PROPERTIES OF A LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD j
Regulatory Document ED E ARTHOUAKE RESPONSES.
NUREG/CR 5973 CODES AND STANDARDS AND OTHER GUIDANCE j
CITED IN REGULATORY DOCUMEN1S Shipping Cask NUREG/CA 6001 STRESS ANALYSIS OF CLOSURE BOLTS FOR j
Reinforced Concrete SHIPPING CASKS' j
NUREG/CR 5755. STIFFNESS OF LOW-ASPECT RATIO, REINFORCED CONCRETE SHEAR WALLS-Smart Sensor NUREG/CR-5903 VALIDATION OF SMART SENSOR TECHNOLOGIES Residual Heat Removal FOR INSTRUMENT CAllBRATION REDUCTION !N NUCLEAR NUREG 1275 V09 OPERATING EXPERIENCE FEEDBACK REPORT -
l PRESSURE LOCKING AND THERMAL BINDING OF GATE POWER PLANTS i
]
VALVES Commercial Power Reactors gag Resin NUREG/CR-5988 SOIL CHARACTERIZATION METHODS FOR UN-SATURATED LOW-LEVEL WASTE SITES NUREG/CR-5229 V05 FIEl D LYSIMETER INVESTIGATIONS LOW.
l LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR SoH-Structure Interaction j
FISCAL YEAR 1992. Annual Report.
NUREG/CR 5956 CONSIDERATION OF UNCERTAINTIES IN SOIL-
)
Response Time Testing STRUCTURE INTERACTION COMPUTATIONS NUREG/CR 5903. VAllDATION OF SMART SENSOR TECHNOLOGIES 3
b i
FO NSTR MENT CAllBRATION REDUCTION IN NUCLEAR E /CR
- 98. SIMULATION OF UNSATURATED FLOW AND NON-REACTIVE SOLUTE TRANSPORT IN A HETEROGENEOUS SOIL AT Rules THE FIELD SCALE.
NUREG-0936 Vit N04 NRC REGULATORY AGENDA.Ouarterly Report. October-December 1992 b
C
'[CR-5911:
SOURCE TERM EVALUATION FOR RADIOACTIVE Rules Of Practice LOW-LEVEL WASTE DISPOSAL PERFORMANCE ASSESSMENT.
NUREG-0386 D06 R05-UNITED STATES NUCLEAR REGULATORY Standard Review Plan COMMISSON STAFF PRACTICE AND PROCEDURE DIGEST.Commssion. Appeal Board And Licensing Board Decisions July NUREG/CR 5973 CODES AND STANDARDS AND OTHER GUIDANCE 1972 - March 1992 CITED IN REGULATORY DOCUMENTS.
SANS Steel Liner NUREG/CR 5926 SANS INVESTIGATION OF LOW ALLOY STEELS IN NUREG/CR 5961: POSTTEST DESTRUCTIVE EXAMINATION OF THE NEUTRON IRRADIATED, ANNEALED. AND REIRRADIATED CONDI.
STEEL LINER IN A 16-SCALE REACTOR CONTAINMENT MODEL i
TIONS Stress Analysis f
SA DHIRE NUREG/CR-6007. STRESS ANALYSIS OF CLOSURE BOLTS FOR NUREG/CR 5964 SAPHIRE TECHNICAL REFERENCE SHIPPING CASKS.
MANUAL lRRAS/ SARA VERSION 4 0.
Stress Triaxiality i
Safety Enchancement NUREG/CR-5958-TWO-PARAMETER FRACTURE MECHANICS NUREG-1366. IMPROVEMENTS TO TECHNICAL SPECIFICATIONS THEORY AND APPLICATIONS 4
t SURVEILLANCE REQUIREMENTS.
Structure Damping Safety Evaluation Report NUREG/C46011; REVIEW OF STRUCTURE DAMDING VALUES FOR a
NUREG 0797 S26 SAFETY EVALUATION REPORT RELATED TO THE ELASTIC SE!SMIC ANALYSIS OF NUCLEAR POWER PLANTS OPERATON OF COMANCHE PEAK STEAM EL ECTRIC NUREG/CR-6012: STIFFNESS AND DAMPING PROPERTIES OF A STATION.UN!T
- 2. Docket No 50-446 (Texas Utilities Electnc LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD-Company.et al.)
ED EARTHOUAKE RESPONSES.
Safety System Subsurface injection NUREG'CR 5863 RISK ASSESSMENT OF ISOLATION DEVICES IN NUREG/CR-5998: SUBSURFACE INJECTION OF RADIOACTIVE SAFETY SYSTEMS.
TRACERS Field Expenment For Model Vahdation Testing 3
Selsmic SurveHlance Requirement NUREG/CR-5755 STIFFNESS OF LOW. ASPECT RATIO. REINFORCED NURE G-1360. IMPROVEMENTS TO TECHNICAL SPECIFICATIONS CONCRETE SHEAR WALLS SURVEILLANCE REQUIREMENTS.
NURE G/CR-5956 CONSIDERATION OF UNCERTAINTIES IN SOIL-STRUCTURE INTERACTION COMPUT ATIONS Switch NUREG/CR-6011: REVIEW OF STRUCTURE DAMPING VALUES FOR HUREG/CR-5844. AGING ASSESSMENT OF BISTABLES AND ELASTIC SEISMIC ANALYSIS OF NUCLEAR POWER PLANTS SWITCHES IN NUCLEAR POWER PLANTS.
28 Subject index Systematic Assessment Of Ltcensee Performance Tritium NUREG-1214 Alt. HtSTORICAL DATA
SUMMARY
OF THE SYSTEMAT-NUREG/CR 5980 THREE DIMENSIONAL RED STRIBUTION OF TRITI-IC ASSESSMENT OF UCENSE E PERFORMANCE UM F ROM A POINT CF RELE ASE INTO A UNIFOnM UNSA1URATED SOIL A Determirustm Model for intium Migration in An And Disposal TLD Site NUREG-0837 V12 N04 NRC TLD DIRECT RAD!ATION MONITORING NETWORK. Progress Report October December 1992 Tritium Migration NUREG/CR-5980: THREE DIMENSIONAL REDISTRIBUTION OF TRITI-Technical Specifications UM FROM A POINT OF RELEASE INTO A UNIFORM UNSATURATED NUREG-1366-IMPROVE MENTS TO TECHN! CAL SPECnFICATIONS SOILA Deterministic Model For Tntium Migration In An And Disposal SURVEILLANCE REQUIREMENTS Site.
Therapy M6sadministration Unsaturated Flow NUREG-1460 LOSS OF AN IRIDtUM-192 SOURCE AND THERAPY M:S-NUREG/CR 5998 SIMULATION OF UNSATURATED FLOW AND NON-ADMINISTRATION AT INDIANA REGIONAL CANCER REACTIVE SOLUTE TRANSPORT IN A HETEROGENEOUS SOIL AT CENTER.lNDIANA.PENNSYLVAN; A ON NOVEMBER 16,1992 THE FIELD SCALE.
Thermal Mining Unsaturated Soil NUREG/CR-5822. ANALYSIS OF THERMAL Mix'NG AND BORON Di-NUREG/CR-5980. THREE DIMENSIONAL RED:STRlBUTION OF TRITI-LUTtON IN A PWR UM FROM A POINT OF RELEASE INTO A UNIFORM UNSATURATED SOIL A Deterministic Model For Tntium Migration in An And Disposal Thermal Response Site NUREG/CR-5922 MODULAR HIGH TEMPERATURE GAS-COOLED RE-1 ACTOR SHORT-TERM THERMAL RESPONSE TO FLOW AND REAC-Unsaturated Waste Site TIVITY TRANSIENTS NUREG/CR-5968 SOIL CHARACTERIZATION METHODS FOR UN.
SATURATED LOW LEVEL WASTE SITES i
Thermoluminescent Dosimeter NUREG 0837 V12 N00 NRC TLD DIRECT RADIATION MONITORING Unsaturated Zone NETWORK Progress Repod October-December 1992.
NUREG/CR-5996 SUBSURFACE INJECTION OF RADIOACTIVE TRACERS Field Expentnent For Model Validation Testing NUREG C540 V14 N11: T!TLE UST OF DOCUMENTS MADE PUBLICLY Yendor inspection AVA!L ABLE November 1-30,1992.
NUREG-0040 V16 N04 LICENSEE CONTRACTOR AND VEf 00R IN-NUREG-0540 V14 N12: TITLE LIST OF DOCUMENTS MADE PUBLICLY SPECTION STATUS REPORT. Quarterly Report. October-December AVAILABLE. December 1-31,1992.
1992.(White Book)
NUREG-0540 V15 Not: TITLE LIST OF DOCUMENTS MADE PUBLICLY AV AILABLE. January 1 31.1993.
Waste Treatment NUREG/CR-5938. NATIONAL PROFILE ON COMMERCIALLY GENER-Trammg Program ATED LOW LEVEL RADIOACTIVE MIXED WASTE.
NUREG-1220 RO1: TRAINING REVIEW CRITERIA AND PROCEDURES Weld Training Renew NUREG/CR-5914. CHEMICAL COMPOSITION AND RT(NDT) DETERMI-NUREG-1220 RO1 TRAINING REVIEW CRITERIA AND PROCEDURES NATIONS FOR M:DLAND WELD WF-70
NRC Originating Organization index (Staff Reports)
This index lists those NRC organizations that have published staff reports. The index is ar-ranged alphabetically by major NRC organizations (e.g., program offices) and then by sub-sections of these (e.g., divisions, branches) where appropriate. Each entry is followed by a NUREG number and title of the report (s). If further information is needed, refer to the main citation by NUREG number.
OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
EDO - OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS REGION 1 (POST 820201)
DIVISION OF HIGH-LEVEL W AS1E MANAGEMENT (POST B70413)
NUREG-0837 V12 N04 NRC TLD DIRECT RAD!ATION MONITORING NUREG/CR 5917 V0t SENSITIVITY AND UNCERTAINTY ANAL YSES NETWOAK Progress Report October-December 1992 APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN NUREG/CR 5488 RISN-BASED INSPECTION GUIDE FOR THREE A LAYERED FRACTURED ROCK MULTFRAC - Analytic Solutions MILE ISLAND NUCLEAR STATION UNIT 1 And Local Sensitetees NUREG/CR 5835 AUXILL AR Y FEEDWATER SYSTEM RISK-BASED DIVISION OF LOW-LEVEL WASTE MANAGEMENT & DECOMMISSION-INSPECTION GUIDE FOR THE BEAVER VALLEY. UNITS 1 AND 2 ING (POST 870413)
NUCLEAR POWER PLANTS NUREG-14 76 DRAFT ENylRONMENTAL IMPACT STATEMENT TO REGION 5 (POST 820201)
CONSTRUCT AND OPERATE A FACILITY TO RECEIVE. STORE, NUREG/CR 5836 AUMLIARY FEEDWATER SYSTEM R SOB / SED AND DISPOSE OF 11E.(2) BYPRODUCT MATERIAL NEAR CLIVE, INSPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWER UT AH Docket No 40-8989. Enwrocare Of utah, Inc.
PLANT OFC OF ENFORCEMENT (POST 870413)
U S. NUCLEAR REGULATORY COMMISSION NUREG-0940 V11 NO4 ENFORCEMENT ACTIONS SIGNIFICANT AC.
OFFICE OF THE GENERAL COUNSEL (POST B60701)
TiONS RESOLVED Ouarterly Progress Report. October-December NUREG-0386 D06 R05 UNITED STATES NUCLEAR REGULATORY 1992 COMMISSION STAFF PRACTICE AND PROCEDURE OFC OF PERSONNEL (POST 870413)
DIGEST Commission, Appeal Board And Licensing Board NUREG 0325 R16-U S. NUCLEAR REGULATORY COMMlSSION Decessons July 1972 - March 1992.
FUNCTIONAL ORGAN!ZATION CHARTS March 15.1993 NRC - NO DETAILED AFFILIATION GIVEN NUREG 1480- LOSS OF AN IRIDIUM-192 SOURCE AND THERAPY EDO - OFFICE OF ADMINISTRATION (PRE 870413 & POST 890205)
MISADMINISTRATION AT INDIANA REGIONAL CANCER O! VISION OF FREEDOM OF INFORMATION & PUBLICATIONS SERV-CENTER.lNDIANA. PENNSYLVANIA.ON NOVEMBER 16,1992 ICES (POST 890205 NUREG/CR-5917 V02 SENSITIVITY AND UNCERTAINTY ANALYSES NUREG-0304 V17 N14 REGULATORY AND TECHNICAL REPORTS APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN (ABSTRACT INDEX JOURNAL) Annual Compilation For 1992 A LAYERED FRACTURED ROCK Evaluation Of The Limit State Ap-NUAEG-0640 V14 N11. TITLE UST OF DOCUMENTS MADE PUBUC-proach.
LY AVAILABLE. November 1-30,1992 NUREG-0540 V14 N12 TITLE UST OF DOCUMENTS MADE PUBLIC.
EDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)
LY AVAILABLE. December 1-31.1992 DIVISION OF REGULATORY APPUCATIONS (POST B70413)
NUREG-0540 Vt5 N01. TITLE UST OF DOCUMENTS MADE PUBUC.
NUREG-0713 V12: OCCUPATIONAL RADIATION EXPOSURE AT LY AVAILABLE. January 1-31.1993 COMMERCIAL NUCLEAR POWER REACTORS AND OTHER NUREG-0750 V36 NO1 NUCLEAR REGULATORY COMM:SSION IS-F ACluTIES.1990. Twenty Third Annua! Report.
SUANCES FOR JULY 1992 Pages 1-45 WASTE MANAGEMENT BRANCH (POST 910830)
NUREG-0750 V36 NO2 NUCLEAR REGULATORY COMMISSION IS.
NUREG /CR-5988: SOIL CHARACTER!ZATION METHODS FOR UN.
SUANCES FOR AUGUST 1992 Paoes47-140.
SATURATED LOW-LEVEL WASTE SITES.
NUREG-0750 V36 NO3 NUCLEAR dEGULATORY COMMISSION is-SUANCES FOR SEPTEMBER 1992. Pages 149 220.
EDO - OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)
NUREG-0750 V36 N04 NUCLE AR REGULATORY COMM!SSION IS.
OFFICE OF NUCLEAR REACTOR REGULATION DIRECTOR (POST SUANCES FOR OCTOBER 1992 Pages 221-249 870411)
NUREG-0750 V36 N05 NUCLEAR REGULATORY COMM!SSION IS-NUREG/CP-0128. PROCEEDINGS OF THE INTERNATIONAL WORK-SUANCES FOR NOVEMBER 1992 Pages 251-350 SHOP ON THE CONDUCT OF INSPECTIONS AND INSPECTOR NUREG-0750 V36 N06 NDCLEAR REGULATORY COMMISSION 15 OUALIFICATION AND TRAINING.
SUANCES FOR DECEf/BlR 1992 Pages 351-396 PROJECT DIRECTORATE l 4 NUREG-0750 V37 N01 NUCLEAR REGULATORY COMM!SSION IS-NUREG/CR-5488. RISK-BASED INSPECTION GUIDE FOR THREE SUANCES FOR JANUARY 1993 Pages 1-54 MILE ISLAND NUCLEAR STATION UNIT 1 NUREG-0936 V11 NO4 NRC REGULATORY AGENDA Quarterly DIVISION OF RE ACTOR PROJECTS - Iluv.V (POST 901216)
Report. October-December 1992 NUREG-0797 b26. SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF COMANCHE PEAK ST E AM ELECTRIC EDO - OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL STATION. UNIT 2 Docket No 50-446 (Texas Utilities Electnc DATA Company et al)
INCIDENT RESPONSE BRANCH DIVISION OF OPERATIONAL EVENTS ASSESSMENT (870411921003)
NUREG/CR 5247 V01 Rt. RASCAL VERSION 2.0 USER'S GUIDE NUREG-1366 IMPROVEMENTS TO TECHNICAL SPECIFICATIONS DIVISION OF SAFETY PROGRAMS (POST B73413)
SURVEILLANCE REOUIREMENTS NUREG-1275 V09 OPERATING EXPERIENCE FEEDBACK REPORT -
DIVISION OF UCENSEE PERFORMANCE & OUAUTY EVALUATION PRESSURE LOCKING AND THERMAL B!NDiNG OF GATE (870411 921003)
VALVES Commercial Power Reactors NUREG-1220 ROI TRAINING REVIEW CRITERIA AND PROCE-TRENDS & PATTERNS ANALYSIS BRANCH DURES NUREG/CR 5964 SAPHiRE TECHNICAL REFERENCE DIVISION OF REACTOR CONTROLS & HUMAN FACTORS (POST MANUALtRRAS/ SARA VERSION 4 0 921004)
NUREG-1021 R07 OPERATOR UCE NSING EXAMINER STAND-EDO - OFFICE OF INFORM ATION RESOURCES MANAGEMENT & ARM ARDS (POST 861109)
DIVtSION OF REACTOR INSPECTION & UCENSEE PERFORMANCE DIVISION OF COMPUTE R & TELECOMMUNICATIONS SERVICES (POST 921004)
(POST 890205)
NUREG-0040 V16 N04. LICENSEE CONTRACTOR AND VENDOR IN-NUREG-0020 V17, UCENSED OPERATING REACTORS STATUS SPECTION STATUS REPORT. Quarterly Report. October-December
SUMMARY
REPORT. Data As Of December 31,1992-(Gray Book l}
1992 (White Book) 29
30 NRC Originating Organization index (Staff Reports)
NUREG 1214 R11: HISTORICAL DATA
SUMMARY
OF THE Sv' STEM-NUREG 14 73 ELECTRICAL DISTRIBUTION SYSTEM FUNCTIONAL ATIC ASSESSMENT OF LICENSEE PERFORMANCE INSPECTION (EDSFI) DATA B ASE FHOGR AM i
l N
s I
f I
i l
l t
1_ t k
i i
i
NRC Originating Organization Index (International Agreements)
This index lists those NRC organizations that have published international agreement re-ports. The index is arranged alphabetically by major NRC organizations (e.g., program of-fices) and then by subsections of these (e.g., divisions, branches) where appropriate. Each 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.
- "fe no NUREGilA reports for this quarter.
)
9 31 i
i
i NRC Contract Sponsor Index (Contractor Reports)
This index lists the NRC organizations that sponsored the contractor reports listed in this compilation. It is arranged alphabetically by major NRC organization (e.g., program office) and then by subsections of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) prepared by that organi-zation. If further information is needed, refer to the main citation by the NUREG/CR number.
EDO-OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR-6012. STIFFNESS AND DAMPING PROPERTIES OF A DATA LOW ASPECT RATIO SHEAR WALL BUILDtNU BASED ON RE-OfVISION OF OPERATIONAL ASSESSMENT (POST 870413)
CORDED EARTHOUAKE RESPONSES NUREG/CR-5247 V01 R1 RASCAL VERS!ON 2 0 USER'S GUIDE DIVISION OF REGULATORY APPLICATIONS (POST 6704t3; DIV!SION OF SAFETY PROGRAMS (POST 870413)
NUREG/CR 5229 V05 FIELD LYSIMETER INVESTIGATIONS: LOW-NURE 5822 NALYSIS OF THERMAL MIXING AND BORON DI.
LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NU EG/C 56 2 V03 HA AC RISTICS OF LOW-LEVEL RADIO-OP R T NG VE TS'1 92 ACTIVE DECONTAMINATION WASTE. Annual Report For Fiscal EDO - OFFICE OF INFORMATION RESOURCES MANAGEMENT & ARM Year 1992.
(POST 861109)
NUREG/CR-5883 HEALTH RISK ASSESSMENT OF IRRADIATED DivlSION OF COMPUTER & TELECOMMUNICATIONS SERVICES TOPAZ.
(POST 890205)
NUREG/CR-5962. HEALTH AND SAFETY IMPACTS FROM DIS-NUREG/CR 2850 VII. DOSE COMMITMENTS DUE TO RADIOAC-CRETE SOURCES OF NATURALLY-OCCURRING AND ACCELERA.
TlVE RELEASES FROM NUCLEAR POWER PLANT SITES IN 1989 TOR-PRODUCED RADIOACT!VE MATERIALS (NARM)
NUREG/CR-5980 THREE DIMENSIONAL REDISTRIBUTION OF EDO - OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS TRITlUM FROM A POINT OF RELEASE INTO A UNIFORM UN-S S
A nms um aun in An NL E CR 6 R S ANALY F
And Disposal Site WMMM EMEME D UKU ERM OfVISION OF HIGH-LEVEL WASTE MANAGEMENT (POST 870413)
NUREG/CR 5917 V01: SENSITIVITY AND UNCERTAINTY ANALYSES TION - LITER ATURE REVIEW.
APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN NUREG/CR-5991: PORFLOW. A MULTIFLUID MULTIPHASE MODEL A LAYERED FRACTURED ROCK MULTFRAC Analytic Solutens FOR SIMULATING FLOW. HEAT TRANSFEA AND MASS TRANS-And Local sensitet es PORT IN FRACTURED POROUS MEDIA. User's Manua! - Version NUREG/CR-5917 V02: SENSITIVITY AND UNCERTAINTY ANALYSES 2 41.
APPLIED TO ONE-DIMENSIONAL RAD!ONUCLIDE TRANSPORT IN NUREG/CR-5996. SUBSURFACE INJECTION OF RADIOACllVE A LAYERED FRACTURED ROCK Evaluation Of The Limit State Ap_
TR ACERS Field Expenment For Model Vahdat on Teshng proach NUREG/CR-5998: SIMULATION OF UNSATURATED FLOW AND l
DIVISION OF LOW LEVEL WASTE MANAGEMENT & DECOMMISSION.
NONREACTIVE SOLUTE TRANSPORT IN A HETEROGENEOUS ING (POST 870413)
SOIL AT THE FIELD SCALE.
NUREG/CR 5911 SOURCE TERM EVALUATION f OR RADIOACTIVE DIVISION OF SAFETY ISSUE RESOLUTION (POST 880717)
LOW. LEVEL WASTE DISPOSAL PERFORMANCE ASSESSMENT.
NUREG/CR-4551 V7R1P t: EVALUATION OF SEVERE ACCIDENT i
NUREG/CR 5938. NATIONAL PROFILE ON COMMERCIALLY GEN-RISKS ZION UNIT 1. Main Report.
ERATED LOW LEVEL RADIOACTIVE M!xED WASTE.
NUREG/CR-4551V7R1P2A EVALUATION OF SEVERE ACCIDENT HISKS ZION UNIT 1. Appendix A EDO - OFFICE OF NUCLEAR REGULATORY RESEARCH (POST 820405)
NUREG/CR-4551V7R1P2B EVALUATION OF SEVERE ACCIDENT DIVISION OF ENGINEERING (POST 8704131 D, And E RISKS ZION UNIT 1 Appendeces B. C'FOR A GENERAL ELECTRIC NUREG/CR-4273 CRACK PROPAGATION IN HIGH STRAIN RE-NUREG/CR-5791: RISK EVALUATION NUF GC 5 G GAD EF VICE WEAR OF CONTROL S AFETY-RELATED EOUIPMENT Evaluation Of Genenc issue 57.
R Ni REG /CR-5663 RISK ASSESSMENT OF ISOLATION DEVICES IN NUREG 75 S FFNESS O O
SP T R T O.
REIN.
FORCED CONCRETE SHEAR WALLS SAFETY SYSTEMS a
NUREG/CR 5783 AGING ASSESSMENT OF THE COMBUSTION EN.
NUhEG/CR 5936 ENHANCEMENTS TO THE ACCIDENT PRECUR-GINEERING AND BABCOCK & WILCOX CONTROL ROD DRIVES SOR METHODOLOGY-NUREG/CR-5964 SAPHIRE TECHNICAL REFERENCE NUREG/CR-5844 AGING ASSESSMENT OF BISTABLES AND SWITCHES IN NUCLEAR POWER PLANTS.
MANUAL:lRRAS/ SARA VERSION 4 0 NUREG/CR-5851 LONG TERM PERFORMANCE AND AG!NG CHAR.
DIVISION OF SYSTEMS RESEARCH (POST 880717)
ACTERISTICS OF NUCLEAR PLANT PRESSURE TRANSMITTERS NUREG/CR-5818 UNCERTAINTY ANALYSIS OF MINIMUM VESSEL NUREG/CR 5903 VALtDATION OF SMART SENSOR TECHNOL.
LIQUID INVENTORY DURING A SMALL-BREAK LOCA IN A B&W OGIES FOR INSTRUMENT CAllBRATION REDUCTION IN NUCLE.
PLANT AN APPLICATION OF THE CSAU METHODOLOGY USING AR POWER PLANTS THE RELAP5/ MOD 3 COMPUTER CODE.
NUREG/CR-5914 CHEMICAL COMPOSIT!ON AND RT(NDT) DETER.
NUREG/CR-5922. MODULAR HIGH-TEMPERATURE GAS-COOLED M! NATIONS FOR MIDLAND WELD WF-70.
REACTOR SHORT TERM THERMAL RESPONSE TO FLOW AND i
NUREG/CR-5926-SANS INVESTIGATION OF LOW ALLOY STEELS REACTIVITY TRANSlENTS.
IN NEUTRON IRRADIATED, ANNEALED, AND REIRRADIATED NUREG/CR 5951: THE MANAGEMENT OF ATWS BY BORON INJEC-CONDITIONS TION NUREG/CR-5952 EVALUATION OF CRACK POP-INS AND THE DE-NUREG/CR-5977: A PERFORMANCE INDICATOR OF THE EFFEC-TERM l NATION Or THEIR RELEVANCE TO DESIGN CONSIDER-TlVENESS OF HUMAN-MACHINE INTERFACES FOR NUCLEAR ATIONS POWER PLANTS NUREG/CR-5958 TWO-PARAMETE R FRACTURE MECHANICS.
THEORY AND APPLICATIONS EDO OFFICE OF NUCLEAR REACTOR REGULATION (POST 800428)
NUREG/CR-5961. POSTTEST DESTRUCTIVE EXAMINATION OF THE PROGRAM MANAGEMENT, POLICY DEVE LOPMENT & ANALYSIS STEEL LINER IN A 16-SCALE REACTOR CONTAINMENT MODEL.
ST AFF (POST 870411)
NUREG/CR-59BB SOIL CHARACTER!ZATION METHODS FOR UN-NUREG/CR 5973 CODES AND STANDARDS AND OTHER GUID-SATURATED LOW-LEVEL WASTE SITES ANCE CITED IN REGULATORY DOCUMENTS NUREG/CR-6011. REVIEW OF STRUCTURE DAMPING VALUES FOR NUREG/CR-5975 INCENTIVE REGULATION OF INVESTOR-OWNED ELASTIC SEISMIC ANALYSIS OF NUCLEAR POWER PLANTS NUCLEAP.,')WER PLANTS BY PUBLIC UTILITY REGULATORS l
33 l
34 NRC Contract Sponsor Index DIVISION OF SYSTEMS SAFETY & ANALYSIS (POST 921004)
NUREG/CR 589b AUXILLARY F EEDWATER SYSTEM RISK-BASED NUREC'CR 5488 RISK-BASED INSPECTION GUIDE FOR THREE INSPECTION GUIDE FOR THE POINT BE ACH NUCLF AR POWER MILE ISLAND NUCLE AR STATION UNIT 1 PLANT NUREG/CR-5766 AUXILIARY FEEDWATER SYSTEM RISK-BASED NUREG/CR 5933 HIGH PRESSURE COOLANT INJE'CTION (HPC!}
INSPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR SYSTEM RISK-BASED INSPECTION GUIDE FOR DRESDEN NU-POWER PLANT.
CLEAR POWER STAFION UNITS 2 AND 3 NUREG/CR-5834 AUXILIARY FEEDWATER SYSTEM RISK-BASED NUREG/CR 5934. HIGH PRESSURE COOLANT INJECTION (HPCl)
INSPECTION GUIDE FOR THE FORT CALHOUN NUCLEAR SYSTEM RISK BASED INSPECTION GUIDE FOR OUAD-CITIES POWER PL ANT.
STATION. UNITS 1 AND 2 NUREGICR-5835 AUXILIARY FEEDWATER SYSTEM RISK-BASED NUREG/CR 5959 HIGH PRESSURE COOLANT INJECTION (HPCI)
INSPECTION GUIDE FOR THE BEAVER VALLEY UNITS 1 AND 2 SfSTEM RISK-BASED INSPECTION GUIDE FOR ENRICO F ERMI NUCLEAR POWER PLANTS-ATOMIC POWER PLANT. UNIT 2.
NUREG/CR'5836 AUXILIARY FEEDWATER SYSTEM RISK, BASED DIVISION OF ENGINEERING (POST 921004)
INSPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWER NUREG/CR 5956 CONSIDERATION OF UNCERTAINTIES IN SOfL-PLANT.
STRUCTURE INTERACTION COMPUT ATIONS i
s.
a i
4 l
\\
Contractor index This index lists, in alphabetical order, the contractors that prepared the NUREG/CR reports listed in this compilation. Listed below each contractor are the NUREG/CR numbers and titles of their reports. If further information is needed, refer to the main citation by the j
NUREG/CR number.
ADVANCED SYSTEML TECHNOLOGY, lNC, NUREG/CR-5BB3. HEALTH RISK ASSESSMENT OF IRRADIATED NUREG/CR 5962. HEALTH AND SAFETY IMPACTS FROM DISCRETE TOPAZ.
SOURCES OF NATURALLY.OCCURRlNG AND ACCELERATOR PRO.
NUREG/CR-5911 SOURCE TERM EVALUATION FOR RADIOACTIVE DUCED RADIOACTIVE MATER:ALS (NARM)
LOW-LEVEL WASTE DISPOSAL PERFORMANCE ASSESSMENT.
NUREG/CR 5933' HIGH PRESSURE COOLANT INJECTION (HPCI)
ANALYSIS & MEASUREMENT SEPVICES CORP.
SYSTEM RISK-BASED INSPECTION GUIDE FOR DRESDEN NUCLE-NUREGICR-5851. LONG TERM PERFORMANCE AND AGING CHAR.
AR POWER STATION UNITS 2 AND 3 l
ACTERISTICS OF NUCLEAR PLANT PRESSURE TRANSMITTERS-NUREG/CR-5934: HIGH PRESSURE COOLANT INJECTION (HPCI)
NUREG/CR-5903 VALIDATION OF SMART SENSOR TECHNOLOGIES SYSTEM RISK-BASED INSPECTION GUIDE FOR QUAD-CITIES FOR INST RUMENT CAllBRATION REDUCTION IN NUCLEAR STATION. UNITS 1 AND 2.
POWER PLANTS' NUREG/CR-5959. HIGH PRESSURE COOLANT INJECTION (HPCI) 1 SYSTEM RISK-BASED INSPECTION GUIDE FOR ENRICO FERMI ANALYTIC & COMPUTIONAL RESEARCH,INC.
NUREG/CR-5991: PORFLOW A MULTIFLUlO MULTIPHASE MODEL ATOMIC POWER PLANT, UNIT 2, FOR SIMULATING FLOW. HEAT TRANSFER, AND MASS TRANS-BROWN UNIV. PROVIDENCE RI T IN FRACTURED POROUS MEDIA. User's Manual Version NUREG/CRd958 TWO PARAMETER FRACTURE MECHANICS.
THEORY AND APPLICATIONS.
i ARGONNE NATIONAL LABORATORY NUREG/CR-5822: ANALYSIS OF THERMAL MIXING AND BORON Dl_
CALIFORNIA INSTITUTE OF TECHNOLOGY, PASADENA, CA LUTION IN A PWR.
NUREG/CR-6012. STIFFNESS AND DAMPING PROPERTIES OF A i
LOW ASPECT RATIO SHEAR WALL BUILDING BASED ON RECORD-ARIZON A, UNIV. OF, TUCSON, AZ ED EARTHOUAKE RESPONSES.
NUREG/CR 5988 SOIL CHARACTERIZATION METHODS FOR UN-SATURATED LOW-LEVEL WASTE SITES.
CALIFORNI A, UNIV. OF, BERKELEY, C A NUREG/CR 5980: THREE DIMENSIONAL REDISTRIBUTION OF TRITI-BATTELLE MEMORIAL INSTITUTE. PACIFIC NORTHWEST UM FROM A POINT OF RELEASE INTO A UNIFORM UNSATURATED LABORATORY SOIL.A Deterministic Model For Tntium Migration in An Arid Disposal NUREG/CR-2850 VII: DOSE COMMITMENTS DUE TO RADIOACTIVE Sete.
RELE ASES FROM NUCLE AR POWER PLANT SITES IN 1969 NUREG/CR-5247 VOI R1 RASCAL VERSION 2 0 USER'S GUIDE-CALIFORNIA, UNIV. OF, SANTA BARBARA, CA NUREG/CR 5468. RISK-BASED INSPECTION GUIDE FOR THREE MILE NUREG/CR-5951: THE MANAGEMENT OF ATWS BY BORON INJEC-ISLAND NUCLEAR STATION UNIT 1.
NUREG/CR 5766-AUXILIARY FEEDWATER SYSTEM RISK-BASED IN-SPECTION GUIDE FOR THE SAN ONOFRE UNIT 2 NUCLEAR CENTER FOR NUCLEAR WASTE REGULATORY ANALYSES NUREG/CR-5917 V01. SENSITIVITY AND UNCERTAINTY ANALYSES NU E /A5 4 AUXtLIARY FEEDWATER SYSTEM RISK-BASED IN-APPLIED TO ONE-DIMENSIONAL RADIONUCLIDE TRANSPORT IN A l
SPECTION GUIDE FOR THE FORT CALHOUN NUCLEAR POWER PLANT.
LAYERED FRACTURED ROCKMULTFRAC - Analytic Solutions And l
NUREG/CR 5835 AUXILIARY FEEDWATER SYSTEM RISK-BASED IN.
Local Sensitmties.
l SPECTION GUIDE FOR THE BEAVER VALLEY.UNFS 1 AND 2 NU-NUREG/CR-5917 V02. SENSITIVITY AND UNCERTAINTY ANALYSES I
CLEAR POWER PLANTS APPLIED TO ONE-OlMENSIONAL RADIONUCLIDE TRANSPORT IN A NUREG/CR-5836 AUXlLIARY FEEDWATER SYSTEM RISK-BASED IN.
LAYERED FRACTURED ROCK Evaluation Of The Lmt State Ap-SPECTION GUIDE FOR THE PALO VERDE NUCLEAR POWER proach PLANT.
NUREG/CR 5991. PORFLOW A MULTIFLUID MULTIPHASE MODEL NUREG/CR-5898 AUXILIARY FEEDWATER SYSTEM RISK BASED IN-FOR SIMULATING FLOW. HEAT TRANSFER, AND MASS TRANS-SPECTION GUIDE FOR THE POINT BEACH NUCLEAR POWER PORT IN FRACTURED POROUS MEDIA User's Manual - Version PLANT 2.41.
NUREG/CR-5973 CODES AND STANDARDS AND OTHER GUIDANCE CITED IN REGULATORY DOCUMENTS CITY COLLEGE OF NEW YORK, NEW YORK, NY NUREG/CR-5975. INCENTIVE REGULATION OF INVESTOR-OWNED NUREG/CR-5356. CONSIDERATION OF UNCERTAINTIES IN SOIL-NUCLF AA DWR PLANTS Pi PUBLIC UTILITY REGULATORS STRUCTURE INTERACTION COMPUTATIONS.
NURES/CR-59BB. DL CH'AACTERIZATION METHODS FOR UN-r SATURATFD LOW LEVEL WASTE SITES EG&G IDAHO, INC, i
NUREG/CRM96. SUBSURFACE INJECTION OF RADIOACTIVE NUREG/CR-5229 V05 FIELD LYSIMETER INVESTIGATIONS: LOW-A EDYL3W AND NON-N E /CR 599 5 OL7 TION O A
A BE KVNM RNW W US
^L
^
9^
REACTIVE SOLUTE TRANSPORT IN A HETEROGENEOUS SOIL AT NU EG/C 6 2 V03 ARA RlSTICS OF LOW-LEVEL RADIOAC-THE FIELD SCALE-TlVE DECONTAMINATION WASTE Annual Report For Fiscal Year EROOKHAVEN NATIONAL LABORATORY 1992.
NUREG/CR 5818. UNCERTAINTY ANALYSIS OF MINIMUM VESSEL NUREG/CR-4551 V7R1P1: EVALUATION OF SEVERE ACCIDENT LIQUID INVENTORY DURING A SMALL-BREAK LOCA IN A D8W RISKS ZION UNIT 1 Main Report NUREG/CR-4551V7R1P2A; EVALUATION OF SEVERE ACCIDENT PLANT AN A? PLICATION OF THE CSAU METHODOLOGY USING RISKS: ZION UNIT 1. Appenda A.
THE RELAPS/ MOD 3 COMPUTER CODE.
NUREG/CR 4551V7R1P2B: EVALUATION OF SEVERE ACCIDENT NUREG/CR 5953: STUDIES OF HUMAN PERFORMANCE DURING OP-RISKS ZION UNIT 1. Appendices B C, D. And E.
ERATING EVENTS 1990 1992.
NUREG/CR-5783 AGING ASSESSMENT OF THE COMBUSTION ENGI-NUREG/CR 5964 SAPHIRE TECHNICAL REFERENCE NEERING AND BABCOCK & WILCOX CONTROL ROD DRIVES MANUAllRRAS/SAR A VERSION 4 0.
NUREG/CR-5844: AGING ASSESSMENT OF BISTABLES AND NUREG/CR 5907 MICROBIAL-INFLUENCED CEMENT DEGRADATION SWITCHES IN NUCLEAR POWER PLANTS.
- LITERATURE REVIEW 35
36 Contractor index EOE ENGINEERING CONSULTANTS (FORMERLY EOE ENGINEERING.
NEW ME XICO ST ATE UNIV., LAS CRUCES. NM INC.)
NUREG/CR 59% SOIL CH AR ACT E Rl2ATION METHODS FOR UN-NUREG<CR 6011. REVIEW OF S1RUCTURE DAMHNG % ALUt.S f Oh SATURATED LOW L EVEL WASTE SITL S E L ASilC SE ISMIC ANALYSIS OF NUCLE AR POWER PLANTS NEW MEXICO. UNIV. 0F, ALBUQUEROUE. NM NUREG/CR 6012 STlFF NESS AND DAMPING PROPERTIES OF A NUREG/CR 5755 STIF FNESS Of LOW-ASPECT RATIO. REINFORCE D LOW ASPECT RATIO SHE AR WALL BUILDING BASE D ON RE CORD, CONCRE TE SHEAR WALLS ED E ARTHOUANE RESPONSES OAK RIDGE NATIONAL LABORATORY ILLINOIS, UNIV. OF, URB AN A. IL NUREG/CR 5247 V01 R t RASCAL VERSION 2 0 USER S GUIDE NUREG/CR 5977 A PERFORMANCE INDICATOR OF THE EFFECTIVE-NUREG/CR 5699 VO1-AGING AND SERVICE WE AR OF CONT ROL NE SS OF HUMAN MACHINE INTE RF AGES FOR NUCL E AR POWER ROD DRIVE MECHANISMS FOR BWR NUCLE AR PLANTS PLANTS NUREG/CR 5914 CHEMICAL COMPDSITION AND RT(NOT) DETE RMI-NATIONS FOR MtDL AND WELD WF-70 IMPERIAL COLLEGE, LONDON, UK NURE G/CR 5922 MODULAR HIGH-TEMPERATURE GAS-COOLED RE.
NUREG TR 5950 T WO-PARAME T E R FRACTURE MECHANICS ACTOR SHORT. TERM THERMAL RESPONSE TO FLOW AND RE AC-THEORY AND APPLICATIONS TlVITY TRANSIENTS NUREG/CR-5938 NATIONAL PROFILE ON COMME RCIALLY GE NER-ATED LOW 1EVEL RADIOACTIVE mixed WASTE INSTITUTE FOR MATERIALS RESEARCH NURE G/CR 5952 EVALUATION OF CRACK POP-INS AND THE DE-NUREG/CR 5926 SANS fNVEST!GATION OF LOW ALLOY STEELS IN TE RMINATION OF T HEIR RELEVANCE TO DESIGN CONSIDER-NEUTRON 1RRADIATED. ANNE ALED, AND REIRRADIATED CONDI ATIONS TIONS PHOENIX ASSOCIATES. INC.
NUR G CR CRA PROPAGATION IN HIGH STRAIN REGIONS OF SEQUOYAH CONTA!NME NT SANDIA NATIONAL LABORATORIES NUREG/CR-5791. RISK EVALUATION FOR A GENERAL ELECTRIC KAISER ENGINEERWG (FORMERLY K AISER ENGINEERS)
BWR, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON NURE G/CR 6007: 5 TRESS ANALYSIS OF CLOSURE BOLTS FOR SAFETY.RELATED EQUIPME NT Evaluaton Of Genenc lssue 57 SHtPPING CASKS NUREG/CR 5603 RISK ASSESSMENT OF ISOLATION DEVICES IN SAFETY SYSTEMS LAWRENCE LIVERMORE NATIONAL LABORA FORY NUREG/CR 5936 ENHANCEMENTS TO THE ACCIDENT PRECURSOR NUREG<CR 6007 STRESS ANALYS!S OF CLOSURE BOLTS FOR METHODOL OGY NUREG/CR-5961. POSTTEST DESTRUCTIVE EXAM; NATION OF THE SHIPPING CASKS STEEL LINE R IN A 16. SCALE REACTOR CONTAINMENT MODEL LOS ALAMOS NATIONAL LABORATORY jgfg,'CR S 9 OR' A GENERAL ELECTRIC N
SS OF LOWASPECT RATIO, REINFORCED R Sk EVALU i>
C T HE S
BWR. EFFECTS OF FIRE' PROTECTION SYSTEM ACTUATION ON SAF ETY-RELATED EQUIPMENT. Evaluation Of Genenc issue 57 MATERIALS ENGINEERING ASSOCIATES. INC.
NURE G/CR4026 SANS INVESTIGATION OF LOW ALLOf STEELS IN SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY PCUTRON IRRADIATED. ANNEALED. AND REIRRADtATED CONDI-SCIENCE APPLICATIONS.
TIONa NUREG-0713 V12 OCCUPATIONAL RADIATION EXPOSURE AT COM-ME ACI AL NUCLEAR POWER REACTORS AND OTHER MORATUWA. UN!V. OF, SRI LANKA
^
NUREG'CR 5951 THE MANAGEMENT OF ATWS BY BORON INJEC.
NURE /
863 S
ES E"I T F SOLATION DEVICES IN TION SAFETY SYSTEMS NAVY. DEPT.OF VIKING SYSTEMS INTERNATIONAL NUREG/CR 5356 TWO-P AR AMETE R FRACTURE MECHANICS NUREG/CR 5956 CONSIDERATION OF UNCERTAINTIES IN SOll-THEORY AND APPLICATIONS STRUCTURE INTERACTION COMPUT ATIONS l
J l
9
international Organization index This index lists, in alphabetical order, the countries and performing organizations that pre-pared the NUREG/lA reports listed in this compilation. Listed below each country and per-forming organization are the NUREG/lA numbers and titles of their reports. If further infor-mation is needed, refer to the main citation by the NUREG/lA number.,
There were no NUREG/lA reports for this quarter.
37
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1 Licensed Facility Index This index lists the facilities that were the subject of NRC staff or contractor reports. The facility names are arranged in alphabetical order. They are preceded by their Docket number and followed by the report number. If further information is needed, refer to the main citation by the NUREG number.
50 334 Beaw, Valley Power Statort Ur* 1. Ducuesne NUREG/CR 5835 50 266 Pomt Beach Nxkw Plant, Umt t. Wisconsm NUREG'CR4836 Ugnt Co Eectre Power Co.
W412 Beaver Valley Peeer St ton Urut 2. Ducuesre NUREG/CR 5835 50 301 Pomt Beach Nuclear Plant Umt 2. W&onsm NUREG/CR 5896 Lght Cc.
Electnc Power Co
% 446 ComarrJe Peak Steam Ekekc Statm Umt 2.
NUREG479? S26
% 254 QuadCties Statm Unt 1. Commonwealth NOREGJCR 5934 Texas utstes E ecir Edson Co 50 237 Dresoen Nuclear Power Statm Umt 2.
NUREG/CR 5933 E265 Ouad-Cdes Suten, Umt 2. Cormnonweam UEG'CR 5934
% 361 San m Stam W 2, hn METCR SM 50-249 Dresden s wer S ort Urnt 3.
NUREGICR 5933 327 W 1. Tewssee WW273 W34 t Enr At Fower Plant, Umt 2. Debi NUREGICH-5959 40 8969 E
e of Utat inc.. Salt take Cdv UT.
NUREu-1476 y
50 2e5 Fort Calhoun Stabon. Umt 1. Omaha P2hc NUREGICA 5834 50-289 Three Mae Nucmar Staten. Umt 1.
NUREG/CR 5486 b MCI GenetW Put:hc Uthhes SN5529 Pac Vera Nuclear Statm Urd 1. Anzona NUREG/CR 5836 50-295 Zon Nuciear Power Slabort Und 1, NUREG/CR-4551 V7R1P1 PR Secree Co.
Commonweatih Esson Co.
STNM529 Fala verde Nucler Stalm Unt 2. A.'2cna NUREG/CR 5836 50-295 Zon Nuclear Power Statm UM 1.
NUREG!CR-4551V7R f P2A Phc Servce Co Commonwealth Edson Co.
STN 50-530 Pac verde Nuclear Statm Umt 3, Anzona NUREGICR-5836 50 295 Zon Nutbar Power Stanon, Und I, NUREG/CR-4551V7 RIP 28 P@c Sentce Co Commonwealth Esson Co 39
NRC FORM 335 U S. NUCLEAR REGULATORY COMMISSION
- 1. REPORT NUMBE R (2 89)
( Assamed by NRC, Add Vol.,
NRCM 1 t02, Supp. Rev., and Addendum Num-m. 3202 BIBLIOGRAPHIC DATA SHEET be' ' ' " *"Y - )
(See instrveiions on the reverse)
N UR EG--0304 2 itTLE AND SUB RTLE
- 3. DAT E RI Poli f PUCLINlED Regulatory and Technical Reports (Abstract Index. Journal)
PAONTH YEAR Compilation for May 1993 17irst Quarter 1993
- 4. RN OR GRANT NUMBER January-March
- b. Au l MvH p)
- 6. T YPE OF REPOHI Reference
- 7. PERIOD COvtRED (inclusive Dates)
January-March 1993 8 PEHFORMING ORGANIZATION - NAME AND ADDHESS Uf NRC, provide Dmseon, Office or Regkm, U.S. Nuclear Regulatory Commission, and mailing address; :f contractor, provH:2e name and maeling address )
Division of Freedom of Information and Publications Services j
Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555
- 9. SPONSORING ORGANIZATION - NAME AND ADDRESS Of NRC type "Same as above"; if contractor, provide NRC Dmsiori, Of 5ce or Region.
U S Nuclear Regulatory Commission, and mailing address.)
Same as 8, above.
10 SUPPLEMENT ARY NOT ES 11, ABSTHACT (200 words or ness)
This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceed.
ings of conferences and workshops; as well as international agreement reports. The entrics in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, ccmtractor, international organization, and licensed facility.
1 l
l 13 AVAILABILITY ST ATEMENT
- 12. KEY WOriDS'DESCRPTORS (List words or phrases that will assist researchets in locating the report.)
Unlimited
- 14. Si:CURITY CLASSlFICATION compilation g i,,,,,
abstract index Unclassified (T ha licport)
Unclassified
- 15. NUMUE R OF PAGES
- 16. PHICE l
NRC FORM 335 (2-89)
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